Dominion Nuclear Connecticut, Inc. Millstone Power Station, Unit 3; Exemption, 52765-52766 [2012-21485]

Download as PDF Federal Register / Vol. 77, No. 169 / Thursday, August 30, 2012 / Notices cladding. The licensee proposes to use Optimized ZIRLOTM as the cladding material and therefore is requesting an exemption from the requirements. In summary, by letter dated November 17, 2011, (Agencywide Documents Access and Management System (ADAMS), Accession No. ML11329A003), the licensee requested an exemption from the requirements of 10 CFR 50.46 and Appendix K to 10 CFR part 50. The reason for the exemption is to allow the use of Optimized ZIRLOTM as a cladding material. Foundation published a notice in the Federal Register of a permit modification request received. The permit modification was issued on August 24, 2012 to: Permit No. 2012–003 Mod. #1 Jo-Ann Mellish Nadene G. Kennedy, Permit Officer. [FR Doc. 2012–21365 Filed 8–29–12; 8:45 am] BILLING CODE 7555–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 50–423; NRC–2012–0197] Dominion Nuclear Connecticut, Inc. Millstone Power Station, Unit 3; Exemption mstockstill on DSK4VPTVN1PROD with NOTICES 1.0 Background Dominion Nuclear Connecticut, Inc., (the licensee, Dominion) is the holder of Renewed Facility Operating License No. NPF–49, which authorizes operation of the Millstone Power Station, Unit 3 (MPS3). The license provides, 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. MPS3 shares the site with Millstone Power Station Unit 1, a permanently defueled boiling water reactor nuclear unit, and Millstone Power Station Unit 2, a pressurized water reactor. The facility is located in Waterford, Connecticut, approximately 3.2 miles west southwest of New London, CT. This exemption applies to MPS3 only. The other units, Units 1 and 2, are not part of this exemption. 2.0 Request/Action Section 50.46 of Title 10 of the Code of Federal Regulations (10 CFR), ‘‘Acceptance criteria for emergency core cooling systems [ECCS] for light-water nuclear power reactors,’’ requires that each power reactor meet the acceptance criteria for ECCS provided therein for zircaloy or ZIRLOTM cladding. Appendix K of 10 CFR part 50, ‘‘ECCS Evaluation Models,’’ requires the rate of energy release, hydrogen generation, and cladding oxidation from the metal/ water reaction to be calculated using the Baker-Just equation (Baker, L., Just, L.C., ‘‘Studies of Metal Water Reactions at High Temperatures, III. Experimental and Theoretical Studies of the Zirconium-Water Reaction,’’ ANL–6548, page 7, May 1962). Both of the above requirements require the use of zircaloy or ZIRLOTM VerDate Mar<15>2010 17:07 Aug 29, 2012 Jkt 226001 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. These circumstances include the special circumstances that application of the regulation is not necessary to achieve the underlying purpose of the rule. Authorized by Law This exemption would allow the licensee to use Optimized ZIRLO TM fuel rod cladding material at MPS3. As stated above, 10 CFR 50.12 allows the NRC to grant exemptions from the requirements of 10 CFR part 50. The NRC staff has determined that granting of the licensee’s proposed exemption will not result in a violation of the Atomic Energy Act of 1954, as amended, or the Commission’s regulations. Therefore, the exemption is authorized by law. No Undue Risk to Public Health and Safety The underlying purpose of 10 CFR 50.46 is to establish acceptance criteria for adequate ECCS performance. By letter dated June 10, 2005 (ADAMS Accession No. ML051670408), the NRC staff issued a safety evaluation (SE) approving Addendum 1 to Westinghouse Topical Report WCAP– 12610–P–A and CENPD–404–P–A, ‘‘Optimized ZIRLOTM’’ (ADAMS Accession No. ML062080576), wherein the NRC staff approved the use of Optimized ZIRLOTM as a fuel cladding material. The NRC staff approved the use of Optimized ZIRLOTM as a fuel cladding material based on: (1) Similarities with ZIRLOTM, (2) demonstrated material performance, and (3) a commitment to provide irradiated PO 00000 Frm 00090 Fmt 4703 Sfmt 4703 52765 data and validate fuel performance models ahead of burnups achieved in batch application. The NRC staff’s SE for Optimized ZIRLOTM includes 10 conditions and limitations for its use. As previously documented in the NRC staff’s review of topical reports submitted by Westinghouse Electric Company, LLC (Westinghouse), and subject to compliance with the specific conditions of approval established therein, the NRC staff finds that the applicability of these ECCS acceptance criteria to Optimized ZIRLOTM has been demonstrated by Westinghouse. Ring compression tests performed by Westinghouse on Optimized ZIRLOTM (NRC reviewed, approved, and documented in Appendix B of WCAP– 12610–P–A and CENPD–404–P–A, Addendum 1–A, ‘‘Optimized ZIRLOTM’’) (ADAMS Accession No. ML062080576) demonstrate an acceptable retention of post-quench ductility up to 10 CFR 50.46 limits of 2200 °F and 17 percent equivalent clad reacted. Furthermore, the NRC staff has concluded that oxidation measurements provided by the licensee illustrate that oxide thickness (and associated hydrogen pickup) for Optimized ZIRLOTM at any given burnup would be less than both zircaloy-4 and ZIRLOTM. Hence, the NRC staff concludes that Optimized ZIRLOTM would be expected to maintain better post-quench ductility than ZIRLOTM. This finding is further supported by an ongoing loss-of-coolant accident (LOCA) research program at Argonne National Laboratory, which has identified a strong correlation between cladding hydrogen content (due to inservice corrosion) and post-quench ductility. The underlying purpose of 10 CFR Part 50, Appendix K, Section I.A.5, ‘‘Metal-Water Reaction Rate,’’ is to ensure that cladding oxidation and hydrogen generation are appropriately limited during a LOCA and conservatively accounted for in the ECCS evaluation model. Appendix K states that the rates of energy release, hydrogen concentration, and cladding oxidation from the metal-water reaction shall be calculated using the Baker-Just equation. Since the Baker-Just equation presumes the use of zircaloy clad fuel, strict application of the rule would not permit use of the equation for Optimized ZIRLO TM cladding for determining acceptable fuel performance. However, the NRC staff has found that metal-water reaction tests performed by Westinghouse on Optimized ZIRLO TM demonstrate conservative reaction rates relative to the Baker-Just equation and are bounded E:\FR\FM\30AUN1.SGM 30AUN1 52766 Federal Register / Vol. 77, No. 169 / Thursday, August 30, 2012 / Notices by those approved for ZIRLO TM under anticipated operational occurrences and postulated accidents. Based on the above, no new accident precursors are created by using Optimized ZIRLO TM, thus, the probability of postulated accidents is not increased. Also, based on the above, the consequences of postulated accidents are not increased. Therefore, there is no undue risk to public health and safety. Consistent With Common Defense and Security The proposed exemption would allow the use of Optimized ZIRLOTM fuel rod cladding material at MPS3. This change to the plant configuration has no relation to security issues. Therefore, the common defense and security is not impacted by this exemption. mstockstill on DSK4VPTVN1PROD with NOTICES Special Circumstances Special circumstances, in accordance with 10 CFR 50.12(a)(2)(ii), are present whenever application of the regulation in the particular circumstances is not necessary to achieve the underlying purpose of the rule. The underlying purpose of 10 CFR 50.46 and Appendix K to 10 CFR part 50 is to establish acceptance criteria for ECCS performance and to ensure that cladding oxidation and hydrogen generation are appropriately limited during a LOCA and conservatively accounted for in the ECCS evaluation model. The wording of the regulations in 10 CFR 50.46 and Appendix K is not directly applicable to Optimized ZIRLO TM, even though the evaluations above show that the intent of the regulation is met. Therefore, since the underlying purposes of 10 CFR 50.46 and Appendix K are achieved through the use of Optimized ZIRLO TM fuel rod cladding material, the special circumstances required by 10 CFR 50.12(a)(2)(ii) for the granting of an exemption from certain requirements of 10 CFR 50.46 and Appendix K exist. 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 Dominion an exemption from certain requirements of 10 CFR 50.46 and Appendix K to 10 CFR part 50, to allow the use of Optimized ZIRLO TM fuel rod cladding material, for MPS3. Pursuant to 10 CFR 51.32, the Commission has determined that the VerDate Mar<15>2010 17:07 Aug 29, 2012 Jkt 226001 granting of this exemption will not have a significant effect on the quality of the human environment (77 FR 50533). This exemption is effective upon issuance. Dated: August 28, 2012. Connie M. Downs, Corporate Secretary, Overseas Private Investment Corporation. Dated at Rockville, Maryland, this 23rd day of August 2012. For the Nuclear Regulatory Commission. BILLING CODE 3210–01–P Michele G. Evans, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. SECURITIES AND EXCHANGE COMMISSION [FR Doc. 2012–21485 Filed 8–29–12; 8:45 am] BILLING CODE 7590–01–P [FR Doc. 2012–21595 Filed 8–28–12; 4:15 pm] [Release No. 34–67725; File No. 4–652] Technology and Trading Roundtable Securities and Exchange Commission. ACTION: Notice of roundtable discussion; request for comment. AGENCY: OVERSEAS PRIVATE INVESTMENT CORPORATION Sunshine Act; Board of Directors Meeting September 13, 2012. Thursday, September 13, 2012, 9:30 a.m. (Open Portion); 10 a.m. (Closed Portion). PLACE: Offices of the Corporation, Twelfth Floor Board Room, 1100 New York Avenue NW., Washington, DC. STATUS: Meeting OPEN to the Public from 9:30 a.m. to 10 a.m. Closed portion will commence at 10 a.m. (approx.). MATTERS TO BE CONSIDERED: 1. President’s Report. 2. Confirmation: John F. Moran as Vice President, Insurance. 3. Minutes of the Open Session of the June 14, 2012 Board of Directors Meeting. TIME AND DATE: FURTHER MATTERS TO BE CONSIDERED (Closed to the Public 10 a.m.): 1. Finance Project—Jordan. 2. Finance Project—South Africa. 3. Finance Project—Turkey. 4. Insurance Project—Ghana. 5. Insurance Project—Egypt, Jordan and Pakistan. 6. Insurance Project—Ghana. 7. Finance Project—Pan-Africa. 8. Finance Project—Indonesia. 9. Finance Project—Russia. 10. Finance Project—India. 11. Finance Project—India. 12. Minutes of the Closed Session of the June 14, 2012 Board of Directors Meeting. 13. Reports. 14. Pending Major Projects. Written summaries of the projects to be presented have been posted on OPIC’s Web site. CONTACT PERSON FOR INFORMATION: Information on the meeting may be obtained from Connie M. Downs at (202) 336–8438. PO 00000 Frm 00091 Fmt 4703 Sfmt 4703 The Securities and Exchange Commission will host a one day roundtable entitled ‘‘Technology and Trading: Promoting Stability in Today’s Markets’’ to discuss ways to promote stability in markets that rely on highly automated systems. The roundtable will focus on the relationship between the operational stability and integrity of our securities market and the ways in which market participants design, implement, and manage complex and interconnected trading technologies. The roundtable discussion will be held in the multi-purpose room of the Securities and Exchange Commission headquarters at 100 F Street NE., in Washington, DC on September 14, 2012 from 10 a.m. to approximately 4 p.m. The public is invited to observe the roundtable discussion. Seating will be available on a first-come, first-served basis. The roundtable discussion also will be available via webcast on the Commission’s Web site at www.sec.gov. The roundtable will consist of two panels. The morning panel will focus on error prevention—where technology experts will discuss current best practices and practical constraints for creating, deploying, and operating mission-critical systems, including those that are used to automatically generate and route orders, match trades, confirm transactions, and disseminate data. The afternoon panel will focus on error response—where panelists will discuss how the market might employ independent filters, objective tests, and other real-time processes or crisismanagement procedures to detect, limit, and possibly terminate erroneous market activities when they do occur, thereby limiting the impact of such errors. SUMMARY: The roundtable discussion will take place on September 14, 2012. The Commission will accept comments DATES: E:\FR\FM\30AUN1.SGM 30AUN1

Agencies

[Federal Register Volume 77, Number 169 (Thursday, August 30, 2012)]
[Notices]
[Pages 52765-52766]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2012-21485]


=======================================================================
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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-423; NRC-2012-0197]


Dominion Nuclear Connecticut, Inc. Millstone Power Station, Unit 
3; Exemption

1.0 Background

    Dominion Nuclear Connecticut, Inc., (the licensee, Dominion) is the 
holder of Renewed Facility Operating License No. NPF-49, which 
authorizes operation of the Millstone Power Station, Unit 3 (MPS3). The 
license provides, 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.
    MPS3 shares the site with Millstone Power Station Unit 1, a 
permanently defueled boiling water reactor nuclear unit, and Millstone 
Power Station Unit 2, a pressurized water reactor. The facility is 
located in Waterford, Connecticut, approximately 3.2 miles west 
southwest of New London, CT. This exemption applies to MPS3 only. The 
other units, Units 1 and 2, are not part of this exemption.

2.0 Request/Action

    Section 50.46 of Title 10 of the Code of Federal Regulations (10 
CFR), ``Acceptance criteria for emergency core cooling systems [ECCS] 
for light-water nuclear power reactors,'' requires that each power 
reactor meet the acceptance criteria for ECCS provided therein for 
zircaloy or ZIRLO\TM\ cladding. Appendix K of 10 CFR part 50, ``ECCS 
Evaluation Models,'' requires the rate of energy release, hydrogen 
generation, and cladding oxidation from the metal/water reaction to be 
calculated using the Baker-Just equation (Baker, L., Just, L.C., 
``Studies of Metal Water Reactions at High Temperatures, III. 
Experimental and Theoretical Studies of the Zirconium-Water Reaction,'' 
ANL-6548, page 7, May 1962).
    Both of the above requirements require the use of zircaloy or 
ZIRLO\TM\ cladding. The licensee proposes to use Optimized ZIRLO\TM\ as 
the cladding material and therefore is requesting an exemption from the 
requirements.
    In summary, by letter dated November 17, 2011, (Agencywide 
Documents Access and Management System (ADAMS), Accession No. 
ML11329A003), the licensee requested an exemption from the requirements 
of 10 CFR 50.46 and Appendix K to 10 CFR part 50. The reason for the 
exemption is to allow the use of Optimized ZIRLO\TM\ as a cladding 
material.

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. These circumstances include 
the special circumstances that application of the regulation is not 
necessary to achieve the underlying purpose of the rule.

Authorized by Law

    This exemption would allow the licensee to use Optimized ZIRLO \TM\ 
fuel rod cladding material at MPS3. As stated above, 10 CFR 50.12 
allows the NRC to grant exemptions from the requirements of 10 CFR part 
50. The NRC staff has determined that granting of the licensee's 
proposed exemption will not result in a violation of the Atomic Energy 
Act of 1954, as amended, or the Commission's regulations. Therefore, 
the exemption is authorized by law.

No Undue Risk to Public Health and Safety

    The underlying purpose of 10 CFR 50.46 is to establish acceptance 
criteria for adequate ECCS performance. By letter dated June 10, 2005 
(ADAMS Accession No. ML051670408), the NRC staff issued a safety 
evaluation (SE) approving Addendum 1 to Westinghouse Topical Report 
WCAP-12610-P-A and CENPD-404-P-A, ``Optimized ZIRLOTM'' 
(ADAMS Accession No. ML062080576), wherein the NRC staff approved the 
use of Optimized ZIRLOTM as a fuel cladding material. The 
NRC staff approved the use of Optimized ZIRLOTM as a fuel 
cladding material based on: (1) Similarities with ZIRLOTM, 
(2) demonstrated material performance, and (3) a commitment to provide 
irradiated data and validate fuel performance models ahead of burnups 
achieved in batch application. The NRC staff's SE for Optimized 
ZIRLOTM includes 10 conditions and limitations for its use. 
As previously documented in the NRC staff's review of topical reports 
submitted by Westinghouse Electric Company, LLC (Westinghouse), and 
subject to compliance with the specific conditions of approval 
established therein, the NRC staff finds that the applicability of 
these ECCS acceptance criteria to Optimized ZIRLOTM has been 
demonstrated by Westinghouse. Ring compression tests performed by 
Westinghouse on Optimized ZIRLOTM (NRC reviewed, approved, 
and documented in Appendix B of WCAP-12610-P-A and CENPD-404-P-A, 
Addendum 1-A, ``Optimized ZIRLOTM'') (ADAMS Accession No. 
ML062080576) demonstrate an acceptable retention of post-quench 
ductility up to 10 CFR 50.46 limits of 2200[emsp14][deg]F and 17 
percent equivalent clad reacted. Furthermore, the NRC staff has 
concluded that oxidation measurements provided by the licensee 
illustrate that oxide thickness (and associated hydrogen pickup) for 
Optimized ZIRLOTM at any given burnup would be less than 
both zircaloy-4 and ZIRLOTM. Hence, the NRC staff concludes 
that Optimized ZIRLOTM would be expected to maintain better 
post-quench ductility than ZIRLOTM. This finding is further 
supported by an ongoing loss-of-coolant accident (LOCA) research 
program at Argonne National Laboratory, which has identified a strong 
correlation between cladding hydrogen content (due to in-service 
corrosion) and post-quench ductility.
    The underlying purpose of 10 CFR Part 50, Appendix K, Section 
I.A.5, ``Metal-Water Reaction Rate,'' is to ensure that cladding 
oxidation and hydrogen generation are appropriately limited during a 
LOCA and conservatively accounted for in the ECCS evaluation model. 
Appendix K states that the rates of energy release, hydrogen 
concentration, and cladding oxidation from the metal-water reaction 
shall be calculated using the Baker-Just equation. Since the Baker-Just 
equation presumes the use of zircaloy clad fuel, strict application of 
the rule would not permit use of the equation for Optimized ZIRLO \TM\ 
cladding for determining acceptable fuel performance. However, the NRC 
staff has found that metal-water reaction tests performed by 
Westinghouse on Optimized ZIRLO \TM\ demonstrate conservative reaction 
rates relative to the Baker-Just equation and are bounded

[[Page 52766]]

by those approved for ZIRLO \TM\ under anticipated operational 
occurrences and postulated accidents.
    Based on the above, no new accident precursors are created by using 
Optimized ZIRLO \TM\, thus, the probability of postulated accidents is 
not increased. Also, based on the above, the consequences of postulated 
accidents are not increased. Therefore, there is no undue risk to 
public health and safety.

Consistent With Common Defense and Security

    The proposed exemption would allow the use of Optimized ZIRLO\TM\ 
fuel rod cladding material at MPS3. This change to the plant 
configuration has no relation to security issues. Therefore, the common 
defense and security is not impacted by this exemption.

Special Circumstances

    Special circumstances, in accordance with 10 CFR 50.12(a)(2)(ii), 
are present whenever application of the regulation in the particular 
circumstances is not necessary to achieve the underlying purpose of the 
rule. The underlying purpose of 10 CFR 50.46 and Appendix K to 10 CFR 
part 50 is to establish acceptance criteria for ECCS performance and to 
ensure that cladding oxidation and hydrogen generation are 
appropriately limited during a LOCA and conservatively accounted for in 
the ECCS evaluation model. The wording of the regulations in 10 CFR 
50.46 and Appendix K is not directly applicable to Optimized ZIRLO 
\TM\, even though the evaluations above show that the intent of the 
regulation is met. Therefore, since the underlying purposes of 10 CFR 
50.46 and Appendix K are achieved through the use of Optimized ZIRLO 
\TM\ fuel rod cladding material, the special circumstances required by 
10 CFR 50.12(a)(2)(ii) for the granting of an exemption from certain 
requirements of 10 CFR 50.46 and Appendix K exist.

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 Dominion an exemption from 
certain requirements of 10 CFR 50.46 and Appendix K to 10 CFR part 50, 
to allow the use of Optimized ZIRLO \TM\ fuel rod cladding material, 
for MPS3.
    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 (77 FR 50533).
    This exemption is effective upon issuance.

    Dated at Rockville, Maryland, this 23rd day of August 2012.

    For the Nuclear Regulatory Commission.

Michele G. Evans,
Director, Division of Operating Reactor Licensing, Office of Nuclear 
Reactor Regulation.
[FR Doc. 2012-21485 Filed 8-29-12; 8:45 am]
BILLING CODE 7590-01-P
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