Commonwealth Edison Co.; Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing

NUCLEAR REGULATORY COMMISSION

[Docket Nos. 50-373 AND 50-374]

Commonwealth Edison Co.; Notice of Consideration of Issuance of

Amendments to Facility Operating Licenses, Proposed No Significant

Hazards Consideration Determination, and Opportunity for a Hearing

The U.S. Nuclear Regulatory Commission (the Commission) is

[[Page 7282]]

considering issuance of amendments to Facility Operating License Nos.

NPF-11 and NPF-18 issued to Commonwealth Edison Company (ComEd, the

licensee) for operation of the LaSalle County Station, Units 1 and 2,

located in LaSalle County, Illinois.

The proposed amendment would change the setpoints for the automatic

primary containment isolation signal upon detection of a high main

steamline tunnel differential temperature. Additionally, the proposed

amendments would delete the automatic isolation function upon detection

of a high main steamline tunnel temperature. Both these temperature

generated signals detect possible steam leaks in the main steamline

tunnel and initiate the isolation signals cited above, thereby

providing automatic closure of the main steamline isolation valves

(MSIVs) and the main steamline drain isolation valves. The intent of

the proposed actions is to minimize spurious isolation signals which,

in turn, would trip the reactor. The licensee proposes to provide for

early detection of a main steamline break by relying on an automatic

isolation signal which would be generated by a main steamline leak of

100 gallons per minute (gpm) or greater. The current isolation

setpoints are based on a steam leakage of 25 gpm in the main steamline

tunnel.

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.

The Commission has made a proposed determination 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) Involve a significant increase in the probability or

consequences of an accident previously evaluated because:

a. There is no effect on accident initiators so there is no

change in probability of an accident. The accident analysis

associated with a steam line break in the main steam line tunnel

assumes an instantaneous circumferential break of a main steam line

downstream of the outermost isolation valve. The leak detection

isolation on differential temperature based on less than or equal to

10 percent of a calculated critical crack of a main steam line is

only a precursor of a break, and thus does not affect the

probability of a break.

b. There is no or minimal effect on the consequences of analyzed

accidents due to deletion of the automatic isolation on high

temperature leak detection in the main steam line tunnel or due to

increasing the leak detection differential temperature setpoint and

allowable values to detect a 100 gpm steam leak from a crack in a

main steam line. The worst case accident corresponding to main steam

lines outside of the reactor vessel and primary containment boundary

is a main steam line break, which bounds the dose consequences of

any size steam leak less than a full break. Also, a 200 gpm steam

leak results in a calculated offsite dose within the annual whole

body dose limit and the radioiodine release limit per 10 CFR 50

Appendix I, if detected and isolated within several weeks.

(2) Create the possibility of a new or different kind of

accident from any accident previously evaluated because:

The purpose of the main steam line isolation is based on leak

detection and automatic isolation for leakage in the main steam line

tunnel downstream of the outermost isolation valve. This change

maintains this capability with only the leak detection based on high

differential temperature in the steam line tunnel. Also, the primary

containment isolation logic for main steam line leak detection

isolation on high differential temperature remains the same. Thus no

new or different accident is created.

(3) Involve a significant reduction in the margin of safety

because:

The increased setpoint for differential temperature leak

detection for automatic isolation of the main steam lines due to a

steam leak outside of the primary containment is based on

calculated/analyzed response to a steam leak [that is] small

compared to the leak from a critical crack. The leak detection

isolation logic remains single failure proof. The previous

evaluation of diversity of isolation parameters considered the

ambient temperature and differential temperature isolations as one

parameter in Table 5.2-8 of the LaSalle [Updated Final Safety

Analysis Report] UFSAR. The deletion of leak detection isolation of

the main steam lines based on high ambient temperature in the main

steam line tunnel is acceptable, because the differential

temperature isolation has been analyzed to detect and isolate the

main steam lines based on bounding inlet air temperatures.

Therefore, the Main Steam Line High flow, vessel low level, and the

differential temperature instruments maintain adequate diversity of

isolation parameters without main steam line tunnel high

temperature.

The differential temperature leak detection for the main steam

line tunnel depends on normal ventilation flow to detect leakage.

Therefore, the trip function will be declared inoperable upon loss

of or shutdown of normal ventilation. The Technical Specifications

currently allow the main steam tunnel high temperature and high

differential temperature isolation channels to be inoperable for up

to 4 or 12 hours during the performance of specified required

surveillances. The 12 hours allowed outage time is currently for an

18 month surveillance requirement. The addition of allowance for up

to 12 hours allowed outage time to recover normal ventilation

following an unplanned loss of normal ventilation is reasonable,

since the time is small compared to the time frame over which a pipe

crack grows. Also, supplemental monitoring of water collection sumps

and area temperature in the main steam line tunnel provides

heightened awareness of operators to detect leakage in the main

steam line tunnel during the time normal ventilation is not

available. The planned shutdown of normal ventilation is currently

allowed for up to 4 hours by the Technical Specifications. The

unplanned loss of normal ventilation is expected to be less than two

times per cycle upon completion [of] design changes to make the

isolation logic power supply D.C. instead of A.C. through motor

generator sets.

The NRC staff has reviewed the licensee's analysis and, based on

this review, it appears that the three standards of 10 CFR 50.92(c) are

satisfied. Therefore, the NRC staff proposes to determine that the

amendment request involves no significant hazards consideration.

The Commission is seeking public comments on this proposed

determination. Any comments received within 30 days after the date of

publication of this notice will be considered in making any final

determination.

Normally, the Commission will not issue the amendment until the

expiration of the 30-day notice period. However, should circumstances

change during the notice period such that failure to act in a timely

way would result, for example, in derating or shutdown of the facility,

the Commission may issue the license amendment before the expiration of

the 30-day notice period, provided that its final determination is that

the amendment involves no significant hazards consideration. The final

determination will consider all public and State comments received.

Should the Commission take this action, it will publish in the Federal

Register a notice of issuance and provide for opportunity for a hearing

after issuance. The Commission expects that the need to take this

action will occur very infrequently.

Written comments may be submitted by mail to the Rules Review and

Directives Branch, Division of Freedom of Information and Publications

Services, Office of Administration, U.S.

[[Page 7283]]

Nuclear Regulatory Commission, Washington, DC 20555, and should cite

the publication date and page number of this Federal Register notice.

Written comments may also be delivered to Room 6D22, Two White Flint

North, 11545 Rockville Pike, Rockville, Maryland, from 7:30 a.m. to

4:15 p.m. Federal workdays. Copies of written comments received may be

examined at the NRC Public Document Room, the Gelman Building, 2120 L

Street, NW., Washington, DC.

The filing of requests for hearing and petitions for leave to

intervene is discussed below.

By March 28, 1996, the licensee may file a request for a hearing

with respect to issuance of the amendment to the subject facility

operating license and any person whose interest may be affected by this

proceeding and who wishes to participate as a party in the proceeding

must file a written request for a hearing and a petition for leave to

intervene. Requests for a hearing and a petition for leave to intervene

shall be filed in accordance with the Commission's ``Rules of Practice

for Domestic Licensing Proceedings'' in 10 CFR Part 2. Interested

persons should consult a current copy of 10 CFR 2.714 which is

available 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 Jacobs Memorial Library, Illinois Valley

Community College, Oglesby, Illinois 61348. If a request for a hearing

or petition for leave to intervene is filed by the above date, the

Commission or an Atomic Safety and Licensing Board, designated by the

Commission or by the Chairman of the Atomic Safety and Licensing Board

Panel, will rule on the request and/or petition; and the Secretary or

the designated Atomic Safety and Licensing Board will issue a notice of

hearing or an appropriate order.

As required by 10 CFR 2.714, a petition for leave to intervene

shall set forth with particularity the interest of the petitioner in

the proceeding, and how that interest may be affected by the results of

the proceeding. The petition should specifically explain the reasons

why intervention should be permitted with particular reference to the

following factors: (1) The nature of the petitioner's right under the

Act to be made party to the proceeding; (2) the nature and extent of

the petitioner's property, financial, or other interest in the

proceeding; and (3) the possible effect of any order which may be

entered in the proceeding on the petitioner's interest. The petition

should also identify the specific aspect(s) of the subject matter of

the proceeding as to which petitioner wishes to intervene. Any person

who has filed a petition for leave to intervene or who has been

admitted as a party may amend the petition without requesting leave of

the Board up to 15 days prior to the first prehearing conference

scheduled in the proceeding, but such an amended petition must satisfy

the specificity requirements described above.

Not later than 15 days prior to the first prehearing conference

scheduled in the proceeding, a petitioner shall file a supplement to

the petition to intervene which must include a list of the contentions

which are sought to be litigated in the matter. Each contention must

consist of a specific statement of the issue of law or fact to be

raised or controverted. In addition, the petitioner shall provide a

brief explanation of the bases of the contention and a concise

statement of the alleged facts or expert opinion which support the

contention and on which the petitioner intends to rely in proving the

contention at the hearing. The petitioner must also provide references

to those specific sources and documents of which the petitioner is

aware and on which the petitioner intends to rely to establish those

facts or expert opinion. Petitioner must provide sufficient information

to show that a genuine dispute exists with the applicant on a material

issue of law or fact. Contentions shall be limited to matters within

the scope of the amendment under consideration. The contention must be

one which, if proven, would entitle the petitioner to relief. A

petitioner who fails to file such a supplement which satisfies these

requirements with respect to at least one contention will not be

permitted to participate as a party.

Those permitted to intervene become parties to the proceeding,

subject to any limitations in the order granting leave to intervene,

and have the opportunity to participate fully in the conduct of the

hearing, including the opportunity to present evidence and cross-

examine witnesses.

If a hearing is requested, the Commission will make a final

determination on the issue of no significant hazards consideration. The

final determination will serve to decide when the hearing is held.

If the final determination is that the amendment request involves

no significant hazards consideration, the Commission may issue the

amendment and make it immediately effective, notwithstanding the

request for a hearing. Any hearing held would take place after issuance

of the amendment.

If the final determination is that the amendment request involves a

significant hazards consideration, any hearing held would take place

before the issuance of any amendment.

A request for a hearing or a petition for leave to intervene must

be filed with the Secretary of the Commission, U.S. Nuclear Regulatory

Commission, Washington, DC 20555, Attention: Docketing and Services

Branch, or may be delivered to the Commission's Public Document Room,

the Gelman Building, 2120 L Street, NW., Washington, DC, by the above

date. Where petitions are filed during the last 10 days of the notice

period, it is requested that the petitioner promptly so inform the

Commission by a toll-free telephone call to Western Union at 1-(800)

248-5100 (in Missouri 1-(800) 342-6700). The Western Union operator

should be given Datagram Identification Number N1023 and the following

message addressed to Robert A. Capra: petitioner's name and telephone

number, date petition was mailed, plant name, and publication date and

page number of this Federal Register notice. A copy of the petition

should also be sent to the Office of the General Counsel, U.S. Nuclear

Regulatory Commission, Washington, DC 20555, and to Michael I. Miller,

Esquire; Sidley and Austin, One First National Plaza, Chicago, Illinois

60603, attorney for the licensee.

Nontimely filings of petitions for leave to intervene, amended

petitions, supplemental petitions and/or requests for hearing will not

be entertained absent a determination by the Commission, the presiding

officer or the presiding Atomic Safety and Licensing Board that the

petition and/or request should be granted based upon a balancing of the

factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).

For further details with respect to this action, see the

application for amendment dated January 18, 1996, 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 Jacobs Memorial Library, Illinois

Valley Community College, Oglesby, Illinois 61348.

Dated at Rockville, Maryland, this 21st day of February 1996.

For the Nuclear Regulatory Commission.

M. David Lynch,

Senior Project Manager, Project Directorate III-2, Division of Reactor

Projects--III/IV, Office of Nuclear Reactor Regulation.

[FR Doc. 96-4343 Filed 2-26-96; 8:45 am]

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