Federal Register / Vol. 62, No. 39 / Thursday, February 27, 1997 / Notices 9001

the Federal Register on November 27,

1995 (60 FR 58402). However, by letter

dated February 4, 1997, the licensee

withdrew the proposed change.

For further details with respect to this

action, see the application for

amendment dated October 24, 1995, as

supplemented March 7, 1996, and the

licensee’s letter dated February 4, 1997,

which withdrew the application for

license amendment. The above

documents 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 Learning Resources

Center, Three Rivers CommunityTechnical College, 574 New London

Turnpike, Norwich, Connecticut, and

the Waterford Library, ATTN: Vince

Juliano, 49 Rope Ferry Road, Waterford,

Connecticut.

Dated at Rockville, Maryland, this 19th day

of February 1997.

For the Nuclear Regulatory Commission.

Daniel G. McDonald,

Senior Project Manager Special Projects

Office—Licensing Office of Nuclear Reactor

Regulation.

[FR Doc. 97–4856 Filed 2–26–97; 8:45 am]

BILLING CODE 7590–01–P

Northeast Utilities; Notice of Document

Availability and Public Meeting

On January 31, 1997, the U.S. Nuclear

Regulatory Commission (NRC) received

from Northeast Nuclear Energy

Company (NNECO), the licensee for the

Millstone Nuclear Power Station, its

comprehensive plan for resolving

employee safety concerns. The plan is

in response to an NRC Order. On

October 24, 1996, the Director of the

Office of Nuclear Reactor Regulation

sent an Order to NNECO requiring: (1)

A comprehensive plan for resolving the

Millstone station employees’ safety

concerns; and (2) an independent thirdparty oversight of NNECO’s

implementation of this plan. Copies of

NNECO’s Comprehensive Plan

pertaining to the employee safety

concerns program are available at the

Waterford Public Library, ATTN: Mr.

Vincent Juliano, 49 Rope Ferry Road,

Waterford, Connecticut, and the

Learning Resources Center, Three Rivers

Community-Technical College, 574 New

London Turnpike, Norwich,

Connecticut.

The NRC will hold a public meeting

regarding the comprehensive plan for

resolving the Millstone station

employees’ safety concerns. The

meeting will be held in the near future

at the Waterford Town Hall in

Waterford, Connecticut. The meeting

will be open to public attendance and

will be transcribed. The NRC has

elected to hold such a public meeting

because of the public’s interest.

The structure of the public meeting

shall be as follows:

NRC opening remarks

Members of the public comments and

questions

NRC closing remarks

Meeting concludes

The purpose of this public meeting is

to obtain comments from members of

the public for NRC staff use in

evaluating NNECO’s comprehensive

plan addressing employee safety

concerns. The staff will not offer any

preliminary views on its evaluation of

the comprehensive plan. The public

meeting will be chaired by a senior NRC

official who will limit presentations to

the above subject.

A meeting notice will be issued

stating the date and time of the meeting.

Dated at Rockville, Maryland, this 19th day

of February 1997.

For the Nuclear Regulatory Commission.

Helen N. Pastis,

Senior Project Manager, Special Projects

Office—Licensing, Office of Nuclear Reactor

Regulation.

[FR Doc. 97–4854 Filed 2–26–97; 8:45 am]

BILLING CODE 7590–01–P

[Docket No. 50–362]

Southern California Edison Company;

Notice of Consideration of Issuance of

Amendment to Facility Operating

License, Proposed No Significant

Hazards Consideration Determination,

and Opportunity for a Hearing

The U.S. Nuclear Regulatory

Commission (the Commission) is

considering issuance of an amendment

to Facility Operating License No. NPF–

15 issued to Southern California Edison

Company (the licensee) for operation of

the San Onofre Nuclear Generating

Station (SONGS), Unit No. 3 located in

San Diego County, California.

The proposed amendment would

defer implementation of Surveillance

Requirement 3.3.5.6 of Technical

Specification 3.3.5, ‘‘Engineered Safety

Features Actuation System (ESFAS)

Instrumentation’’ for the 30 subgroup

relays identified in Attachment C of the

licensee’s February 18, 1997, letter to no

later than the upcoming SONGS Unit 3

Cycle 9 refueling outage (currently

scheduled to begin on April 12, 1997).

The exigent circumstances for this TS

amendment request exist because it

would avoid an undesirable transient

associated with an unnecessary plant

shutdown and this would minimize

potential safety consequences and

operational risks associated with such

action. In the event of a planned or

unplanned shutdown of Unit 3, prior to

the Cycle 9 refueling outage, testing in

accordance with Surveillance

Requirement 3.3.5.6 will be completed

prior to increasing in Modes from that

shutdown.

Before issuance of the proposed

license amendment, the Commission

will have made findings required by the

Atomic Energy Act of 1954, as amended

(the Act) and the Commission’s

regulations.

Pursuant to 10 CFR 50.91(a)(6) for

amendments to be granted under

exigent circumstances, the NRC staff

must determine that the amendment

request involves no significant hazards

consideration. Under the Commission’s

regulations in 10 CFR 50.92, this means

that operation of the facility in

accordance with the proposed

amendment would not (1) involve a

significant increase in the probability or

consequences of an accident previously

evaluated; or (2) create the possibility of

a new or different kind of accident from

any accident previously evaluated; or

(3) involve a significant reduction in a

margin of safety. As required by 10 CFR

50.91(a), the licensee has provided its

analysis of the issue of no significant

hazards consideration, which is

presented below:

1. The proposed change does not involve

a significant increase in the probability or

consequences of an accident previously

evaluated.

The proposed change would defer

completion of Surveillance Requirement (SR)

3.3.5.6 of Technical Specification (TS) 3.3.5

for 30 Emergency Safety Feature Actuation

System (ESFAS) subgroup relays until the

Unit 3, Cycle 9 refueling outage.

Operation of the facility would remain

unchanged as a result of the proposed change

and no assumptions or results of any

accident analyses are affected. Based on other

surveillance testing, the response time

margin available for these subgroup relays,

results of response time testing on Unit 2

relays, and the history of no failures since the

1989 to 1993 time period, the capability of

these ESFAS subgroup relays to perform their

specified safety function has been

demonstrated and they are operable.

Therefore, the proposed change will not

involve a significant increase in the

probability or consequences of an accident

previously evaluated.

2. The proposed change does not create the

possibility of a new or different kind of

accident from any accident previously

evaluated.

The proposed change would defer

completion of SR 3.3.5.6 of TS 3.3.5 for 30

ESFAS subgroup relays until the Unit 3,

Cycle 9 refueling outage.