[Federal Register Volume 59, Number 168 (Wednesday, August 31, 1994)]
[Unknown Section]
[Page 0]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 94-21453]


[[Page Unknown]]

[Federal Register: August 31, 1994]


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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-423]

 

Northeast Nuclear Energy 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-49, issued to Northeast Nuclear Energy Company (the licensee), for 
operation of the Millstone Nuclear Power Station, Unit 3, located in 
New London County, Connecticut.
    The proposed amendment would grant a one-time change to the Action 
Statement for Limiting Condition for Operation 3.7.5 of the Technical 
Specifications. The amendment would permit Millstone Unit No. 3 to 
remain in Modes 1, 2, 3, or 4 while the average water temperature of 
the ultimate heat sink is greater than 75 deg.F for a 24 hour period 
for the months of August and September 1994. Exigent action is 
justified in order to permit the licensee to continue operations in the 
above mentioned Modes.
    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 (SHC), which is 
presented below:
    1. Involve a significant increase in the probability or 
consequences of an accident previously analyzed.
    The proposed temporary change to the Action Statement of LCO 3.7.5 
of the Millstone Unit No. 3 Technical Specifications will increase the 
time the plant may be in Modes 1, 2, 3, or 4 with the average water 
temperature of the ultimate heat sink greater than 75 deg.F from 6 
hours to 24 hours. The proposed change does not involve an increase in 
the probability of an accident previously analyzed. The probability of 
an accident previously evaluated is not increased by a short term 
increase in the ultimate heat sink average water temperature. The 
probability of Condition IV accidents, as described in Chapter 15 of 
the FSAR, occurring in conjunction with the short duration increase in 
ultimate heat sink average water temperature above 75 deg.F is low 
enough such that they are not risk significant. Further, an evaluation 
has been performed that safe shutdown will be achieved and maintained 
for a loss of offsite power and a steam generator tube rupture event 
with the additional consideration of a single failure with ultimate 
heat sink average water temperatures as high as 77 deg.F. There has 
been no significant increase in the consequences of these previously 
evaluated events.
    2. Create the possibility of a new or different kind of accident 
from any previously analyzed.
    The proposed temporary technical specification change does not 
create the possibility of a new or different kind of accident 
previously analyzed. The change increases the amount of time that is 
allowed for the plant to be in hot standby should the ultimate heat 
sink average water temperature increase above 75 deg.F from 6 to 24 
hours. This extension of the time allowed for the plant to be in hot 
standby does not change the plant configuration. As such, the change 
does not create the possibility of a new or different kind of accident 
previously evaluated.
    3. Involve a significant reduction in the margin of safety.
    The proposed technical specification change does not involve a 
significant reduction in the margin of safety. The proposed change 
increases the time required for the plant to be in hot standby from 6 
to 24 hours should the ultimate heat sink average water temperature 
exceed 75 deg.F. An evaluation has been performed to demonstrate that 
the risk significance associated with the increased action time is very 
low. In addition, safe shutdown capability has been demonstrated for 
ultimate heat sink average water temperatures as high as 77 deg.F.
    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 15 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 15-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 15-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. 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. 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 
20555.
    The filing of requests for hearing and petitions for leave to 
intervene is discussed below.
    By September 29, 1994, 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 20555 and at the local 
public document room located at the Learning Resource Center, Three 
Rivers Community-Technical College, Thames Valley Campus, 574 New 
London Turnpike, Norwich, Connecticut 06360. 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 a 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 the amendment is issued before the expiration of the 30-day 
hearing period, the Commission will make a final determination on the 
issue of no significant hazards consideration. If a hearing is 
requested, 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 20555, 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 John Stolz: 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 Ms. L. M. 
Cuoco, Senior Nuclear Counsel, Northeast Utilities Service Company, 
Post Office Box 270, Hartford, Connecticut 06141-0270, 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 August 19, 1994, which is available for 
public inspection at the Commission's Public Document Room, the Gelman 
Building, 2120 L Street, NW., Washington, DC 20555, and at the local 
public document room, located at the Learning Resource Center, Three 
Rivers Community-Technical College, Thames Valley Campus, 574 New 
London Turnpike, Norwich, Connecticut 06360.

    Dated at Rockville, Maryland, this 25th day of August 1994.

    For the Nuclear Regulatory Commission.
Vernon L. Rooney,
Senior Project Manager, Project Directorate I-4, Division of Reactor 
Projects--I/II, Office of Nuclear Reactor Regulation.
[FR Doc. 94-21453 Filed 8-30-94; 8:45 am]
BILLING CODE 7590-01-M