[Federal Register Volume 64, Number 10 (Friday, January 15, 1999)]
[Notices]
[Page 2685]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 99-965]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-250 and 50-251]
Florida Power and Light Company (Turkey Point Units 3 and 4);
Exemption
I
Florida Power and Light Company (the licensee) is the holder of
Facility Operating Licenses Nos. DPR-31 and DPR-41, which authorize
operation of Turkey Point Units 3 and 4, respectively (the facility),
at a steady-state reactor power level not in excess of 2300 megawatts
thermal. The facility is a pressurized-water reactor located at the
licensee's site in Dade County, Florida. The licenses require among
other things that the facility comply with all rules, regulations, and
orders of the U.S. Nuclear Regulatory Commission (the Commission or
NRC) now or hereafter in effect.
II
In exemptions dated March 27, 1984, and August 12, 1987, concerning
the requirements of Section III.G, Appendix R to 10 CFR Part 50, the
NRC staff approved the use of 1-hour-rated fire barriers in lieu of 3-
hour-rated fire barriers in certain outdoor areas at Turkey Point Units
3 and 4. In addition, the staff found that, for certain outdoor areas
not protected by automatic fire detection and suppression systems,
separation of cables and equipment and associated circuits of redundant
trains by a horizontal distance of 20 feet free of intervening
combustibles provided an acceptable level of fire safety.
On the basis of the results of the industry's Thermo-Lag fire
endurance testing program, the licensee concluded that the outdoor
Thermo-Lag fire barrier designs cannot achieve a 1-hour fire-resistive
rating but can achieve a 30-minute fire-resistive rating when exposed
to a test fire that follows the American Society for Testing and
Materials Standard E-119 time-temperature curve. Because of these test
results, the licensee in a letter dated June 15, 1994, requested an
exemption to use 30-minute fire barriers for outdoor applications in
lieu of the 1-hour-rated fire barriers previously approved; however,
the licensee withdrew the exemption request by letter dated June 28,
1996.
In a letter dated July 31, 1997, as supplemented on July 2, October
27, and December 9, 1998, the licensee requested an exemption from the
requirements pertaining to the 3-hour-rated fire barriers required by
Section III.G.2.a, Appendix R to 10 CFR Part 50, for fire zones 79
(partial), 80 (partial), 82, 84 (partial), 85 (partial), 88 (partial),
89 (partial), 91, 92, 105, and 117 in the turbine building. The
licensee requested that the NRC approve the following fire protection
schemes as alternatives to the protection required by Section III.G.2
of Appendix R to 10 CFR Part 50: (1) separation of cables and equipment
and associated circuits of redundant post-fire safe-shutdown trains
within the turbine building fire zones 79 (partial), 80 (partial), 82,
84 (partial), 85 (partial), 88 (partial), 91, 92, and 105 between
column lines A and E-1 by a fire barrier having a minimum 1-hour fire
resistive rating; (2) separation of cables and equipment and associated
circuits of redundant post-fire safe-shutdown trains within the turbine
building fire zones 79 (partial), 84 (partial), 88 (partial), and 89
(partial) between column lines E-1 and Jc by a fire barrier having a
minimum 25-minute fire resistive rating; and (3) separation of cables
and equipment and associated circuits of redundant post-fire safe-
shutdown trains within the turbine building above the turbine operating
deck, fire zone 117, by a fire barrier having a minimum 25-minute fire
resistive rating. This request is based on the following: (1) for the
turbine building between column lines A and E-1, automatic fixed water
suppression systems would be provided for the major fire hazards
(combustible sources) and the turbine lube oil equipment, and automatic
wet pipe sprinkler protection would be provided for area coverage,
including the turbine lube oil distribution piping locations as
described in the enclosed safety evaluation; and (2) for the turbine
building between column lines E-1 and Jc, an automatic wet pipe
sprinkler protection would be provided.
III
The underlying purpose of Section III.G.2.a, Appendix R to 10 CFR
Part 50, is to provide reasonable assurance that one safe-shutdown
train and associated circuits used to achieve and maintain safe-
shutdown are free of fire damage.
On the basis of the staff's supporting safety evaluation of the
licensee's submittals, the staff concludes that the exemption from the
requirements of Section III.G.2.a of Appendix R to 10 CFR Part 50, for
fire zones 79 (partial), 80 (partial), 82, 84 (partial), 85 (partial),
88 (partial), 89 (partial), 91, 92, 105, and 117 as requested by the
licensee, provides an adequate level of fire safety and presents no
undue risk to public health and safety. In addition, the staff
concludes that the underlying purpose of the rule is achieved.
IV
Accordingly, the Commission has determined that, pursuant to 10 CFR
50.12(a), the exemption is authorized by law, will not present an undue
risk to public health and safety, and is consistent with the common
defense and security. In addition, the Commission has determined that
special circumstances are present in that application of the regulation
is not necessary to achieve the underlying purpose of the rule.
Therefore, the Commission hereby grants Florida Power and Light Company
an exemption from the requirements of Section III.G.2.a of Appendix R
to 10 CFR Part 50, as requested in its previously-referenced
submittals, for fire zones 79 (partial), 80 (partial), 82, 84
(partial), 85 (partial), 88 (partial), 89 (partial), 91, 92, 105, and
117.
Pursuant to 10 CFR 51.32, the Commission has determined that
granting this exemption for fire zones 79 (partial), 80 (partial), 82,
84 (partial), 85 (partial), 88 (partial), 89 (partial), 91, 92, 105,
and 117, will not have a significant effect on the quality of the human
environment (63 FR 65619).
This exemption is effective upon issuance.
Dated at Rockville, Maryland, this 22nd day of December 1998.
For the Nuclear Regulatory Commission.
Samuel J. Collins,
Director, Office of Nuclear Reactor Regulation.
[FR Doc. 99-965 Filed 1-14-99; 8:45 am]
BILLING CODE 7590-01-P
