[Federal Register Volume 64, Number 20 (Monday, February 1, 1999)]
[Notices]
[Pages 4904-4906]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 99-2306]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-388]


PP&L, Inc.; 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. 
22 issued to PP&L, Inc. (the licensee) for operation of the Susquehanna 
Steam Electric Station (SSES), Unit 2, located in Luzerne County, 
Pennsylvania.
    This notice supersedes the previous notice published on Spetember 
9, 1998, (63 FR 48263) in its entirety. The proposed amendment would 
change the allowable values for both the core spray system and low 
pressure coolant injection system reactor steam dome pressure low 
functions.
    Before issuance of the proposed license amendment, the Commission 
will have made findings required by the

[[Page 4905]]

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. The proposed change does not involve a significant increase 
in the probability or consequences of an accident previously 
evaluated.
    This proposal does not involve an increase in the probability or 
consequences of an accident previously evaluated. The proposed 
amendment changes the ``Reactor Steam Dome Pressure-Low'' Allowable 
Values so to provide further assurance that the Core Spray and RHR 
systems will perform their LOCA design basis function.
    The functional design basis of the Core Spray and LPCI is to 
inject water into the reactor vessel to cool the core during a LOCA 
by opening the Core Spray and LPCI injection valves when reactor 
pressure drops below the reactor vessel low pressure permissive. The 
upper analytical limit for the permissive is the Core Spray and LPCI 
systems' maximum design pressure, and the lower analytical limit is 
the lowest pressure which allows injection to prevent exceeding the 
fuel cladding temperature limit. The new allowable values were 
selected to lie within the upper and lower limits to ensure there 
will be no change in the required logic or functions of the Core 
Spray and LPCI systems. These new values do not affect the LOCA or 
its ``limiting fault'' frequency of occurrence and do not introduce 
any new accidents or malfunctions of equipment important to safety. 
Since they do not affect the LOCA, they do not change the 
probability of occurrence of the LOCA. The new allowable values do 
not change the logic or function of the reactor vessel low pressure 
permissive. These new allowable values simply provide the basis for 
which the associated pressure instruments are to be set to ensure 
proper operation of Core Spray and LPCI within the design pressures 
as described above. Therefore, the change in allowable values does 
not increase the probability of occurrence or the consequences of an 
accident or malfunction of equipment important to safety.
    Based upon the analysis presented above, PP&L concludes that the 
proposed action does not involve an 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.
    This proposal does not create the probability of a new or 
different type of accident from any accident previously evaluated. 
The new allowable values do not change any plant systems, 
structures, or components, nor do they change any existing or create 
any new Core Spray and LPCI logic or functions. The new allowable 
values were selected to ensure the required operation of the Core 
Spray and LPCI systems within the design pressures described above.
    Therefore, the proposed change does not create the possibility 
of a new or different kind of accident from any accident previously 
evaluated.
    3. The proposed change does not involve a significant reduction 
in the margin of safety.
    The change does not involve a reduction in the margin of safety. 
Technical Specification Bases Section B3.3.5.1 9 (ECCS 
Instrumentation) identifies that the low reactor steam dome pressure 
signals are used as permissives for operation of the low pressure 
ECCS subsystems. The new allowable values were selected so to not 
impact the logic, redundancy, operability or surveillance 
requirements for these subsystems. The new allowable values maintain 
the margin requirements that the Core Spray and LPCI system 
pressures such that they do not exceed their system maximum design 
pressures and that system pressures are high enough to ensure that 
the ECCS injection prevents the fuel peak cladding temperature from 
exceeding the limits of 10CFR50.46.
    The margin of safety is unaffected by the proposed changes.

    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 Chief, Rules and 
Directives Branch, Division of Administrative Services, Office of 
Administration, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001, and should cite the publication date and page number of 
this Federal Register notice. Written comments may also be delivered to 
Room 6D59, 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 3, 1999, 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 Osterhout Free Library, Reference 
Department, 71 South Franklin Street, Wilkes-Barre, PA 18701. 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

[[Page 4906]]

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 20555-0001, Attention: Rulemakings and 
Adjudications Staff, or may be delivered to the Commission's Public 
Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC, 
by the above date. A copy of the petition should also be sent to the 
Office of the General Counsel, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, and to Jay Silberg, Esquire, Shaw, Pittman, 
Potts and Trowbridge, 2300 N Street NW., Washington, DC 20037, 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 November 23, 1998, 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 Osterhout Free Library, Reference 
Department, 71 South Franklin Street, Wilkes-Barre, PA 18701.

    Dated at Rockville, Maryland, this 27th day of January, 1999.

    For the Nuclear Regulatory Commission.
Victor Nerses,
Senior Project Manager, Project Directorate I-1, Division of Reactor 
Projects-I/II, Office of Nuclear Reactor Regulation.
[FR Doc. 99-2306 Filed 1-29-99; 8:45 am]
BILLING CODE 7590-01-P