Federal Register / Vol. 69, No. 212 / Wednesday, November 3, 2004 / Notices 64113

Dated: October 28, 2004. 

Michael J. Kurtz, 

Assistant Archivist for Records Services—

Washington, DC.

[FR Doc. 04–24501 Filed 11–2–04; 8:45 am] 

BILLING CODE 7515–01–P

NATIONAL SCIENCE FOUNDATION

Notice of Intent To Seek Approval to 

Revise and Extend an Information 

Collection

AGENCY: National Science Foundation.

ACTION: Notice and request for 

comments. 

SUMMARY: The National Science 

Foundation (NSF) is announcing plans 

to request clearance of this collection. In 

accordance with the requirement of 

section 3506(c)(2)(A) of the Paperwork 

Reduction Act of 1995 (Pub. L. 104–13), 

we are providing opportunity for public 

comment on this action. After obtaining 

and considering public comment, NSF 

will prepare the submission requesting 

that OMB approve clearance of this 

collection for no longer than 1 year.

DATES: Written comments on this notice 

must be received by January 3, 2005, to 

be assured of consideration. Comments 

received after that date will be 

considered to the extent practicable.

FOR FURTHER INFORMATION CONTACT:

Contact Suzanne H. Plimpton, Reports 

Clearance Officer, National Science 

Foundation, 4201 Wilson Boulevard, 

Suite 295, Arlington, VA 22230; 

telephone (703) 292–7556; or send email to splimpto@nsf.gov. Individuals 

who use a telecommunications device 

for the deaf (TDD) may call the Federal 

Information Relay Service (FIRS) at 1 

(800) 877–8339 between 8 a.m. and 8 

p.m., Eastern time, Monday through 

Friday. You also may obtain a copy of 

the data collection instrument and 

instructions from Ms. Plimpton.

SUPPLEMENTARY INFORMATION:

Title of Collection: Follow-up 

Research on Undergraduate Research 

Opportunities (URO–2). 

OMB Number: 3145–0121. 

Expiration Date of Approval: April 30, 

2006. 

Type of request: Intent to seek 

approval to revise and extend an 

information collection for one year. 

Abstract: Follow-up Research on 

Undergraduate Research Opportunities 

(URO–2). 

Proposed Project: The National 

Science Foundation (NSF) manages a 

number of programs that provide 

meaningful research experiences for 

undergraduate students. This suite of 

programs includes: Research 

Experiences for Undergraduates (REU), 

both the Site and Supplement 

components; Research in Undergraduate 

Institutions (RUI); the undergraduate 

research components in several of NSF’s 

large research centers programs, e.g.,

Engineering Research Centers (ERC) 

Programs, Science and Technology 

Centers (STCs); and several institutionwide resources development programs 

in which undergraduate research 

experiences are often one component.

These Programs provide a wide range 

of US undergraduate students with 

opportunities to conduct hands-on 

research under the mentorship of 

graduate students, postdoctoral fellows, 

and faculty in various types of higher 

education institutions, including small 

liberal arts colleges, minority-serving 

institutions, research universities, as 

well as non-profit institutions in which 

science or engineering research is 

conducted. 

The purpose of the proposed 

evaluation is to follow-up on 

undergraduate participants in research 

experiences supported by NSF who 

were surveyed in 2003. The 2003 survey 

collected information about why 

participants chose to participate in 

research, the nature of the research 

activities, effects of research on 

participants knowledge, skills, 

confidence, awareness, and academic 

and career interests and aspirations. The 

proposed survey will provide 

information about participants’ current 

academic and employment status (in 

2003, most of the respondents were in 

their senior year of college) and 

participants’ current perceptions of the 

effects of their undergraduate research 

experiences on their career and 

academic decisions. The survey 

database will be linked to that of the 

2003 survey to assess differences on a 

number of dimensions, including NSF 

program, academic major, type of 

academic institution, and sex and race/

ethnicity of the participant. 

Use of the information: NSF and 

others who design undergraduate 

research programs will be able to use 

the information to help design programs 

that meet the needs of different kinds of 

students in different kinds of settings. 

Estimate of Burden: Public reporting 

burden for this collection of information 

is estimated to average 30 minutes per 

response. 

Respondents: Individuals. 

Estimated Number of Respondents:

2900. 

Estimated Total Annual Burden on 

Respondents: 1450 hours—2900 

respondents at 30 minutes each. 

Frequency of response: One time. 

Comments: Comments are invited on 

(a) whether the proposed collection of 

information is necessary for the proper 

performance of the functions of the 

Agency, including whether the 

information shall have practical utility; 

(b) the accuracy of the Agency’s 

estimate of the burden of the proposed 

collection of information; (c) ways to 

enhance the quality, utility, and clarity 

of the information on respondents; and 

(d) ways to minimize the burden of the 

collection of information on those who 

are to respond.

Dated: October 29, 2004. 

Suzanne H. Plimpton, 

Reports Clearance Officer, National Science 

Foundation.

[FR Doc. 04–24533 Filed 11–2–04; 8:45 am] 

BILLING CODE 7555–01–M

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–498 and 50–499] 

STP Nuclear Operating Company; 

South Texas Project, Unit No. 1 and 2; 

Exemption 

1.0 Background 

The STP Nuclear Operating Company 

(STPNOC or the licensee) is the holder 

of Facility Operating License Nos. NPF–

76 and NPF–80, which authorize 

operation of South Texas Project (STP), 

Units 1 and 2, respectively. The licenses 

provide, among other things, that the 

facility is subject to all rules, 

regulations, and orders of the Nuclear 

Regulatory Commission (NRC, the 

Commission) now or hereafter in effect. 

The facility consists of two 

pressurized water reactors located in 

Matagorda County, Texas. 

2.0 Request/Action 

Title 10 of the Code of Federal 

Regulations (10 CFR) part 50, section 

50.44, specifies requirements for the 

control of hydrogen gas generated after 

a postulated loss-of-coolant accident 

(LOCA). Section 50.46 of 10 CFR 

contains acceptance criteria for the 

emergency core cooling system (ECCS) 

for reactors with zircaloy or ZIRLOTM

clad fuel. Appendix K to 10 CFR part 50 

requires, among other things, that the 

Baker-Just equation be used to predict 

the rates of energy release, hydrogen 

concentration, and cladding oxidation 

from the metal-water reaction. Of these 

three regulations (10 CFR 50.44, 50.46, 

and Appendix K to 10 CFR part 50), 10 

CFR 50.44 is the only one that has 

undergone considerable changes relative 

to its previous version, changes that 

became effective on January 1, 2004. 

64114 Federal Register / Vol. 69, No. 212 / Wednesday, November 3, 2004 / Notices 

1Letter from T.J. Jordan (South Texas) to U.S. 

Nuclear Regulatory Commission, ‘‘The South Texas 

Project, Units 1 and 2 Request for Exemption 

Pursuant to 10 CFR 50.12 Exemption to the Fuel 

Cladding Material Specified in 10 CFR 50.44, 10 

CFR 50.46, and 10 CFR 50 Appendix K,’’ Docket 

Nos. STN 50–498 and STN 50–499, May 27, 2004, 

ADAMS Accession No. ML041590200.

2Letter from T.J. Jordan (South Texas) to U.S. 

Nuclear Regulatory Commission, ‘‘The South Texas 

Project, Units 1 and 2 Response to Request for 

Additional Information Regarding Exemption to 

Use a Low Tin Cladding,’’ Docket Nos. STN 50–498 

and STN 50–499, August 23, 2004, ADAMS 

Accession No. ML042430272.

3Westinghouse Electric Company Topical Report, 

WCAP–12610–P–A, ‘‘VANTAGE+ Fuel Assembly 

Reference Core Report,’’ April 1995.

4Letter from U.S. Nuclear Regulatory 

Commission to D.A. Christian (Dominion), 

‘‘Millstone Power Station, Unit No. 3, Exemption 

from the Requirements of Title 10 of the Code of 

Federal Regulations (10 CFR) Part 50.44, 10 CFR 

50.46, and 10 CFR part 50, Appendix K,’’ Docket 

No. 50–423, February 11, 2004, ADAMS Accession 

No. ML040070238.

5Letter from U.S. Nuclear Regulatory 

Commission to D.M. Jamil (Duke), ‘‘Catawba 

Nuclear Station, Units 1 and 2 RE: Exemption from 

the Requirements of 10 CFR 50.44, 10 CFR 50.46, 

and 10 CFR 50 Appendix K,’’ August 4, 2003, 

ADAMS Accession No. ML032060473.

6Letter from U.S. Nuclear Regulatory 

Commission to P.E. Katz (Constellation), ‘‘Calvert 

Cliffs Nuclear Power Plant, Unit No. 2,’’ December 

3, 2002, ADAMS Accession No. ML022540002.

Prior to that date, 10 CFR 50.44 

specified requirements for the control of 

hydrogen gas generated after a 

postulated LOCA for reactors with 

zircaloy or ZIRLOTM clad fuel. The new 

regulation in 10 CFR 50.44 no longer 

identifies zircaloy or ZIRLOTM as 

requisite fuel cladding, nor does it 

identify the LOCA or 10 CFR 50.46 as 

bases. Because the intent of this 

exemption request relates solely to the 

specific types of cladding material 

specified in these regulations, no 

exemption is needed from the 

requirements of 10 CFR 50.44. As 

written, zircaloy or ZIRLOTM cladding 

continues to be the requisite fuel 

cladding that is explicitly identified in 

10 CFR 50.46 and Appendix K to 10 

CFR part 50. Therefore, an exemption 

from the requirements of 10 CFR 50.46 

and Appendix K to 10 CFR part 50 is 

needed in order to irradiate up to eight 

lead test assemblies (LTAs) comprised 

of low tin (Optimized) ZIRLOTM at the 

STP, Units 1 and/or 2. 

In summary, in a letter dated May 27, 

2004 (Reference 1)1, as supplemented by 

letter dated August 23, 2004 (Reference 

2)2, STPNOC requested an exemption 

from 10 CFR 50.44, ‘‘Standards for 

Combustible Gas Control System in 

Light-Water-Cooled Power Reactors‘‘; 10 

CFR 50.46, ‘‘Acceptance Criteria for 

Emergency Core Cooling Systems for 

Light-Water Nuclear Power Reactors’’; 

and Appendix K to 10 CFR part 50, 

‘‘ECCS Evaluation Models,’’ which 

would allow irradiation of up to eight 

LTAs containing fuel rods, guide tubes, 

and instrumentation tubes fabricated 

with Optimized ZIRLOTM. Optimized 

ZIRLOTM is not within the licensing 

basis of the approved ZIRLOTM as 

described in WCAP–12610–P–A 

(Reference 3)3 for STP, Units 1 and 2. 

Irradiation of up to eight Optimized 

ZIRLOTM LTAs in STP Units 1 and/or 2 

will provide data on fuel and material 

performance to support future licensing 

activities.

3.0 Discussion 

The staff has previously reviewed 

exemption requests for LTA programs 

comprised of fuel with Optimized 

ZIRLOTM cladding material 

manufactured by Westinghouse Electric 

Company (Westinghouse). Exemptions 

from 10 CFR 50.46 and Appendix K to 

10 CFR part 50 for use of Optimized 

ZIRLOTM have been issued by the NRC 

staff for Millstone, Unit 3 (Reference 4)4, 

Catawba Station (Reference 5)5, and 

Calvert Cliffs, Unit 2 (Reference 6)6.

3.1 Material Evaluation 

3.1.1 Fuel Mechanical Design 

Tin is a solid solution strengthener 

and a-phase stabilizer present entirely 

in the base a-phase zirconium 

crystalline structure. Potential impacts 

of a reduced tin content on material 

properties include (1) a reduced tensile 

strength, (2) an increased thermal creep 

rate, (3) an increased irradiation growth 

rate, (4) a reduced a↔a+b phase 

transition temperature, and (5) an 

improved corrosion resistance. The 

slight reduction in tin content will not 

affect the size, shape, or distribution of 

any second phase or inter-metallic 

precipitates nor the overall 

microstructure of this developmental 

zirconium alloy. With a consistent 

microstructure, Optimized ZIRLOTM

will exhibit material characteristics very 

similar to that of ZIRLOTM.

In Reference 2, the licensee provided 

information concerning their postirradiation examination plan. In 

Reference 2, the licensee stated that 

their plan would be consistent with 

those of the other Optimized ZIRLOTM

irradiation programs currently 

underway. As with the post-irradiation 

examinations involved in the other 

irradiation programs, the detailed 

examinations in the licensee’s 

Optimized ZIRLOTM irradiation program 

will be based on the fuel duty, cycle 

performance, need for specific 

information, and time available on site 

during refueling outages. The measured 

parameters will include rod 

profilometry, rod wear, assembly and 

rod growth, assembly bow, grid cell 

dimensions, and oxide thickness. As a 

result of these post-irradiation 

examinations, any negative aspects of 

the Optimized ZIRLOTM performance, 

including the potential impacts of 

reduced tin content identified above, 

will be identified and resolved. 

Furthermore, significant deviations from 

model predictions will be reconciled. 

The fuel rod burnup and fuel duty 

experienced by the Optimized ZIRLOTM

LTAs in STP, Units 1 and 2, will remain 

well within the operating experience 

base and applicable licensed limits for 

ZIRLOTM. 

Utilizing currently approved fuel 

performance and fuel mechanical design 

models and methods, the STP, Units 1 

and 2, and Westinghouse will perform 

cycle-specific reload evaluations to 

ensure that the Optimized ZIRLOTM

LTAs satisfy design criteria. 

Based upon the irradiation experience 

of LTAs with ZIRLOTM of a similar low 

tin content, expected performance due 

to similar material properties, and an 

extensive LTA post-irradiation 

examination program aimed at 

qualifying model predictions, the NRC 

staff finds the Optimized ZIRLOTM LTA 

mechanical design acceptable for STP, 

Units 1 and 2. 

3.1.2 Core Physics and Non-LOCA 

Safety Analysis 

The STP, Units 1 and 2, exemption 

request relates solely to the specific 

types of cladding material specified in 

the regulations. Due to similar material 

properties, any impact of Optimized 

ZIRLOTM on the safety analysis models 

and methods is expected to be minimal. 

Utilizing currently approved core 

physics, core thermal-hydraulics, and 

non-LOCA safety analysis models and 

methods, the licensee and Westinghouse 

will perform cycle-specific reload 

evaluations to ensure that the LTAs 

satisfy design criteria. Fuel management 

guidelines will require that LTAs be 

placed in non-limiting core locations. In 

Reference 2, the licensee described how 

the power peaking margin would be 

used to ensure that LTAs will not be 

limiting. 

Based upon the use of approved 

models and methods, expected material 

performance, and the placement of 

LTAs in non-limiting core locations, the 

NRC staff finds that the irradiation of up 

to eight Optimized ZIRLOTM LTAs in 

STP, Units 1 and 2, will not result in 

unsafe operation nor violation of 

specified acceptable fuel design limits. 

Furthermore, in the event of a designbasis accident, these LTAs will not 

Federal Register / Vol. 69, No. 212 / Wednesday, November 3, 2004 / Notices 64115

7Westinghouse Electric Company Topical Report, 

Addendum 1 to WCAP–12610–P–A and CENPD–

404–P–A, ‘‘Optimized ZIRLO’’, February 2003.

promote consequences beyond those 

currently analyzed. 

3.2 ECCS Performance and 

Exemptions 

Pursuant to 10 CFR 50.12, the 

Commission may, upon application by 

any interested person or 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) special circumstances are present. 

Special circumstances are present if 

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.

The underlying purpose of 10 CFR 

50.46 is to establish acceptance criteria 

for ECCS performance. In Addendum 1 

to WCAP–12610–P–A (Reference 7)7, 

Westinghouse demonstrates that the 

material properties of Optimized 

ZIRLOTM are similar to those of the 

currently approved ZIRLOTM cladding 

and that the ECCS acceptance criteria 

for ZIRLOTM clad fuel are also 

applicable to fuel with Optimized 

ZIRLOTM cladding. Ring compression 

tests performed by Westinghouse on 

Optimized ZIRLOTM demonstrate an 

acceptable retention of ductility up to 

10 CFR 50.46 limits of 2200 °F peak 

cladding temperature and 17 percent 

total oxidation. Utilizing currently 

approved LOCA models and methods, 

Westinghouse will perform cyclespecific reload evaluations to ensure 

that the Optimized ZIRLOTM LTAs 

satisfy 10 CFR 50.46 acceptance criteria.

Paragraph I.A.5 of Appendix K to 10 

CFR part 50 states that the rates of 

energy, hydrogen concentration, and 

cladding oxidation from the metal-water 

reaction shall be calculated using the 

Baker-Just equation. Since the BakerJust equation presumes the use of 

zircaloy clad fuel, strict application of 

the rule would not permit use of the 

equation for the Optimized ZIRLOTM

LTA cladding for determining 

acceptable fuel performance. Metalwater reaction tests performed by 

Westinghouse on Optimized ZIRLOTM

(documented in Appendix B of 

Addendum 1 to WCAP–12610–P–A) 

demonstrate conservative reaction rates 

relative to the Baker-Just equation. 

Thus, application of Appendix K, 

Paragraph I.A.5, in these circumstances, 

is not necessary for the licensee to 

achieve the underlying purpose of the 

regulation. 

Based upon the results of metal-water 

reaction tests and ring-compression 

tests, which ensure the applicability of 

ECCS models and acceptance criteria 

and the use of approved LOCA models 

to ensure that the Optimized ZIRLOTM

LTAs satisfy 10 CFR 50.46 acceptance 

criteria, the NRC staff finds it acceptable 

to grant an exemption from the 

requirements of 10 CFR 50.46 and 

Appendix K to 10 CFR part 50 for the 

use of up to eight LTAs in STP, Units 

1 and 2. 

3.3 Special Circumstances 

In summary, the NRC staff has 

reviewed the licensee’s request for an 

exemption to allow up to eight LTAs 

containing fuel rods, guide thimble 

tubes, and instrumentation tubes 

fabricated with Optimized ZIRLOTM to 

be used in STP, Units 1 and 2. Based on 

the NRC staff’s evaluation, as set forth 

above, the NRC staff considers that 

granting the proposed exemption will 

not defeat the underlying purpose of 10 

CFR 50.46, or Appendix K to 10 CFR 

part 50. Accordingly, special 

circumstances, are present pursuant to 

10 CFR 50.12(a)(2)(ii). 

3.4 Other Standards in 10 CFR 50.12 

The NRC staff reviewed information 

provided by the licensee in References 

1 and 2 to support the exemption 

request, and concluded that the use of 

Optimized ZIRLOTM would satisfy 10 

CFR 50.12(a) as follows: 

(1) The requested exemption is 

authorized by law: 

No law precludes the activities 

covered by this exemption request. The 

Commission, based on technical reasons 

set forth in rulemaking records, 

specified the specific cladding materials 

identified in 10 CFR 50.46 and 10 CFR 

part 50, Appendix K. Cladding materials 

are not specified by statute. 

(2) The requested exemption does not 

present an undue risk to the public 

health and safety. As stated by the 

licensee in Reference 1:

The lead test assembly safety evaluation 

will ensure that these acceptance criteria are 

met following insertion of the assemblies 

containing Optimized ZIRLOTM material. 

Fuel assemblies using Optimized ZIRLOTM

cladding will be evaluated using NRCapproved analytical methods and will 

address the changes in the cladding material 

properties. The safety analysis for the South 

Texas Project is supported by the applicable 

technical specifications. The South Texas 

Project reload cores containing Optimized 

ZIRLOTM cladding will continue to be 

operated in accordance with the operating 

limits specified in the technical 

specifications. Lead test assemblies using 

Optimized ZIRLOTM cladding will be placed 

in non-limiting core locations. Therefore, this 

exemption will not pose an undue risk to 

public health and safety.

The NRC staff has evaluated these 

considerations as set forth in Section 3.1 

and 3.2 of this Exemption. For the 

reasons set forth in Sections 3.1 and 3.2, 

the NRC staff concludes that Optimized 

ZIRLOTM may be used as a cladding 

material for up to eight LTAs to be 

placed in non-limiting core locations in 

STP, Units 1 and 2, and that an 

exemption from the requirements of 10 

CFR 50.46 and 10 CFR part 50, 

Appendix K, does not pose an undue 

risk to the public health and safety. 

(3) The common defense and security 

are not affected and, therefore, not 

endangered by this exemption. 

4.0 Conclusion 

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 

the public health and safety, and is 

consistent with the common defense 

and security. Also, special 

circumstances are present. Therefore, 

the Commission hereby grants STPNOC 

an exemption from the requirements of 

10 CFR part 50, Appendix K and 

Section 50.46, for the use of up to eight 

LTAs containing Optimized ZIRLOTM in 

STP, Units 1 and 2, up to a lead rod 

average burnup of 62,000 megawatt days 

per metric ton of uranium. 

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 (69 FR 45352). 

This exemption is effective upon 

issuance.

For the Nuclear Regulatory Commission. 

Ledyard B. Marsh, 

Director, Division of Licensing Project 

Management, Office of Nuclear Reactor 

Regulation.

[FR Doc. 04–24493 Filed 11–2–04; 8:45 am] 

BILLING CODE 7590–01–P

NUCLEAR REGULATORY 

COMMISSION 

Draft Appendix C (DG–1138) to 

Regulatory Guide 1.200, ‘‘An Approach 

for Determining the Technical 

Adequacy of Probabilistic Risk 

Assessment Results for Risk-Informed 

Activities,’’ Workshop 

The U.S. Nuclear Regulatory 

Commission (NRC) has issued draft 

Appendix C, ‘‘NRC Staff Position on 

ANS External Hazards PRA Standard’’

in August 2004. This Appendix will be