[Federal Register Volume 71, Number 10 (Tuesday, January 17, 2006)]
[Notices]
[Pages 2585-2586]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E6-415]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-321 and 50-366]
Southern Nuclear Operating Company, Inc., Edwin I. Hatch Nuclear
Plant, Unit Nos. 1 and 2 Exemption
1.0 Background
The Southern Nuclear Operating Company, Inc. (SNC, or the
licensee), is the holder of Facility Operating License Nos. DPR-57 and
NPF-5 which authorizes operation of the Edwin I. Hatch Nuclear Plant,
Unit Nos. 1 and 2 (Hatch 1 and 2), respectively. The license provides,
among other things, that the facility is subject to all rules,
regulations, and orders of the Nuclear Regulatory Commission (NRC,
Commission) now or hereafter in effect.
The facility consists of two boiling water reactors located in
Appling County, Georgia.
2.0 Request/Action
Title 10 of the Code of Federal Regulations (10 CFR), Section
50.55a(b)(2)(ix), states the requirements for the examination of metal
containments and liners of concrete containments. In particular,
Section 50.55a(b)(2)(ix)(G) requires, in part, that a VT-3 examination
method be used to conduct examinations of Item E.20 of Table IWE-2500-1
of Section IX of the American Society of Mechanical Engineers, Boiler
and Pressure Vessel Code (ASME Code).
By letter dated March 30, 2005, as supplemented by letters dated
August 2 and 24, 2005, the licensee submitted a request for an
exemption from the requirements of Section 50.55a(b)(2)(ix)(G). The
exemption request would allow the licensee to perform an alternative
examination of the accessible surface areas of the containment vessel
pressure retaining boundary vent system, in lieu of the VT-3
examination required by the rule. The licensee stated that the
alternate examination method is currently in use at Hatch 1 and 2 and
has proven to be sufficient to maintain the structural integrity and
leak-tightness of the containment surfaces, and, therefore, serves the
underlying purpose of the rule.
The licensee is currently in its 3rd 10-year inservice inspection
(ISI) interval. The licensee's code of record for the 3rd 10-year ISI
interval is the 1992 edition through the 1992 addenda of the ASME Code.
The code of record contains the requirement to perform a VT-3
examination of the accessible surface areas of the vent system. In
Relief Request RR-MC-9 submitted by letter dated July 19, 2000, the
licensee requested relief from the requirement to perform a VT-3
examination on nonsubmerged, accessible pressure boundary surfaces,
including the vent system, at the end of the 3rd 10-year ISI interval.
The licensee explained that the proposed alternative to perform a
general visual examination was sufficient to detect the types of
corrosion expected in the components covered by the relief. On October
4, 2000, this request was approved by the NRC staff.
The licensee's 4th 10-year ISI interval is scheduled to begin in
2006. The licensee's code of record for this interval will be the 2001
edition through the 2003 addenda of the ASME Code. Modifications to the
ASME Code and 10 CFR 50.55a since the beginning of the 3rd 10-year ISI
interval have relocated the requirement to perform the subject VT-3
examination from the ASME Code to 10 CFR 50.55a(b)(2)(ix). As a result,
licensees wanting relief from the requirement to perform a VT-3
examination for the subject structures must now request an exemption
from the requirements of 10 CFR 50.55a(b)(2)(ix)(G).
The licensee stated in its August 24, 2005, letter that the
examination provisions previously authorized through Relief Request RR-
MC-9 have proven to be sufficient to maintain the structural integrity
and leak-tightness of the containment surfaces, and, therefore, serve
the underlying purpose of the rule. As an alternative to the VT-3
examination, SNC is proposing the examination on all nonsubmerged,
accessible pressure boundary surfaces of the vent system. This general
visual-type examination will be performed in accordance with the Hatch
1 and 2 Qualified (N) Coatings Program. The licensee indicated that the
details of this program were provided in the October 19, 1998, response
to NRC Generic Letter 98-04, ``Potential for Degradation of the
Emergency Core Cooling System and the Containment Spray System after a
Loss-of-Coolant Accident Because of Construction and Protective Coating
Deficiencies and Foreign Material in Containment.'' The procedures and
personnel qualifications applicable for the coatings program
implementation are in compliance with Regulatory Guide 1.54 (1973), and
the implementation is based on the following documents: (1) ANSI N
101.2-1972, ``Protective Coatings (Plants) for Light Water Nuclear
Reactor Containment Facilities;'' (2) ANSI N101.4-1972, ``Quality
Assurance for Protective Coatings Applied to Nuclear Facilities;'' and
(3) EPRI Report TR-109937, ``Guideline on Nuclear Safety-Related
Coatings.'' This program was approved by the NRC staff in a letter
dated November 19, 1999.
The licensee further noted that the Qualified (N) Coatings program
examination frequency is equivalent to the requirements of Section XI
to the ASME Code, and the program requires that when evidence of
degradation is detected, a detailed examination and evaluation be
performed. The detailed visual examination would be performed in
accordance with the provisions of ASME Code, Section XI, paragraph IWE-
2310(c). The exterior surfaces of the vent system that connects the
drywell to the suppression pool are located in the reactor building.
The reactor building environment does not pose adverse conditions that
would promote rapid degradation of the outside pressure boundary
surfaces of the vent system. The interior surfaces of the vent system
that connect the drywell to the suppression pool and the portions of
the vent system located inside the suppression pool are maintained in a
nitrogen inerted environment during normal power operation in
accordance with technical specification requirements. Operational
experience and previous examinations have indicated that this
environment does not promote rapid degradation of the surfaces.
The licensee stated that the requirements specified for a VT-3
examination were developed for detecting flaws in metal components and
are more stringent than those required for detecting corrosion-related
degradation. Since corrosion of base metal is the primary issue of
concern for
[[Page 2586]]
containment pressure boundary surface areas, a general visual-type
examination, in accordance with the Hatch 1 and 2 Qualified (N)
Coatings Program, is sufficient to inspect the subject surface areas of
the containment and will provide an acceptable level of quality and
safety.
In summary, the licensee is proposing an exemption from the
requirements of Section 50.55a(b)(2)(ix)(G) to use an alternate
examination method to examine Item E.20 of Table IWE-2500-1 of ASME
Code, Section XI, pursuant to 10 CFR 50.12(a)(1) and 10 CFR
50.12(a)(2)(ii). The licensee stated in its application that compliance
with the visual examination requirements of Section 50.55a(b)(2)(ix)(G)
is not necessary for accessible surface areas of the containment vessel
pressure retaining boundary Vent System to achieve the underlying
purpose of the rule.
3.0 Discussion
Pursuant to 10 CFR 50.12, the Commission may, upon application by
any interested person or upon its own initiative, grant exemptions from
the requirements of 10 CFR Part 50 when: (1) The exemptions are
authorized by law, will not present an undue risk to public health or
safety, and are consistent with the common defense and security; and
(2) when special circumstances are present. Special circumstances are
present whenever, in accordance with 10 CFR Part 50.12(a)(2)(ii),
``Application of the regulation in the particular circumstances would
not serve the underlying purpose of the rule or is not necessary to
achieve the underlying purpose of the rule * * *.'' Therefore, in
determining the acceptability of the licensee's exemption request, the
NRC staff has performed the following evaluation to satisfy the
requirements of 10 CFR 50.12 for granting the exemption.
The underlying purpose of 10 CFR 50.55a(b)(2)(ix)(G), as it applies
to Item E1.20 of Table IWE-2500-1, is to ensure that an examination of
the metal containment or the metal liner of a concrete containment is
performed to identify corrosion or other degradation that could affect
the structural or leak-tight integrity of the structure.
The NRC staff examined the licensee's rationale to support the
exemption request and concluded that maintaining the integrity of the
coating system applied to the Hatch 1 and 2 containment vent system
components is a preventive measure that would protect against corrosion
of the coated components. As the licensee emphasizes the effectiveness
of its coating program, the NRC staff believes that the general visual
examination performed as part of maintaining the integrity of the
coating system is a proactive action and will ensure the integrity of
the coated vent system components. The proposed alternative will
provide the quality and safety level similar to the one intended by the
use of VT-3 examination of the vent system components, and would meet
the underlying purpose of 10 CFR Section 50.55a(b)(2)(ix)(G).
Based on a consideration of proposed alternatives contained in the
licensee's letters dated March 20, and August 2 and 24, 2005, the NRC
staff concludes that degradation of the containment structure would be
detected using the proposed alternative, thus meeting the underlying
purpose of the rule. Therefore, the NRC staff concludes that the
proposed exemption from 10 CFR Section 50.55a(b)(2)(ix)(G) is
acceptable.
4.0 Conclusion
Accordingly, the Commission has determined that, pursuant to 10 CFR
50.12, the exemption is authorized by law, will not present an undue
risk to the public health and safety, and is consistent with the common
defense and security. Also, special circumstances are present.
Therefore, the Commission hereby grants SNC an exemption from the
requirement of 10 CFR Section 50.55a(b)(2)(ix)(G) to perform a VT-3
examination for Item E1.2 of Table IWE-2500-1, for Hatch 1 and 2, for
the 4th 10-year ISI interval.
Pursuant to 10 CFR 51.32, the Commission has determined that the
granting of this exemption will not have a significant effect on the
quality of the human environment (70 FR 76082).
This exemption is effective upon issuance.
Dated at Rockville, Maryland, this 6th day of January 2006.
For the Nuclear Regulatory Commission.
Catherine Haney,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. E6-415 Filed 1-13-06; 8:45 am]
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