192 Federal Register / Vol. 61, No. 2 / Wednesday, January 3, 1996 / Notices

Evaluation dated December 11, 1995.No

significant hazards consideration

comments received: None

Local Public Document Room

location: Chattanooga-Hamilton County

Library, 1101 Broad Street, Chattanooga,

Tennessee 37402No significant hazards

consideration comments received: None

TU Electric Company, Docket Nos. 50-

445 and 50-446, Comanche Peak Steam

Electric Station, Unit Nos. 1 and 2,

Somervell County, Texas

Date of amendment request: August

15, 1995 (TXX-95215)

Brief description of amendments:

These changes relocated the Shutdown

Margin limits from the Technical

Specifications (TSs) to the Core

Operating Limits Report (COLR). The

changes were consistent with the intent

of Generic Letter 88-16 which provides

guidelines for the removal of cyclespecific parameter limits from the TSs.

Date of issuance: December 15, 1995

Effective date: December 15, 1995

Amendment Nos.: Unit 1 -

Amendment No. 44; Unit 2 -

Amendment No. 30

Facility Operating License Nos. NPF87 and NPF-89. The amendments

revised the Technical Specifications.

Date of initial notice in Federal

Register: October 11, 1995 (60 FR

52935) The Commission’s related

evaluation of the amendments is

contained in a Safety Evaluation dated

December 15, 1995.No significant

hazards consideration comments

received: No

Local Public Document Room

Location: University of Texas at

Arlington Library, Government

Publications/Maps, 702 College, P.O.

Box 19497, Arlington, TX 76019

Union Electric Company, Docket No.

50-483, Callaway Plant, Callaway

County, Missouri

Date of amendment request: April 26,

1995

Brief description of amendment: The

amendment revises Technical

Specification (TS) 3/4.7.6 to reduce the

upper limit on the flow rate through the

control room filtration subsystem and

adopts ASTM D-3803-1989 as the

laboratory testing standard for control

room filtration and control building

pressurization charcoal adsorber. The

amendment also revises the Bases for TS

3/4.7.6 to reflect the changes.

Date of issuance: December 20, 1995

Effective date: December 20, 1995, to

be implemented within 30 days from

the date of issuance.

Amendment No.: 106

Facility Operating License No. NPF30. The amendment revised the

Technical Specifications.

Date of initial notice in Federal

Register: May 23, 1995 (60 FR 27345)

The Commission’s related evaluation of

the amendment is contained in a Safety

Evaluation dated December 20, 1995.No

significant hazards consideration

comments received: No.

Local Public Document Room

location: Callaway County Public

Library, 710 Court Street, Fulton,

Missouri 65251.

Wolf Creek Nuclear Operating

Corporation, Docket No. 50-482, Wolf

Creek Generating Station, Coffey

County, Kansas

Date of amendment request: June 14,

1995, as supplemented by letters dated

July 13, 1995, and August 22,

1995.I11Brief description of

amendment: The amendment revises

Technical Specification (TS) 3.2.3,

‘‘Nuclear Enthalpy Rise Hot Channel

Factor,’’ TS 6.9.1.9, ‘‘Core Operating

Limits Report,’’ and the associated Bases

sections. The revisions incorporate

changes associated with the planned

implementation of advanced nuclear

and core thermal-hydraulic design

methodologies licensed from

Westinghouse Electric Corporation for

core reload design, starting with Cycle

9.

Date of issuance: December 8, 1995

Effective date: December 8, 1995, to

be implemented prior to restart from the

eighth refueling outage, which is

scheduled to begin in March 1996.

Amendment No.: 92

Facility Operating License No. NPF42. The amendment revised the

Technical Specifications.

Date of initial notice in Federal

Register: August 2, 1995 (60 FR 39456)

The August 22, 1995, supplemental

letter forwarded the nonproprietary

version of Wolf Creek Nuclear Operating

Corporation’s safety evaluation and

analysis provided in the June 14, 1995,

submittal and did not change the staff’s

original no significant hazards

determination.The Commission’s

related evaluation of the amendment is

contained in a Safety Evaluation dated

December 8, 1995.No significant

hazards consideration comments

received: No.

Local Public Document Room

locations: Emporia State University,

William Allen White Library, 1200

Commercial Street, Emporia, Kansas

66801 and Washburn University School

of Law Library, Topeka, Kansas 66621

Wolf Creek Nuclear Operating

Corporation, Docket No. 50-482, Wolf

Creek Generating Station, Coffey

County, Kansas

Date of amendment request: August

22, 1995

Brief description of amendment: The

amendment revises the requirements of

Technical Specification (TS) 3.3.1 and

TS 3.3.2 and relocate Tables 3.3-2 and

3.3-5 and applicable Bases, which

provide the response time limits for the

reactor trip system (RTS) and the

engineered safety features actuation

system (ESFAS) instruments, from the

TS to the Updated Safety Analysis

Report (USAR). The licensee has stated

that the next USAR change request will

include these changes.

Date of issuance: December 12, 1995

Effective date: December 12, 1995, to

be implemented within 60 days of

issuance.

Amendment No.: 93

Facility Operating License No. NPF42. The amendment revised the

Technical Specifications.

Date of initial notice in Federal

Register: September 27, 1995 (60 FR

49950) The Commission’s related

evaluation of the amendment is

contained in a Safety Evaluation dated

December 12, 1995.No significant

hazards consideration comments

received: No.

Local Public Document Room

locations: Emporia State University,

William Allen White Library, 1200

Commercial Street, Emporia, Kansas

66801 and Washburn University School

of Law Library, Topeka, Kansas 66621

Dated at Rockville, Maryland, this

21st Day of December 1995.

For the Nuclear Regulatory Commission

Steven A. Varga,

Director, Division of Reactor Projects - I/II

Office of Nuclear Reactor Regulation

[Doc. 96–1 Filed 1–2–96; 8:45 am]

BILLING CODE 7590–O1–F

[Docket Nos. 50–295 and 50–304]

Commonwealth Edison Company,

(Zion Nuclear Power Station, Unit Nos.

1 and 2); Exemption

I

The Commonwealth Edison Company

(ComEd, the licensee) is the holder of

Facility Operating License Nos. DPR–39

and DPR–48, which authorize operation

of the Zion Nuclear Power Station,

Units 1 and 2 (the facilities). The

licenses provide, among other things,

that the facilities are subject to all the

rules, regulations, and orders of the U.S.

Nuclear Regulatory Commission (the

Commission) now or hereafter in effect.
Federal Register / Vol. 61, No. 2 / Wednesday, January 3, 1996 / Notices 193

The facilities are pressurized water

reactors located at the licensee’s site in

Lake County, Illinois.

II

In 10 CFR 73.55, ‘‘Requirements for

Physical Protection of Licensed

Activities in Nuclear Power Reactors

Against Radiological Sabotage,’’

paragraph (a), in part, states that ‘‘the

licensee shall establish and maintain an

onsite physical protection system and

security organization which will have as

its objective to provide high assurance

that activities involving special nuclear

material are not inimical to the common

defense and security and do not

constitute an unreasonable risk to the

public health and safety.’’

In 10 CFR 73.55(d), ‘‘Access

Requirements,’’ paragraph (1), it

specifies that ‘‘the licensee shall control

all points of personnel and vehicle

access into a protected area.’’ Also, 10

CFR 73.55(d)(5) requires that ‘‘A

numbered picture badge identification

system shall be used for all individuals

who are authorized access to protected

areas without escort.’’ It further states

that individuals not employed by the

licensee (e.g., contractors) may be

authorized access to protected areas

without escort provided that the

individual, ‘‘receives a picture badge

upon entrance into a protected area

which must be returned upon exit from

the protected area * * *.’’

The licensee proposes to implement

an alternative unescorted access system

which would eliminate the need to

issue and retrieve picture badges at the

entrance/exit location to the protected

area and would allow all individuals,

including contractors, to keep their

picture badges in their possession when

departing Zion Station.

III

Pursuant to 10 CFR 73.5, ‘‘Specific

exemptions,’’ the Commission may,

upon application of any interested

person or upon its own initiative, grant

such exemptions from the requirements

of the regulations in this part as it

determines are authorized by law and

will not endanger life or property or the

common defense and security, and are

otherwise in the public interest.

According to 10 CFR 73.55, the

Commission may authorize a licensee to

provide alternative measures for

protection against radiological sabotage

provided the licensee demonstrates that

the alternative measures have the same

‘‘high assurance’’ objective, that the

proposed measures meet the general

performance requirements of the

regulation, and that the overall level of

system performance provides protection

against radiological sabotage equivalent

to that which would be provided by the

regulation.

Currently, unescorted access into the

protected area for both employee and

contractor personnel into Zion Station,

Units 1 and 2, is controlled through the

use of picture badges. Positive

identification of personnel which are

authorized and request access into the

protected area is established by security

personnel making a visual comparison

of the individual requesting access and

that individual’s picture badge. In

accordance with 10 CFR 73.55(d)(5),

contractor personnel are not allowed to

take their picture badges off site. In

addition, in accordance with the plant’s

physical security plan, the licensee’s

employees are also not allowed to take

their picture badges off site.

The proposed system will require that

all individuals with authorized

unescorted access have the physical

characteristics of their hand (hand

geometry) registered with their picture

badge number in a computerized access

control system. Therefore, all authorized

individuals must not only have their

picture badge to gain access to the

protected area, but must also have their

hand geometry confirmed. All

individuals, including contractors, who

have authorized unescorted access into

the protected area will be allowed to

keep their picture badges in their

possession when departing the Zion

Station.

All other access processes, including

search function capability and access

revocation, will remain the same. A

security officer responsible for access

control will continue to be positioned

within a bullet-resistant structure. It

should also be noted that the proposed

system is only for individuals with

authorized unescorted access and will

not be used for those individuals

requiring escorts.

Sandia National Laboratories

conducted testing which demonstrated

that the hand geometry equipment

possesses strong performance

characteristics. Details of the testing

performed are in the Sandia report, ‘‘A

Performance Evaluation of Biometric

Identification Devices,’’ SAND91—0276

UC—906 Unlimited Release, June 1991.

Based on the Sandia report and the

licensee’s experience using the current

photo picture identification system, the

false acceptance rate for the proposed

hand geometry system would be at least

equivalent to that of the current system.

To assure that the proposed system will

continue to meet the general

performance requirements of 10 CFR

73.55(d)(5), the licensee will implement

a process for testing the system. The site

security plans will also be revised to

allow implementation of the hand

geometry system and to allow

employees and contractors with

unescorted access to keep their picture

badges in their possession when leaving

Zion Station.

IV

For the foregoing reasons, the NRC

staff has determined that the proposed

alternative measures for protection

against radiological sabotage meet the

same high assurance objective and the

general performance requirements of 10

CFR 73.55. In addition, the staff has

determined that the overall level of the

proposed system’s performance will

provide protection against radiological

sabotage equivalent to that which is

provided by the current system in

accordance with 10 CFR 73.55.

Accordingly, the Commission has

determined that, pursuant to 10 CFR

73.5, this exemption is authorized by

law, will not endanger life or property

or common defense and security, and is

otherwise in the public interest.

Therefore, the Commission hereby

grants the following exemption:

The requirement of 10 CFR 73.55(d)(5) that

individuals who have been granted

unescorted access and are not employed by

the licensee are to return their picture badges

upon exit from the protected area is no longer

necessary. Thus, these individuals may keep

their picture badges in their possession upon

leaving Zion Nuclear Power Station.

Pursuant to 10 CFR 51.32, the

Commission has determined that the

granting of this exemption will not

result in any significant adverse

environmental impact (60 FR 66566).

Dated at Rockville, Maryland, this 26th day

of December 26, 1995.

For the Nuclear Regulatory Commission.

Gail Marcus,

Acting Director, Division of Reactor Projects—

III/IV, Office of Nuclear Reactor Regulation.

[FR Doc. 96–00042 Filed 1–2–96; 8:45 am]

BILLING CODE 7590–01–P

[IA 95–061]

Gary A. Minnick; Order Prohibiting

Involvement in NRC-Licensed

Activities

I

On various dates in 1992 and 1993,

Gary A. Minnick was employed by

various contractors to perform rigging

and scaffolding work at nuclear power

plants licensed by the Nuclear

Regulatory Commission (NRC or

Commission), including Palo Verde,

Beaver Valley, and North Anna. In each

case, Mr. Minnick was granted