81 FR 14135 - Exelon Generation Company, LLC; Dresden Nuclear Power Station, Units 1, 2, and 3; Independent Spent Fuel Storage Installation
NUCLEAR REGULATORY COMMISSION Federal Register Volume 81, Issue 51 (March 16, 2016)
Federal Register Volume 81, Issue 51 (March 16, 2016)
| Page Range | 14135-14139 | |
| FR Document | 2016-05955 |
[Federal Register Volume 81, Number 51 (Wednesday, March 16, 2016)] [Notices] [Pages 14135-14139] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2016-05955] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-010, 50-237, 50-249, and 72-37; NRC-2016-0046] Exelon Generation Company, LLC; Dresden Nuclear Power Station, Units 1, 2, and 3; Independent Spent Fuel Storage Installation AGENCY: Nuclear Regulatory Commission. ACTION: Exemption; issuance. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption from certain requirements regarding the storage of a thoria rod canister in response to a request submitted by Exelon Generation Company, LLC (EGC) on January 29, 2015, for its general license to operate an independent spent fuel storage installation (ISFSI) at the Dresden Nuclear Power Station (DNPS). This exemption would permit EGC to load and store the DNPS Unit 1 thoria rod canister containing 18 DNPS Unit 1 thoria rods in a Holtec International, Inc., HI-STORM 100 multi-purpose canister (MPC)-68M using Certificate of Compliance (CoC) No. 1014, Amendment No. 8, Rev. 1.\1\ --------------------------------------------------------------------------- \1\ The licensee's application referred to Amendment 8; since that time, Amendment 8 has been revised. (On February 16, 2016, Amendment 8, Rev. 1 to CoC 1014 became effective.) The revision does not impact the exemption request that is the subject of this exemption because none of the changes in the revision revised the thoria contents or the physical characteristics of the storage cask. --------------------------------------------------------------------------- DATES: March 16, 2016. ADDRESSES: Please refer to Docket ID NRC-2016-0046 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document using any of the following methods:Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2016-0046. Address questions about NRC dockets to Carol Gallagher; telephone: 301-415- 3463; email: [email protected]. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. NRC's Agencywide Documents Access and Management System (ADAMS): You may obtain publicly-available documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by email to [email protected]. For the convenience of the reader, the ADAMS accession numbers are provided in a table in the ``Availability of Documents'' section of this document. NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. FOR FURTHER INFORMATION CONTACT: Bernard White, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone: 301-415-6577; email: [email protected]. SUPPLEMENTARY INFORMATION: I. Background Dresden Unit 1 produced power commercially from 1960 to October 31, 1978. The plant shut down in October 1978 and is currently in SAFSTOR. The decommissioning plan was approved in September 1993. No significant dismantlement activities are underway. Isolation of Units 1, 2, and 3 is complete. Consistent with subpart K of part 72 of title 10 of the Code of Federal Regulations (10 CFR), a general license is issued for the storage of spent fuel in an ISFSI at power reactor sites to persons authorized to possess or operate nuclear power reactors under 10 CFR part 50. EGC is currently authorized to store spent fuel at the DNPS ISFSI under the 10 CFR part 72 general license provisions. The DNPS ISFSI is currently loading and storing spent fuel in Holtec HI-STORM 100 storage casks, approved by the NRC under CoC No. 1014. II. Request/Action By letter dated January 29, 2015, as supplemented on June 8, 2015, EGC submitted a request for an exemption from 10 CFR 72.212(b)(3) and the portion of 10 CFR 72.212(b)(11) that requires compliance with the terms, conditions, and specifications of CoC No. 1014, Amendment No. 8, for the Holtec HI-STORM 100 with the MPC-68M, to the extent necessary for EGC to load and store one DNPS Unit 1 thoria rod canister containing 18 DNPS Unit 1 thoria rods. Upon review, the NRC added the following requirements for the proposed action pursuant to its authority under 10 CFR 72.7: 10 CFR 72.212(a)(2), which limits storage of spent fuel in casks approved under part 72; 72.212(b)(5)(i), which states a ``cask, once loaded with spent fuel . . . will conform to the terms, conditions and specifications of a CoC or an amended CoC listed in Sec. 72.214''; and 10 CFR 72.214, ``List of approved spent fuel storage casks.'' III. Discussion Pursuant to 10 CFR 72.7, the Commission may, upon application by any interested person or upon its own initiative, grant such exemptions from the requirements of the regulations of 10 CFR part 72 as it determines are authorized by law and will not endanger life or property or the common defense and security, and are otherwise in the public interest. A. Authorized by Law This exemption would permit the applicant to load and store the DNPS Unit 1 thoria rod canister containing 18 DNPS Unit 1 thoria rods in the HI-STORM 100 MPC-68M CoC 1014, Amendment No. 8, Rev. 1, which otherwise would not permit the storage of thoria rods. The provisions from which the NRC is granting the exemption require the licensee to comply with the terms, conditions, and specifications of the CoCs for the approved cask model it uses. Section 72.7 allows the Commission to grant exemptions from the requirements of 10 CFR part 72 if the exemption is authorized by law, will not endanger life or property or the common defense [[Page 14136]] and security, and is otherwise in the public interest. As explained in the following discussion, the proposed exemption will not endanger life or property, or the common defense and security, and is otherwise in the public interest. Issuance of this exemption is consistent with the Atomic Energy Act of 1954, as amended, and not otherwise inconsistent with NRC's regulations or other applicable laws. Therefore, issuance of the exemption is authorized by law. B. Will Not Endanger Life or Property or the Common Defense and Security Approval of this exemption request will allow EGC to load and store the 18 thoria rods in the DNPS Unit 1 thoria rod canister within a Holtec HI-STORM 100 MPC-68M. As discussed in the following section, the NRC staff finds that EGC's proposal to load and store thoria rods is acceptable and will not endanger life or property or common defense and security. Review of the Requested Exemption The addition of the MPC-68M to the list of approved storage cask designs for the Holtec HI-STORM 100 system was reviewed previously and approved by the NRC. The CoC and safety evaluation report (SER) for Amendment 8 were issued on May 10, 2012, corrected on November 12, 2012, and revised on February 16, 2016. Amendment No. 8 added the MPC- 68M canister, two new boiling water reactor (BWR) fuel assembly/array classes, a new pressurized-water reactor fuel assembly/array class, and revised Condition No. 3 in the certificate to include leak testing of the confinement boundary base material in addition to confinement welds. Amendment 8 also made other administrative changes. Thoria rods/ assemblies were not considered in Amendment No. 8 for the MPC-68M, however they have been approved for storage in the MPC-68, MPC-68F and MPC-68FF in Amendment No. 1. The applicant stated that the design characteristics of the thoria rods in the exemption request are the same as those approved for storage in the MPC-68, MPC-68F and MPC-68FF. The characteristics of these rods are specified in CoC No. 1014, Amendment No. 8, Revision No. 1, Appendix B, Table 2.1-1, Section II, ``MPC MODEL: MPC-68F,'' Item A.7 and Section III, ``MPC MODEL: MPC-68 and MPC-68FF,'' Item A.3. In addition, the applicant cited the Safety Analysis Report (SAR) for CoC No. 1014, Amendment No. 8, and the NRC staff's corresponding SER dated May 10, 2012, which documented the NRC staff's basis for approval of Amendment No. 8, to support the exemption request. The NRC staff reviewed the requested exemption and determined that it does not change the fundamental design, components, or safety features of the storage system. The NRC staff evaluated the applicable potential safety impacts of granting the exemption to assess the potential for any danger to life or property or the common defense and security. Specifically, the NRC staff reviewed the applicant's structural integrity, thermal, confinement, shielding, and criticality evaluations for the proposed exemption. Structural Review for the Requested Exemption: The NRC staff reviewed the exemption request including the documents referenced by the applicant. Specifically, the NRC staff reviewed the design characteristics of thoria rods and canister limits provided by the applicant in its June 8, 2015, response to NRC's request for additional information (RAI) dated May 8, 2015, and verified that the thoria rods and canister limits are the same as those previously approved in Amendment No. 1 to CoC 1014. In its review of Amendment No. 8, the NRC staff determined that the structural analysis presented in ``HI-STORM Topical Safety Analysis Report (TSAR),'' Holtec Report HI-951312, Rev. 11, as supplemented on July 3, 2001, August 13 and 17, and October 5, 12, and 19, 2001, demonstrated that the thoria rod canister was structurally adequate to support the loads during normal lifting operations, normal and off-normal conditions, as well as during postulated-accident conditions. Based on the NRC staff's review of the physical characteristics of the thoria rods, thoria canister and MPC-68M canister, the NRC staff concludes that the proposed storage of thoria rods in an MPC-68M will be bounded by the previously approved structural analysis for MPC-68M because the thoria rods and canister limits are the same as those previously approved in Amendment No. 1 to CoC 1014. Therefore, the NRC staff has reasonable assurance that the structural adequacy of the MPC- 68M for the intended purpose will be maintained, as documented in the NRC staff's SER for Amendment No. 8 to CoC 1014. Thermal Review for the Requested Exemption: The decay heat per DNPS Unit 1 thoria rod canister is less than or equal to 115 watts, which is significantly lower than the maximum allowable decay heat limit of 393 watts per fuel storage location for damaged fuel and fuel debris, as specified in Amendment No. 8 to CoC 1014. In addition, the exemption, does not change the cask decay heat distribution due to the lower decay heat of the DNPS Unit 1 thoria rod canister. Accordingly, the decay heat analyses reviewed and approved by the NRC staff in Amendment 8 are bounding. The applicant referenced the previous Holtec thermal evaluation of the MPC-68M for Amendment No. 8 to CoC 1014 to show that it has lower maximum temperatures (i.e., fuel cladding, basket, and MPC shell) than the maximum temperatures of Holtec's thermal evaluation for the MPC-68 canister. Holtec stated that this is due to the higher thermal conductivity of the Metamic-HT basket material, the use of full length aluminum basket shims, and the higher emissivities of the basket and basket shims. Based on the NRC staff's review of the exemption request and the references cited therein, the NRC staff finds acceptable the small decay heat contribution of the thoria rods, when compared with the design basis-heat load for failed fuel. In addition, the NRC staff finds that the thermal effects of an MPC-68M basket design loaded with one DNPS Unit 1 thoria rod canister is bounded by previous thermal analysis. Therefore, if one DNPS Unit 1 thoria rod canister is included in an MPC-68M, the NRC staff concludes that the fuel cladding temperature of the MPC-68M and its contents are bounded by those NRC reviewed and approved for CoC 1014, Amendment No. 8. The applicant stated that the cladding hoop stress for the thoria rods, during vacuum drying, is similar to the stresses expected in uranium dioxide (UO 2 ) rods stored in an MPC-68M. The applicant also stated it does not plan to load high burnup fuel, i.e., fuel with an average burnup exceeding 45,000 MWD/MTU, in the MPC-68M that contains the thoria rod canister. The applicant stated that this would result in a decay heat below the design basis decay heat and, therefore a lower design basis fuel temperature compared to the value reported in Table 4.III.5 of the HI-STORM 100 FSAR, Revision 11, during vacuum drying operations. Based on the lower decay heat and similar expected cladding hoop stress for the thoria rods during vacuum drying, the NRC staff finds that the vacuum drying time limits in CoC 1014, Amendment No. 8, Revision No. 1, Technical Specifications, which were not necessary for the MPC-68M in CoC 1014, Amendment No. 8, Revision No. 1, are also not necessary for the MPC-68M with the inclusion of the DNPS Unit 1 thoria rod canister. Consistent with EGC's request, this exemption does not authorize the loading and storage of [[Page 14137]] high burnup fuel in the MPC-68M if the DNPS Unit 1 thoria rod canister is loaded in the MPC-68M. Accordingly, the NRC staff finds that the cask loaded with 1 thoria rod canister will continue to meet applicable thermal requirements. Confinement Review for the Requested Exemption: EGC stated that the design of the MPC-68M confinement boundary, which includes the vent and drain ports, is unchanged by the exemption request. In addition, EGC stated that the exemption would not change the short-term cask operations, including draining of the MPC, welding of the lid, drying and backfilling with inert gas, and handling of the MPC that were approved in Amendment No. 8 to CoC No. 1014. Since this exemption would not change the design aspects, including a leak tight confinement boundary (leak tight is defined as <=1 x 1-\7\ ref-cc/sec, as defined by American National Standards Institute (ANSI) N14.5, ``Radioactive Materials--Leakage Tests on Packages for Shipment''), from those previously reviewed and approved by the NRC, the confinement characteristics will continue to be adequately maintained. Shielding Review for the Requested Exemption: The NRC staff reviewed the exemption request and the applicant's RAI response. EGC is relying on NRC's previous approval of Amendment Nos. 1 and 8 to CoC No. 1014 to conclude that offsite doses from a storage cask containing a single thoria rod canister along with 67design basis 6x6 Dresden Unit 1 fuel assemblies are is the same as or bounded by previous analyses and did not perform any additional analysis for this exemption. The applicant cites the shielding analysis of the thoria rods as previously documented in ``HI-STORM TSAR,'' HOLTEC Report HI-951312, Rev. 11, and approved by the NRC staff in CoC 1014, Amendment No. 1 and documented in the NRC staff's SER dated July 18, 2002. Sections 5.2.6 and 5.4.8 of the Holtec TSAR includes Holtec's analysis of the thoria rods, and presents a summary of the neutron and photon sources in Tables 5.2-7, 5.2-19, 5.2-37, and 5.2-38. EGC stated that the neutron source for the thoria rods remains below that of the design basis fuel assembly. EGC also stated that the photon source for the thoria rods is bounded by the design basis fuel assembly except in the 2.5-3.0 MeV energy range. To demonstrate that the gamma dose rate from the thoria rods is bounded by the design-basis BWR fuel, EGC referred to Holtec's TSAR for Amendment No. 1, which, according to Holtec, conservatively assumed 68 thoria rod canisters were present in the MPC, even though only one thoria rod canister exists on the DNPS site. Holtec's dose rate evaluation showed that the external dose rate for a HI-STORM 100 cask loaded with 68 thoria rod canisters, each with 18 Thoria rods, was 17 percent higher than a canister filled with design-basis fuel. In its SER for approval of Amendment No. 1, the NRC staff considered the conservatisms built into Holtec's dose rate analysis and concluded that a single thoria rod canister would not likely result in a dose rate increase for a MPC-68M canister loaded with 67 BWR spent fuel assemblies and a single thoria rod canister containing up to 18 thoria rods. Subsequently, in its review of Amendment 8, the NRC staff reviewed the impact from the MPC-68M basket on external dose rates compared to the borated baskets for the other MPC-68 canisters. Considering that the outer loaded assemblies provide significant shielding of the innermost assemblies, the NRC staff determined that the dose rate is dominated by the peripherally loaded assemblies. The NRC staff, using MicroShield[supreg], calculated dose rates with the two different basket materials. Based on the results of this calculation, the NRC staff found that the canister and overpack were the components most critical to shielding. Additionally, in the SER for Amendment No. 8, NRC staff concluded that Holtec showed that the shielding provided by the MPC-68M did not significantly change from the MPC-68 canister, since neither the canister shell nor the overpack changed and the Metamic-HT basket would have negligible impact on external dose rates. In prior NRC staff reviews of Amendment Nos. 1 and 8, the NRC staff concluded that the Metamic-HT basket in the MPC-68M has very little effect on the external dose rate; and a single thoria rod canister, while unbounded in the 2.5-3.0 MeV energy range, will not impact cask external dose rates. Accordingly, NRC staff has reasonable assurance that off-site doses from the presence of a single, thoria rod canister in an MPC-68M loaded with design-basis fuel with the same characteristics as those approved for the MPC-68, MPC-68F and MPC-68FF will not increase when compared to a canister loaded with 68 design- basis fuel assemblies. Therefore, such a canister will continue to meet applicable offsite dose requirements. Criticality Review for the Requested Exemption: The NRC staff reviewed the exemption request and the applicant's RAI response. The applicant initially only cited the criticality analysis of the thoria rods previously documented in ``HI-STORM TSAR'', Holtec Report HI- 951312, Rev. 11, and documented in the NRC staff's SER dated July 18, 2002, which was the basis for approval of Amendment No. 1 to CoC No. 1014. In Section 6.4.6 of the TSAR, Holtec shows that the reactivity of the thoria rods remains below that of the design-basis fuel assembly reactivity, which is summarized in Holtec TSAR Tables 6.1.7 and 6.1.8. The NRC staff did not analyze any impact the thoria rods might have on criticality during its review of the Holtec TSAR as the components important to criticality control in the MPC-68 and MPC-68FF remained unchanged from its prior review of the HI-STAR Amendment No. 1. This is not the case with the MPC-68M. In its June 8, 2015 response to additional information, the applicant cited the NRC staff's basis for approval of CoC 1014, Amendment No. 8 in its SER dated May 10, 2012, to support this exemption request. The applicant noted several advantages that Metamic- HT has over older basket designs. Among them are the inability of the neutron absorber material to detach or relocate, and the presence of absorber material along the entire length of the basket, rather than a fixed, discrete section. During its review of Amendment No. 8, NRC staff noted that the applicant's analysis resulted in a large margin to criticality and concluded that the use of the existing fuel assemblies authorized in the CoC within the Metamic-HT basket in the MPC-68M would remain subcritical. Two prior NRC staff reviews of amendments (HI-STORM Amendment Nos. 1 and 8) have found the Metamic-HT basket in the MPC-68M to be at least as effective as those in the MPC-68 and MPC-68FF. In addition, these reviews found that a thoria rod canister is less reactive than the spent fuel assemblies currently authorized in CoC 1014. Based on its consideration of these previous approvals, NRC staff concludes that the presence of a single, thoria rod canister in an MPC-68M is bounded by prior analyses of existing, authorized contents. Review of Common Defense and Security: The NRC staff also considered potential impacts of granting the exemption on the common defense and security. The requested exemption is not related to any security or common defense aspect of the DNPS ISFSI, therefore granting the exemption would not result in any potential impacts to common defense and security. Based on its review, the NRC staff has reasonable assurance that in granting the exemption, the storage system will [[Page 14138]] continue to meet the requirements of 10 CFR part 72 and the offsite dose limits of 10 CFR part 20 and, therefore, will not endanger life or property. The NRC staff also finds that the exemption would not endanger common defense and security. C. Otherwise in the Public Interest In considering whether granting the exemption is in the public interest, the NRC staff considered the alternative of not granting the exemption. If the exemption was not granted, in order to comply with the CoC, the DNPS Unit 1 thoria rod canister containing the 18 thoria rods would not be loaded during the 2016 spent fuel loading campaign (SFLC). The applicant maintains that loading the thoria rod canister during the 2016 DNPS SFLC is part of a program to ensure full core discharge capability. EGC stated that granting the exemption is in the public interest since it will permit storage of the thoria rods in an inherently safe and passive system. Additionally, EGC stated that granting the exemption would permit this storage without the burden and impact of requesting an amendment to the CoC. Not granting the exemption would require Holtec to submit an amendment to the CoC, which would delay the DNPS program to ensure full core discharge capability and impact future loadings. In addition to allowing DNPS to continue with its program to ensure full core discharge capability on schedule, based on its review of EGC's request, the NRC staff concludes that allowing thoria rods with the same characteristics as those approved for the MPC-68, MPC-68F and MPC-68FF as an approved content in the MPC-68M would continue to provide adequate protection of public health and safety. Therefore, granting the exemption is otherwise in the public interest. D. Environmental Considerations The NRC staff also considered whether there would be any significant environmental impacts associated with the exemption. For this proposed action, the NRC staff performed an environmental assessment pursuant to 10 CFR 51.30. The environmental assessment concluded that the proposed action would not significantly impact the quality of the human environment. The NRC staff concluded that the proposed action would not result in any changes in the types or amounts of any radiological or non-radiological effluents that may be released offsite, and there is no significant increase in occupational or public radiation exposure because of the proposed action. The Environmental Assessment and the Finding of No Significant Impact was published on March 4, 2016 (81 FR 11603). IV. Conclusions Accordingly, the Commission has determined that, pursuant to 10 CFR 72.7, this exemption is authorized by law, will not endanger life or property or the common defense and security, and is otherwise in the public interest. Therefore, the Commission hereby grants EGC an exemption from 10 CFR 72.212(a)(2), 10 CFR 72.212(b)(3), 10 CFR 72.212(b)(5)(i), 10 CFR 72.214, and the portion of 10 CFR 72.212(b)(11) that requires compliance with terms, conditions, and specifications of the CoC only with regard to storage of DNPS Unit 1 thoria rods with the same characteristics as those specified for storage in the MPC-68, MPC- 68F and MPC-68FF in CoC No. 1014, Amendment No. 8, Revision No. 1, Appendix B, Table 2.1-1, Section II, ``MPC MODEL: MPC-68F,'' Item A.7 and Section III, ``MPC MODEL: MPC-68 and MPC-68FF,'' Item A.3 in the MPC-68M using the Holtec[supreg] CoC No. 1014, Amendment No. 8, Revision No. 1. This exemption does not authorize loading in a canister with other spent fuel which has an average burnup exceeding 45,000 MWD/MTU. V. Availability of Documents The documents identified in the following table are available to interested persons through one or more of the methods indicated in the ADDRESSES section. ------------------------------------------------------------------------ Document ADAMS Accession No. ------------------------------------------------------------------------ Exelon Generation Company (EGC) ML15029A334. application dated January 29, 2015. EGC supplement dated June 8, 2015 ML15159A745. CoC 1014 Amendment 8, Revision 1. ML16041A233. Amendment No. 8 CoC and SER ML12132A028. issued on May 10, 2012. Amendment No 8 correction (CoC ML12213A203. and SER) issued on November 12, 2012. Amendment No. 8, Revision No. 1 ML16041A233. issued on February 10, 2016. ``HI-STORM Topical Safety ML003748149, ML072420266, Analysis Report (TSAR),'' Holtec ML003748010, ML003747975, and Report HI-951312, Rev. 11 ML003747995. (Holtec amendment 1 request) dated August 31, 2000. July 3, 2001 supplement to Holtec ML011900259. amendment 1 request. August 13, 2001 supplement to ML012260436. Holtec amendment 1 request. August 17, 2001 supplement to ML012330523. Holtec amendment 1 request. October 5, 2001, supplement to ML012830522. Holtec amendment 1 request. October 12, 2001, supplement to ML012900007. Holtec amendment 1 request. October 19, 2001, supplement to ML020150094. Holtec amendment 1 request. NRC's request for additional ML15128A088. information dated May 8, 2015. Amendment No. 1 to CoC 1014...... ML022000176. HI-STORM 100 FSAR, Revision 11... ML13246A040. ANSI N14.5, ``Radioactive Accessible from American National Materials--Leakage Tests on Standards Institute. Packages for Shipment''. HI-STAR Amendment No. 1.......... ML003780760. ------------------------------------------------------------------------ [[Page 14139]] The exemption is effective upon issuance. Dated at Rockville, Maryland, this 8th day of March, 2016. For the Nuclear Regulatory Commission. Steve Ruffin, Acting Branch Chief, Spent Fuel Licensing Branch, Division of Spent Fuel Management, Office of Nuclear Material Safetyand Safeguards. [FR Doc. 2016-05955 Filed 3-15-16; 8:45 am] BILLING CODE 7590-01-P
![Federal Register / Vol. 81, No. 51 / Wednesday, March 16, 2016 / Notices 14135
material. Each member provides DATES: March 16, 2016. an ISFSI at power reactor sites to
technical assistance in his/her specific ADDRESSES: Please refer to Docket ID persons authorized to possess or operate
area(s) of expertise, particularly with NRC–2016–0046 when contacting the nuclear power reactors under 10 CFR
respect to emerging technologies. NRC about the availability of part 50. EGC is currently authorized to
Members also provide guidance as to information regarding this document. store spent fuel at the DNPS ISFSI under
NRC’s role in relation to the You may obtain publicly-available the 10 CFR part 72 general license
responsibilities of other Federal information related to this document provisions. The DNPS ISFSI is currently
agencies as well as of various using any of the following methods: loading and storing spent fuel in Holtec
professional organizations and boards. • Federal Rulemaking Web site: Go to HI–STORM 100 storage casks, approved
Members of this Committee have http://www.regulations.gov and search by the NRC under CoC No. 1014.
demonstrated professional for Docket ID NRC–2016–0046. Address II. Request/Action
qualifications and expertise in both questions about NRC dockets to Carol
scientific and non-scientific disciplines By letter dated January 29, 2015, as
Gallagher; telephone: 301–415–3463;
including nuclear medicine; nuclear supplemented on June 8, 2015, EGC
email: Carol.Gallagher@nrc.gov. For
cardiology; radiation therapy; medical submitted a request for an exemption
technical questions, contact the
physics; nuclear pharmacy; State from 10 CFR 72.212(b)(3) and the
individual listed in the FOR FURTHER
medical regulation; patient’s rights and portion of 10 CFR 72.212(b)(11) that
INFORMATION CONTACT section of this
care; health care administration; and requires compliance with the terms,
document. conditions, and specifications of CoC
Food and Drug Administration • NRC’s Agencywide Documents No. 1014, Amendment No. 8, for the
regulation. Access and Management System Holtec HI–STORM 100 with the MPC–
Dated at Rockville, Maryland, this 10th day (ADAMS): You may obtain publicly- 68M, to the extent necessary for EGC to
of March 2016. available documents online in the load and store one DNPS Unit 1 thoria
For the Nuclear Regulatory Commission. ADAMS Public Documents collection at rod canister containing 18 DNPS Unit 1
Andrew L. Bates, http://www.nrc.gov/reading-rm/ thoria rods. Upon review, the NRC
Federal Advisory Committee Management adams.html. To begin the search, select added the following requirements for
Officer. ‘‘ADAMS Public Documents’’ and then the proposed action pursuant to its
[FR Doc. 2016–05944 Filed 3–15–16; 8:45 am] select ‘‘Begin Web-based ADAMS authority under 10 CFR 72.7: 10 CFR
BILLING CODE 7590–01–P
Search.’’ For problems with ADAMS, 72.212(a)(2), which limits storage of
please contact the NRC’s Public spent fuel in casks approved under part
Document Room (PDR) reference staff at 72; 72.212(b)(5)(i), which states a ‘‘cask,
NUCLEAR REGULATORY 1–800–397–4209, 301–415–4737, or by once loaded with spent fuel . . . will
COMMISSION email to pdr.resource@nrc.gov. For the conform to the terms, conditions and
convenience of the reader, the ADAMS specifications of a CoC or an amended
[Docket Nos. 50–010, 50–237, 50–249, and accession numbers are provided in a
72–37; NRC–2016–0046] CoC listed in § 72.214’’; and 10 CFR
table in the ‘‘Availability of Documents’’ 72.214, ‘‘List of approved spent fuel
Exelon Generation Company, LLC; section of this document. storage casks.’’
Dresden Nuclear Power Station, Units • NRC’s PDR: You may examine and
purchase copies of public documents at III. Discussion
1, 2, and 3; Independent Spent Fuel
Storage Installation the NRC’s PDR, Room O1–F21, One Pursuant to 10 CFR 72.7, the
White Flint North, 11555 Rockville Commission may, upon application by
AGENCY: Nuclear Regulatory Pike, Rockville, Maryland 20852. any interested person or upon its own
Commission. FOR FURTHER INFORMATION CONTACT: initiative, grant such exemptions from
ACTION: Exemption; issuance. Bernard White, Office of Nuclear the requirements of the regulations of 10
Material Safety and Safeguards, U.S. CFR part 72 as it determines are
SUMMARY: The U.S. Nuclear Regulatory Nuclear Regulatory Commission, authorized by law and will not endanger
Commission (NRC) is issuing an Washington DC 20555–0001; telephone: life or property or the common defense
exemption from certain requirements 301–415–6577; email: Bernard.White@ and security, and are otherwise in the
regarding the storage of a thoria rod nrc.gov. public interest.
canister in response to a request
submitted by Exelon Generation SUPPLEMENTARY INFORMATION: A. Authorized by Law
Company, LLC (EGC) on January 29, I. Background This exemption would permit the
2015, for its general license to operate applicant to load and store the DNPS
an independent spent fuel storage Dresden Unit 1 produced power
Unit 1 thoria rod canister containing 18
installation (ISFSI) at the Dresden commercially from 1960 to October 31,
DNPS Unit 1 thoria rods in the HI–
Nuclear Power Station (DNPS). This 1978. The plant shut down in October
STORM 100 MPC–68M CoC 1014,
exemption would permit EGC to load 1978 and is currently in SAFSTOR. The
Amendment No. 8, Rev. 1, which
and store the DNPS Unit 1 thoria rod decommissioning plan was approved in
otherwise would not permit the storage
canister containing 18 DNPS Unit 1 September 1993. No significant
of thoria rods. The provisions from
thoria rods in a Holtec International, dismantlement activities are underway.
which the NRC is granting the
Inc., HI–STORM 100 multi-purpose Isolation of Units 1, 2, and 3 is
exemption require the licensee to
canister (MPC)-68M using Certificate of complete.
mstockstill on DSK4VPTVN1PROD with NOTICES
comply with the terms, conditions, and
Compliance (CoC) No. 1014, Consistent with subpart K of part 72
specifications of the CoCs for the
Amendment No. 8, Rev. 1.1 of title 10 of the Code of Federal
approved cask model it uses. Section
Regulations (10 CFR), a general license
72.7 allows the Commission to grant
1 The licensee’s application referred to is issued for the storage of spent fuel in
exemptions from the requirements of 10
Amendment 8; since that time, Amendment 8 has
been revised. (On February 16, 2016, Amendment is the subject of this exemption because none of the
CFR part 72 if the exemption is
8, Rev. 1 to CoC 1014 became effective.) The changes in the revision revised the thoria contents authorized by law, will not endanger
revision does not impact the exemption request that or the physical characteristics of the storage cask. life or property or the common defense
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![Federal Register / Vol. 81, No. 51 / Wednesday, March 16, 2016 / Notices 14139
The exemption is effective upon please contact the NRC’s Public subject of collection; and (4) ways to
issuance. Document Room (PDR) reference staff at minimize the burden of collections on
Dated at Rockville, Maryland, this 8th day 1–800–397–4209, 301–415–4737, or by respondents, including the use of
of March, 2016. email to pdr.resource@nrc.gov. The automated collection techniques or
For the Nuclear Regulatory Commission. ADAMS accession number for each other forms of information technology.
Steve Ruffin, document referenced in this document Comments to the RRB or OIRA must
Acting Branch Chief, Spent Fuel Licensing (if that document is available in contain the OMB control number of the
Branch, Division of Spent Fuel Management, ADAMS) is provided the first time that ICR. For proper consideration of your
Office of Nuclear Material Safetyand a document is referenced. comments, it is best if the RRB and
Safeguards. • NRC’s PDR: You may examine and OIRA receive them within 30 days of
[FR Doc. 2016–05955 Filed 3–15–16; 8:45 am] purchase copies of public documents at the publication date.
BILLING CODE 7590–01–P the NRC’s PDR, Room O1–F21, One 1. Title and purpose of information
White Flint North, 11555 Rockville collection: Employer Reporting; 3220–
Pike, Rockville, Maryland 20852. 0005. Under Section 9 of the Railroad
NUCLEAR REGULATORY FOR FURTHER INFORMATION CONTACT: Retirement Act (RRA), and Section 6 of
COMMISSION Robert Pettis, Office of Nuclear Reactor the Railroad Unemployment Insurance
Regulation, telephone: 301–415–3214; Act (RUIA), railroad employers are
[NRC–2011–0011] required to submit reports of employee
email: Robert.Pettis@nrc.gov; Kenneth
Karwoski, Office of Nuclear Reactor service and compensation to the RRB as
Criteria and Design Features for
Regulation, telephone: 301–415–2752; needed for administering the RRA and
Inspection of Water-Control Structures
email: Kenneth.Karwoski@nrc.gov; or RUIA. To pay benefits due on a
Associated With Nuclear Power Plants; deceased employee’s earnings records or
Correction Mark Orr, Office of Nuclear Regulatory
Research, telephone: 301–415–6003; determine entitlement to, and amount of
AGENCY: Nuclear Regulatory email: Mark.Orr@nrc.gov. All are on the annuity applied for, it is necessary at
Commission. staff of the U.S. Nuclear Regulatory times to obtain from railroad employers
ACTION: Regulatory Guide; issuance; Commission, Washington, DC 20555– current (lag) service and compensation
correction. 0001. not yet reported to the RRB through the
annual reporting process. The reporting
SUPPLEMENTARY INFORMATION: In the FR requirements are specified in 20 CFR
SUMMARY: The U.S. Nuclear Regulatory
Commission (NRC) is correcting a notice on February 18, 2016, in FR Doc. 2016– 209.6 and 209.7.
that was published in the Federal 03346, on page 8254, in the third The RRB currently utilizes Form G–
Register (FR) on February 18, 2016, column, the last line of the first 88A.1, Notice of Retirement and
regarding the issuance of Revision 2 of paragraph, correct ‘‘ML093060317’’ to Verification of Date Last Worked, Form
Regulatory Guide (RG) 1.127, ‘‘Criteria read ‘‘ML102380594.’’ G–88A.2, Notice of Retirement and
and Design Features for Inspection of Dated at Rockville, Maryland this 10th day Request for Service Needed for
Water-Control Structures Associated of March, 2016. Eligibility, and Form AA–12, Notice of
with Nuclear Power Plants.’’ This action For the Nuclear Regulatory Commission. Death and Compensation, to obtain the
is necessary to correct an ADAMS Thomas H. Boyce, required lag service and related
accession number. Chief, Regulatory Guidance and Generic information from railroad employers.
Issues Branch, Division of Engineering, Office Form G–88A.1 is sent by the RRB via a
DATES: The correction is effective March
of Nuclear Regulatory Research. computer-generated listing or
16, 2016. transmitted electronically via the RRB’s
[FR Doc. 2016–05909 Filed 3–15–16; 8:45 am]
ADDRESSES: Please refer to Docket ID Employer Reporting System (ERS) to
BILLING CODE 7590–01–P
NRC–2011–0011 when contacting the employers. ERS consists of a series of
NRC about the availability of screens with completion instructions
information regarding this document. and collects essentially the same
You may obtain publicly-available RAILROAD RETIREMENT BOARD information as the approved manual
information related to this document version. Form G–88A.1 is used for the
using any of the following methods: Agency Forms Submitted for OMB
Review, Request for Comments specific purpose of verifying
• Federal Rulemaking Web site: Go to information previously provided to the
http://www.regulations.gov and search Summary: In accordance with the RRB regarding the date last worked by
for Docket ID NRC–2011–0011. Address Paperwork Reduction Act of 1995 (44 an employee. If the information is
questions about NRC dockets to Carol U.S.C. Chapter 35), the Railroad correct, the employer need not reply. If
Gallagher; telephone: 301–415–3463; Retirement Board (RRB) is forwarding the information is incorrect, the
email: Carol.Gallagher@nrc.gov. For an Information Collection Request (ICR) employer is asked to provide corrected
technical questions, contact the to the Office of Information and information. Form G–88A.2 is used by
individual(s) listed in the FOR FURTHER Regulatory Affairs (OIRA), Office of the RRB to secure lag service and
INFORMATION CONTACT section of this Management and Budget (OMB). Our compensation information when it is
document. ICR describes the information we seek needed to determine benefit eligibility.
• NRC’s Agencywide Documents to collect from the public. Review and Form AA–12 obtains a report of lag
Access and Management System approval by OIRA ensures that we service and compensation from the last
mstockstill on DSK4VPTVN1PROD with NOTICES
(ADAMS): You may obtain publicly- impose appropriate paperwork burdens. railroad employer of a deceased
available documents online in the The RRB invites comments on the employee. This report covers the lag
ADAMS Public Documents collection at proposed collections of information to period between the date of the latest
http://www.nrc.gov/reading-rm/ determine (1) the practical utility of the record of employment processed by the
adams.html. To begin the search, select collections; (2) the accuracy of the RRB and the date an employee last
‘‘ADAMS Public Documents’’ and then estimated burden of the collections; (3) worked, the date of death or the date the
select ‘‘Begin Web-based ADAMS ways to enhance the quality, utility, and employee may have been entitled to
Search.’’ For problems with ADAMS, clarity of the information that is the benefits under the Social Security Act.
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Document Created: 2016-03-15 23:44:23
Document Modified: 2016-03-15 23:44:23
| Category | Regulatory Information | |
| Collection | Federal Register | |
| sudoc Class | AE 2.7: GS 4.107: AE 2.106: | |
| Publisher | Office of the Federal Register, National Archives and Records Administration | |
| Section | Notices | |
| Action | Exemption; issuance. | |
| Dates | March 16, 2016. | |
| Contact | Bernard White, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone: 301-415-6577; email: [email protected] | |
| FR Citation | 81 FR 14135 |
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