[Federal Register Volume 64, Number 112 (Friday, June 11, 1999)]
[Notices]
[Pages 31653-31654]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 99-14841]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-483]
Union Electric Company; Callaway Plant; Issuance of Amendment to
Facility Operating License
The United States Nuclear Regulatory Commission (Commission) has
issued Amendment No. 133 to Facility Operating License No. NPF-30
issued to Union Electric Company (the licensee) for operation of the
Callaway Plant, Unit 1 located in Callaway County, Missouri.
The amendment is effective as of the date of issuance and shall be
implemented by April 30, 2000. The implementation of the amendment
includes the two license conditions which are being added to Appendix C
of the license as part of the amendment.
The amendment replaces, in its entirety, the current Technical
Specifications (TS) with a set of improved TS based on NUREG-1431,
``Standard Technical Specifications, Westinghouse Plants,'' Revision 1,
dated April 1995, including all approved changes to the standard TS;
the Commission's Final Policy Statement, ``NRC Final Policy Statement
on Technical Specifications Improvements for Nuclear Power Reactors,''
published on July 22, 1993 (58 FR 39132); and 10 CFR 50.36, ``Technical
Specifications,'' as amended July 19, 1995 (60 FR 36953). In addition,
the amendment adds two license conditions to Appendix C of the
operating license that require (1) the relocation of current TS
requirements into licensee-controlled documents, and (2) the first
performance of new and revised surveillance requirements for the
improved TS to be related to the implementation date for the improved
TS. The implementation of the amendment and the license conditions will
be completed by April 30, 2000, as stated in the amendment.
The application for the amendment, as supplemented, complies with
the standards and requirements of the Atomic Energy Act of 1954, as
amended (the Act), and the Commission's rules and regulations. The
Commission has made appropriate findings as required by the Act and the
Commission's rules and regulations in 10 CFR Chapter I.
Notice of Consideration of Issuance of Amendment and Opportunity
for Hearing in connection with this action was published in the Federal
Register on April 27, 1999 (64 FR 22658). No request for a hearing or
petition for leave to intervene was filed following this notice.
The Commission has prepared an Environmental Assessment and has
determined not to prepare an environmental impact statement related to
the action to convert the current TS to the improved TS. Based on the
Environmental Assessment, the Commission has concluded that the
issuance of the amendment will not have a significant effect on the
quality of the human environment beyond that described in the Final
Environmental Statement (FES) related to the operation of Callaway
Plant, Unit 1 in NUREG-0813 dated January 1982. The Environmental
Assessment was published in the Federal Register on May 26, 1999 (64 FR
28535).
For CN 9-01-LG in CTS 3/4.4 (and associated CN 3-13-M in CTS 6.0),
the licensee has proposed to relocate the pressure/temperature (P/T)
limits and cold overpressure mitigation system (COMS) limits from the
CTS to the pressure temperature limits report (PTLR) and proposed to
reference WCAP-14040-NP-A, Revision 1, ``Methodology Used to Develop
Cold Overpressure Mitigating System Setpoints and RCS Heatup and
Cooldown Curves,'' as the methodology for calculating the P/T and COMS
limits. The staff approved the use of this WCAP report in its generic
SE dated October 16, 1995. The licensee, however, has stated that it
will operate Callaway, Unit 1 for the near future with the existing
approved P/T and COMS limits in the CTS. Therefore, the limits
addressed in the PTLR are the limits that the staff has previously
reviewed and approved in Amendment 124 dated April 2, 1998. The
amendment approved P/T limit curves that are valid for 20 effective
full power years. The licensee will use the methodology in WCAP-14040-
NP-A to calculate the future P/T and COMS limits before the time when
the current values given in the amendment become invalid. The staff
will review the licensee's future plant-specific application of the
PTLR methodology to allow the licensee's future use of the PTLR
methodology to calculate new P/T and COMS limits without prior staff
approval. In the associated CN 3-13-M in CTS 6.0, the licensee proposed
to add a reference to Amendment 124 to the PTLR in ITS 5.6.6. The
amendment approved the limits that are listed in the PTLR and addressed
the methodology used by licensee to calculate the limits. The staff
believes that the staff's approval of the P/T and COMS limits in
Amendment 124 was not an approval for the licensee to make future
changes to these limits using the methodology described in the
amendment. Listing Amendment 124 in ITS 5.6.6 may imply this is true
and the
[[Page 31654]]
staff is not ready at this time to approve Amendment 124 for that
purpose. The review of Amendment 124, or any other licensee submittal,
for the purpose of allowing the licensee to make future changes to the
P/T and COMS limits in ITS 5.6.6 without prior staff approval will the
subject of a future letter.
For further details with respect to the amendment see (1) the
application for amendment dated May 15, 1997, as supplemented by
letters in 1998 dated June 26, August 4, August 27, September 24,
October 21 (2 letters), November 23, November 25, December 11, and
December 22, and in 1999 dated February 5, March 9, April 7, April 21,
April 30, May 4, May 27, and May 28, and (2) the Commission's related
Safety Evaluation and Environmental Assessment.
All of these items are available for public inspection at the
Commission's Public Document Room, the Gelman Building, 2120 L Street,
N.W., Washington, D.C., and at the local public document room located
at the Elmer Ellis Library, University of Missouri, Columbia, Missouri,
65201.
Dated at Rockville, Maryland, this 28th day of May 1999.
For the Nuclear Regulatory Commission.
Jack N. Donohew,
Senior Project Manager, Section 1, Project Directorate IV &
Decommissioning, Division of Licensing Project Management, Office of
Nuclear Reactor Regulation.
[FR Doc. 99-14841 Filed 6-10-99; 8:45 am]
BILLING CODE 7590-01-P
