81 FR 89511 - Duke Energy Florida, Inc., LLC; Crystal River Unit 3 Nuclear Generating Plant
NUCLEAR REGULATORY COMMISSION Federal Register Volume 81, Issue 238 (December 12, 2016)
Federal Register Volume 81, Issue 238 (December 12, 2016)
| Page Range | 89511-89514 | |
| FR Document | 2016-29712 |
[Federal Register Volume 81, Number 238 (Monday, December 12, 2016)] [Notices] [Pages 89511-89514] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2016-29712] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket No. 50-302; NRC-2016-0253] Duke Energy Florida, Inc., LLC; Crystal River Unit 3 Nuclear Generating Plant AGENCY: Nuclear Regulatory Commission. ACTION: Exemption; issuance. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing a partial exemption from three record keeping requirements in its regulations in response to a September 14, 2016, request from Duke Energy Florida, (DEF, or the licensee). Specifically, the licensee requested that the Crystal River Unit 3 Nuclear Generating Plant (CR- 3), be granted a partial exemption from regulations that require retention of records for certain systems, structures, and components. DATES: The exemption was issued on November 30, 2016. ADDRESSES: Please refer to Docket ID NRC-2016-0253 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-2016-0253. 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]. The ADAMS accession number for each document referenced (if it available in ADAMS) is provided the first time that a document is referenced. 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: John Hickman, Office of Nuclear Material Safety and Safeguards; U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-3017; email: [email protected]. SUPPLEMENTARY INFORMATION: I. Background The CR-3 facility is a decommissioning power reactor located in Citrus County, Florida. The licensee, DEF, is the holder of CR-3 Facility Operating License No. DPR-72. The CR-3 has been shutdown since September 26, 2009. Subsequently, the licensee determined that issues with containment integrity could not be satisfactorily resolved and decided not to attempt to restart the facility. On May 28, 2011, DEF completed the removal of fuel from the reactor vessel at CR-3. By letter dated February 20, 2013 (ADAMS Accession No. ML13056A005), DEF submitted to the NRC a certification in accordance with section 50.82(a)(1)(i) of title 10 of the Code of Federal Regulations (10 CFR), indicating it would permanently cease power operations, and with Sec. 50.82(a)(1)(ii) that it had permanently defueled the reactor vessel at CR-3. Because CR-3 is a permanently shutdown and defueled facility, and in accordance with Sec. 50.82(a)(2), DEF is no longer authorized to operate the reactor or emplace nuclear fuel into the reactor vessel. The licensee is still authorized to possess and store irradiated (i.e., spent) nuclear fuel. The spent fuel is currently being stored onsite in a spent fuel pool (SFP). II. Request/Action By letter dated September 14, 2016 (ADAMS Accession No. ML16258A058), DEF filed a request for NRC approval of an exemption from the record retention requirements of: (1) 10 CFR part 50, appendix B, Criterion XVII, which requires certain records be retained consistent with other regulatory requirements; (2) Sec. 50.59(d)(3), which requires certain records be maintained until termination of a license issued [[Page 89512]] pursuant to 10 CFR part 50; and (3) Sec. 50.71(c), which requires certain records be maintained consistent with various elements of the NRC regulations, facility technical specifications, and other licensing basis documents. The licensee is requesting an exemption from the requirement to retain these records when the following conditions are satisfied: (1) The CR-3 licensing basis requirements previously applicable to the nuclear power unit and associated systems, structures and components (SSCs) are no longer effective (i.e., removed from the Final Safety Analysis Report and/or Technical Specifications by appropriate change mechanisms); or (2) for SSCs associated with safe storage of fuel in the SFPs when spent fuel has been completely removed from the SFPs, and the associated licensing bases are no longer effective. The licensee cites record retention exemptions granted to Zion Nuclear Power Station, Units 1 and 2 (76 FR 39134), Millstone Power Station, Unit 1, (72 FR 5755), and Haddam Neck Plant (70 FR 54587), as examples of the NRC granting similar requests. Records associated with residual radiological activity and with programmatic controls necessary to support decommissioning, such as security and quality assurance, are not affected by the exemption request, and would be retained as decommissioning records until the termination of the CR-3 license. In addition, the licensee did not request an exemption from 10 CFR part 50, appendix A, Criterion 1, which requires certain records to be maintained ``throughout the life of the unit,'' because CR-3 is not a general design criteria facility. Nor did DEF request an exemption associated with any record keeping requirements for storage of spent fuel at the CR-3 ISFSI under 10 CFR part 50, the general license requirements of 10 CFR part 72, or for the other requirements of 10 CFR part 50 or Facility Operating License No. DPR-72 applicable to the decommissioning and dismantlement of the CR-3 plant. III. Discussion Pursuant to Sec. 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 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. However, the Commission will not consider granting an exemption unless special circumstances are present. Special circumstances are described in Sec. 50.12(a)(2). According to the Final Safety Analysis Report, revision 38, submitted May 25, 2016 (ADAMS Accession No. ML16172A182), the majority of plant components at CR-3 no longer meet the definition of safety related in Sec. 50.2. The September 14, 2016 (ADAMS Accession No. ML16258A058) exemption application states that the CR-3 nuclear steam supply system and balance of plant SSCs will be abandoned in place pending dismantlement. These SSCs are no longer operable or maintained except as required to support safe storage of spent fuel in the SFP or those that are needed to meet other regulatory requirements or are needed to support other site facilities (e.g., radioactive waste handling, Heating, Ventilation, and Air Conditioning (HVAC), etc.). The licensee's justification for eliminating records is that these SSCs have been (or will be) removed from service under the NRC license, dismantled or demolished, and that therefore maintenance of these records will not serve any function regulated by the NRC. While DEF stated that it would retain the records required as the project transitions from current plant conditions to a plant with spent fuel only in dry storage, the transition will remove the safety and business need for the maintenance of most records. As the SSCs are removed from the licensing basis and the need for the associated records is eliminated, the licensee proposes that they be exempted from the records retention requirements for SSCs and historical activities associated with (1) the CR-3 licensing basis requirements previously applicable to the nuclear power unit and associated systems, structures and components (SSCs) that are no longer effective (i.e., removed from the Final Safety Analysis Report and/or Technical Specifications by appropriate change mechanisms); or (2) for SSCs associated with safe storage of fuel in the SFPs when spent fuel has been completely removed from the SFPs, and the associated licensing bases are no longer effective, thereby eliminating the associated regulatory and economic burdens of creating alternative storage locations, relocating records, and retaining irrelevant records. The exemption request states that all records necessary for spent fuel and spent fuel storage SSCs and activities have been, and will continue to be, retained for the SFP throughout its functional life. Similar to other plant records, once the SFP is emptied of fuel, drained and ready for demolition, there will be no safety-significant function or other regulatory need for retaining certain SFP-related records. The DEF stated that some records related to the nuclear steam supply system, balance of plant, and SFP will continue to be maintained under NRC regulations due to residual radioactivity. The radiological and other necessary programmatic controls (such as security and quality assurance) for the facility and decommissioning activities are and will continue to be appropriately addressed through the license and current plant documents such as the updated Final Safety Analysis Report and Technical Specifications. These programmatic elements and their associated records would be unaffected by the requested exemption. The Exemption Is Authorized by Law The NRC has determined that granting the licensee's proposed exemption will not result in a violation of the Atomic Energy Act of 1954, as amended, other laws, or other Commission regulations. Therefore, the exemption from the record keeping requirements of 10 CFR 50.71(c); 10 CFR part 50, appendix B, Criterion XVII; and 10 CFR 50.59(d)(3) is authorized by law. The Exemption Presents No Undue Risk to Public Health and Safety Removal of the underlying SSCs associated with the records for which DEF has requested an exemption from record keeping requirements will not have adverse public health and safety impact because the subject SSCs would no longer have a safety function at the permanently shutdown facility, would be removed from the licensing basis by the license, and will be disposed of by the licensee when active decommissioning begins. Elimination of records associated with the removed SSCs therefore would not have an impact on public health and safety. The requested partial exemption from the record keeping requirements of 10 CFR 50.71(c); 10 CFR part 50, appendix B, Criterion XVII; and 10 CFR 50.59(d)(3) for records associated with (1) the CR-3 licensing basis requirements previously applicable to the nuclear power unit and associated systems, structures and components (SSCs) that are no longer effective (i.e., removed from the Final Safety Analysis Report and/or Technical Specifications by appropriate change mechanisms); or (2) for SSCs associated with safe storage of fuel in the SFPs when spent fuel has been completely removed from the SFPs, and the associated licensing bases are no longer effective, is administrative in nature and will have no impact on [[Page 89513]] any remaining decommissioning activities or on radiological effluents. The exemption will only advance the schedule for disposition of the specified records, which would otherwise be retained until license termination requiring the expenditure of resources by the licensee. The Exemption Is Consistent With Common Defense and Security The elimination of the record keeping requirements does not involve information or activities that could potentially impact the common defense and security of the United States. Upon dismantlement of the affected SSCs, the records have no functional purpose relative to maintaining the safe operation of the SSCs, maintaining conditions that would affect the ongoing health and safety of workers or the public, or informing decisions related to nuclear security. Rather, the exemption requested is administrative in nature and would only advance the current schedule for disposition of the specified records, which would otherwise be retained until license termination. This allows the licensee to not expend resources maintaining records that have no benefit or safety purpose. Therefore, the partial exemption from the record keeping requirements of 10 CFR 50.71(c); 10 CFR part 50, appendix B, Criterion XVII; and 10 CFR 50.59(d)(3) for the types records associated with (1) the CR-3 licensing basis requirements previously applicable to the nuclear power unit and associated systems, structures and components (SSCs) that are no longer effective (i.e., removed from the Final Safety Analysis Report and/or Technical Specifications by appropriate change mechanisms); or (2) for SSCs associated with safe storage of fuel in the SFPs when spent fuel has been completely removed from the SFPs, and the associated licensing bases are no longer effective, is consistent with the common defense and security. Special Circumstances Section 50.12(a)(2) states, in part: ``The Commission will not consider granting an exemption unless special circumstances are present. Special circumstances are present whenever: . . . (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; (iii) Compliance would result in undue hardship or other costs that are significantly in excess of those contemplated when the regulation was adopted . . . .'' Criterion XVII of 10 CFR part 50, appendix B, states in part: ``Sufficient records shall be maintained to furnish evidence of activities affecting quality.'' Section 50.59(d)(3) states in part: ``The records of changes in the facility must be maintained until the termination of an operating license issued under this part. . . .'' Section 50.71(c), states in part: ``Records that are required by the regulations in this part or part 52 of this chapter, by license condition, or by technical specifications must be retained for the period specified by the appropriate regulation, license condition, or technical specification. If a retention period is not otherwise specified, these records must be retained until the Commission terminates the facility license . . . .'' In the Statements of Consideration (SOC) for the final rulemaking, ``Retention Periods for Records'' (53 FR 19240; May 27, 1988), in response to public comments received during the rulemaking process, the NRC stated that records must be retained ``for NRC to ensure compliance with the safety and health aspects of the nuclear environment and for the NRC to accomplish its mission to protect the public health and safety.'' In the SOC the Commission also explained that requiring licensees to maintain adequate records assists the NRC ``in judging compliance and noncompliance, to act on possible noncompliance, and to examine facts as necessary following any incident.'' These regulations apply to licensees in decommissioning despite the fact that, during the decommissioning process, safety-related SSCs are retired or disabled and subsequently removed from NRC licensing basis documents by appropriate change mechanisms. Appropriate removal of an SSC from the licensing basis requires either a determination by the licensee or an approval from the NRC that the SSC no longer has the potential to cause an accident, event, or other problem which would adversely impact public health and safety. The records subject to removal under the requested exemption are those associated with SSCs that had been important to safety during power operation or operation of the SFP, but are no longer capable of causing an event, incident, or condition that would adversely impact public health and safety, given their appropriate removal from the licensing basis documents. If the SSCs no longer have the potential to cause these scenarios, then certain records associated with these SSCs would not be necessary to assist the NRC in determining compliance and noncompliance, taking action on possible noncompliance, and examining facts following an incident. Therefore, their retention would not serve the underlying purpose of the rule. Retention of certain records associated with SSCs that are or will no longer be part of the facility serves no safety or regulatory purpose, nor does it serve the underlying purpose of the rule of maintaining compliance with the safety and health aspects of the nuclear environment in order to accomplish the NRC's mission. Accordingly, special circumstances are present which the NRC may consider, pursuant to Sec. 50.12(a)(2)(ii), to grant the requested exemption permitting the disposal of records associated with (1) the CR-3 licensing basis requirements previously applicable to the nuclear power unit and associated systems, structures and components (SSCs) that are no longer effective (i.e., removed from the Final Safety Analysis Report and/or Technical Specifications by appropriate change mechanisms); or (2) for SSCs associated with safe storage of fuel in the SFPs when spent fuel has been completely removed from the SFPs, and the associated licensing bases are no longer effective. Records that continue to serve the underlying purpose of the rule, that is, to maintain compliance and to protect public health and safety in support of the NRC's mission, will continue to be retained pursuant to the regulations in 10 CFR part 50 and 10 CFR part 72. The retained records not subject to the exemption include those associated with programmatic controls, such as those pertaining to residual radioactivity, which continue to be required for eventual decommissioning; security, emergency planning and quality assurance, programs which remain in effect; as well as records associated with the Independent Spent Fuel Storage Installation and spent fuel assemblies. The retention of records required by 10 CFR 50.71(c); 10 CFR part 50, appendix B, Criterion XVII; and 10 CFR 50.59(d)(3) provides assurance that records associated with SSCs will be captured, indexed, and stored in an environmentally suitable and retrievable condition. Given the volume of records associated with the SSCs, compliance with the records retention rule results in a considerable cost to the licensee. Retention of the volume of records associated with the SSCs during the operational phase is appropriate to serve the underlying purpose of determining compliance and noncompliance, taking action on possible noncompliance, and [[Page 89514]] examining facts following an incident, as discussed previously in this notice. However, the cost of retaining operational phase records beyond the operations phase until the termination of the license may not have been fully considered when the records retention rule was put in place. As such, compliance with the rule would result in an undue cost in excess of that contemplated when the rule was adopted. Accordingly, special circumstances are present which the NRC may consider, pursuant to Sec. 50.12(a)(2)(iii), to grant the requested exemption. Environmental Considerations Pursuant to Sec. 51.22(b) and (c)(25), the granting of an exemption from the requirements of any regulation in Chapter I of 10 CFR is a categorical exclusion provided that (i) there is no significant hazards consideration; (ii) there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite; (iii) there is no significant increase in individual or cumulative public or occupational radiation exposure; (iv) there is no significant construction impact; (v) there is no significant increase in the potential for or consequences from radiological accidents; and (vi) the requirements from which an exemption is sought are among those identified in 10 CFR 51.22(c)(25)(vi). The NRC has determined that approval of the exemption request involves no significant hazards consideration because allowing the licensee exemption from the record keeping requirements of 10 CFR 50.71(c); 10 CFR part 50, appendix B, Criterion XVII; and 10 CFR 50.59(d)(3) at the decommissioning CR-3 does not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety (Sec. 50.92(c)). Likewise, there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite, and no significant increase in individual or cumulative public or occupational radiation exposure. The exempted regulations are not associated with construction, so there is no significant construction impact. The exempted regulations do not concern the source term (i.e., potential amount of radiation involved in an accident) or accident mitigation; therefore, there is no significant increase in the potential for, or consequences from, radiological accidents. Allowing the licensee partial exemption from the record retention requirements for which the exemption is sought involves record keeping requirements (Sec. 51.22(c)(35)(vi)(A)), as well as reporting requirements (Sec. 51.22(c)(35)(vi)(B)). Therefore, pursuant to Sec. 51.22(b) and (c)(25), no environmental impact statement or environmental assessment need be prepared in connection with the approval of this exemption request. IV. Conclusions The NRC has determined that the requested partial exemption from the record keeping requirements of 10 CFR 50.71(c); 10 CFR part 50, appendix B, Criterion XVII; and 10 CFR 50.59(d)(3) will not present an undue risk to the public health and safety. The destruction of the identified records will not impact remaining decommissioning activities; plant operations, configuration, and/or radiological effluents; operational and/or installed SSCs that are quality-related or important to safety; or nuclear security. The NRC has determined that the destruction of the identified records does not involve information or activities that could potentially impact the common defense and security of the United States. The purpose for the record keeping regulations is to assist the NRC in carrying out its mission to protect the public health and safety by ensuring that the licensing and design basis of the facility is understood, documented, preserved and retrievable in such a way that will aid the NRC in determining compliance and noncompliance, taking action on possible noncompliance, and examining facts following an incident. Since the CR-3 SSCs that were safety-related or important to safety during operations have been or will be removed from the licensing basis and removed from the plant, the staff finds that the records associated with (1) the CR-3 licensing basis requirements previously applicable to the nuclear power unit and associated systems, structures and components (SSCs) that are no longer effective (i.e., removed from the Final Safety Analysis Report and/or Technical Specifications by appropriate change mechanisms); or (2) for SSCs associated with safe storage of fuel in the SFPs when spent fuel has been completely removed from the SFPs, and the associated licensing bases are no longer effective will no longer be required to achieve the underlying purpose of the records retention rule. Accordingly, the Commission has determined that, pursuant to Sec. 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, and that special circumstances are present. Therefore, the Commission hereby grants Duke Energy Florida a one-time partial exemption from the record keeping requirements of 10 CFR 50.71(c); 10 CFR part 50, appendix B, Criterion XVII; and 10 CFR 50.59(d)(3) for the Crystal River Unit 3 Nuclear Generating Plant to allow removal of records associated with (1) the CR-3 licensing basis requirements previously applicable to the nuclear power unit and associated systems, structures and components (SSCs) that are no longer effective (i.e., removed from the Final Safety Analysis Report and/or Technical Specifications by appropriate change mechanisms); or (2) for SSCs associated with safe storage of fuel in the SFPs when spent fuel has been completely removed from the SFPs, and the associated licensing bases are no longer effective. Records associated with residual radiological activity and with programmatic controls necessary to support decommissioning, such as security, emergency planning, spent fuel management and quality assurance are not affected by the exemption request and are required to be retained consistent with regulatory existing requirement as decommissioning records until the termination of the CR-3 license. This exemption is effective upon issuance. Dated at Rockville, Maryland, this 30th day of November 2016. For the Nuclear Regulatory Commission. Andrea Kock, Deputy Director, Division of Decommissioning, Uranium Recovery and Waste Programs, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2016-29712 Filed 12-9-16; 8:45 am] BILLING CODE 7590-01-P
![Federal Register / Vol. 81, No. 238 / Monday, December 12, 2016 / Notices 89511
select ‘‘Begin Web-based ADAMS does not affect any existing licenses or please contact the NRC’s Public
Search.’’ For problems with ADAMS, agreements. However, RG 1.25 should Document Room (PDR) reference staff at
please contact the NRC’s Public not be used in future requests or 1–800–397–4209, 301–415–4737, or by
Document Room (PDR) reference staff at applications for NRC licensing actions. email to pdr.resource@nrc.gov. The
1–800–397–4209, 301–415–4737, or by Dated at Rockville, Maryland, this 5th day ADAMS accession number for each
email to pdr.resource@nrc.gov. The of December, 2016. document referenced (if it available in
withdrawal notice for RG 1.25 is For the Nuclear Regulatory Commission. ADAMS) is provided the first time that
available in ADAMS under accession Thomas H. Boyce,
a document is referenced.
No. ML16105A081. • NRC’s PDR: You may examine and
Chief, Regulatory Guidance and Generic
• NRC’s PDR: You may examine and Issues Branch, Division of Engineering, Office
purchase copies of public documents at
purchase copies of public documents at of Nuclear Regulatory Research. the NRC’s PDR, Room O1–F21, One
the NRC’s PDR, Room O1–F21, One [FR Doc. 2016–29661 Filed 12–9–16; 8:45 am]
White Flint North, 11555 Rockville
White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.
BILLING CODE 7590–01–P
Pike, Rockville, Maryland 20852. FOR FURTHER INFORMATION CONTACT: John
FOR FURTHER INFORMATION CONTACT: John Hickman, Office of Nuclear Material
Parillo, Office of Nuclear Reactor NUCLEAR REGULATORY Safety and Safeguards; U.S. Nuclear
Regulation, telephone 301–415–1344; COMMISSION Regulatory Commission, Washington,
email John.Parillo@nrc.gov or Mark Orr, DC 20555–0001; telephone: 301–415–
Office of Nuclear Regulatory Research, [Docket No. 50–302; NRC–2016–0253]
3017; email: John.Hickman@nrc.gov.
telephone: 301–415–6003; email: SUPPLEMENTARY INFORMATION:
Duke Energy Florida, Inc., LLC; Crystal
Mark.Orr@nrc.gov. Both are staff of the
River Unit 3 Nuclear Generating Plant I. Background
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001. AGENCY: Nuclear Regulatory The CR–3 facility is a
SUPPLEMENTARY INFORMATION: Regulatory Commission. decommissioning power reactor located
guides may be withdrawn by the NRC ACTION: Exemption; issuance. in Citrus County, Florida. The licensee,
when their guidance no longer provides DEF, is the holder of CR–3 Facility
useful information, or is superseded by SUMMARY: The U.S. Nuclear Regulatory Operating License No. DPR–72. The CR–
technological innovations, Commission (NRC) is issuing a partial 3 has been shutdown since September
congressional actions, or other events. exemption from three record keeping 26, 2009. Subsequently, the licensee
The withdrawal of an RG should be requirements in its regulations in determined that issues with
thought of as the final revision of the response to a September 14, 2016, containment integrity could not be
guide. request from Duke Energy Florida, (DEF, satisfactorily resolved and decided not
The NRC issued RG 1.25, or the licensee). Specifically, the to attempt to restart the facility. On May
‘‘Assumptions used for Evaluating the licensee requested that the Crystal River 28, 2011, DEF completed the removal of
Potential Radiological Consequences of Unit 3 Nuclear Generating Plant (CR–3), fuel from the reactor vessel at CR–3. By
a Fuel Handling Accident in the Fuel be granted a partial exemption from letter dated February 20, 2013 (ADAMS
Handling and Storage Facility for regulations that require retention of Accession No. ML13056A005), DEF
Boiling and Pressurized Water records for certain systems, structures, submitted to the NRC a certification in
Reactors,’’ in March 1972 to provide and components. accordance with section 50.82(a)(1)(i) of
guidance for the evaluation of the DATES: The exemption was issued on title 10 of the Code of Federal
design basis fuel handling accident to November 30, 2016. Regulations (10 CFR), indicating it
demonstrate compliance with the NRC’s ADDRESSES: Please refer to Docket ID would permanently cease power
regulations in part 100 of Title 10 of the NRC–2016–0253 when contacting the operations, and with § 50.82(a)(1)(ii)
Code of Federal Regulations. The NRC NRC about the availability of that it had permanently defueled the
is withdrawing RG 1.25 because the information regarding this document. reactor vessel at CR–3. Because CR–3 is
guidance contained in RG 1.25 has been You may obtain publicly-available a permanently shutdown and defueled
superseded by more current guidance, information related to this document facility, and in accordance with
which has been incorporated into RG using any of the following methods: § 50.82(a)(2), DEF is no longer
1.183, ‘‘Alternative Radiological Source • Federal Rulemaking Web site: Go to authorized to operate the reactor or
Terms for Evaluating Design Basis http://www.regulations.gov and search emplace nuclear fuel into the reactor
Accidents at Nuclear Power Reactors,’’ for Docket ID NRC–2016–0253. Address vessel. The licensee is still authorized to
and RG 1.195, ‘‘Methods and questions about NRC dockets to Carol possess and store irradiated (i.e., spent)
Assumptions for Evaluating Gallagher; telephone: 301–415–3463; nuclear fuel. The spent fuel is currently
Radiological Consequences of Design email: Carol.Gallagher@nrc.gov. For being stored onsite in a spent fuel pool
Basis Accidents at Light-Water Nuclear technical questions, contact the (SFP).
Power Reactors.’’ The information in RG individual listed in the FOR FURTHER
1.183 provides guidance for new and INFORMATION CONTACT section of this
II. Request/Action
existing light-water reactor (LWR) plants document. By letter dated September 14, 2016
that have adopted the alternative source • NRC’s Agencywide Documents (ADAMS Accession No. ML16258A058),
term (AST), and RG 1.195 provides Access and Management System DEF filed a request for NRC approval of
guidance for those LWR plants that have (ADAMS): You may obtain publicly- an exemption from the record retention
mstockstill on DSK3G9T082PROD with NOTICES
not adopted the AST. available documents online in the requirements of: (1) 10 CFR part 50,
The withdrawal of RG 1.25 does not ADAMS Public Documents collection at appendix B, Criterion XVII, which
alter any prior or existing NRC licensing http://www.nrc.gov/reading-rm/ requires certain records be retained
approval or the acceptability of licensee adams.html. To begin the search, select consistent with other regulatory
commitments to RG 1.25. Although RG ‘‘ADAMS Public Documents’’ and then requirements; (2) § 50.59(d)(3), which
1.25 is withdrawn, current licensees select ‘‘Begin Web-based ADAMS requires certain records be maintained
may continue to use it, and withdrawal Search.’’ For problems with ADAMS, until termination of a license issued
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examining facts following an incident, for, or consequences from, radiological exemption is authorized by law, will not
as discussed previously in this notice. accidents. Allowing the licensee partial present an undue risk to the public
However, the cost of retaining exemption from the record retention health and safety, and is consistent with
operational phase records beyond the requirements for which the exemption the common defense and security, and
operations phase until the termination is sought involves record keeping that special circumstances are present.
of the license may not have been fully requirements (§ 51.22(c)(35)(vi)(A)), as Therefore, the Commission hereby
considered when the records retention well as reporting requirements grants Duke Energy Florida a one-time
rule was put in place. As such, (§ 51.22(c)(35)(vi)(B)). partial exemption from the record
compliance with the rule would result Therefore, pursuant to § 51.22(b) and keeping requirements of 10 CFR
in an undue cost in excess of that (c)(25), no environmental impact 50.71(c); 10 CFR part 50, appendix B,
contemplated when the rule was statement or environmental assessment Criterion XVII; and 10 CFR 50.59(d)(3)
adopted. Accordingly, special need be prepared in connection with the for the Crystal River Unit 3 Nuclear
circumstances are present which the approval of this exemption request. Generating Plant to allow removal of
NRC may consider, pursuant to records associated with (1) the CR–3
IV. Conclusions
§ 50.12(a)(2)(iii), to grant the requested licensing basis requirements previously
exemption. The NRC has determined that the applicable to the nuclear power unit
requested partial exemption from the and associated systems, structures and
Environmental Considerations record keeping requirements of 10 CFR components (SSCs) that are no longer
Pursuant to § 51.22(b) and (c)(25), the 50.71(c); 10 CFR part 50, appendix B, effective (i.e., removed from the Final
granting of an exemption from the Criterion XVII; and 10 CFR 50.59(d)(3) Safety Analysis Report and/or Technical
requirements of any regulation in will not present an undue risk to the Specifications by appropriate change
Chapter I of 10 CFR is a categorical public health and safety. The mechanisms); or (2) for SSCs associated
exclusion provided that (i) there is no destruction of the identified records will
with safe storage of fuel in the SFPs
significant hazards consideration; (ii) not impact remaining decommissioning
when spent fuel has been completely
there is no significant change in the activities; plant operations,
removed from the SFPs, and the
types or significant increase in the configuration, and/or radiological
associated licensing bases are no longer
amounts of any effluents that may be effluents; operational and/or installed
effective.
released offsite; (iii) there is no SSCs that are quality-related or Records associated with residual
significant increase in individual or important to safety; or nuclear security. radiological activity and with
cumulative public or occupational The NRC has determined that the programmatic controls necessary to
radiation exposure; (iv) there is no destruction of the identified records
support decommissioning, such as
significant construction impact; (v) does not involve information or
security, emergency planning, spent fuel
there is no significant increase in the activities that could potentially impact
management and quality assurance are
potential for or consequences from the common defense and security of the
not affected by the exemption request
radiological accidents; and (vi) the United States.
The purpose for the record keeping and are required to be retained
requirements from which an exemption
regulations is to assist the NRC in consistent with regulatory existing
is sought are among those identified in
carrying out its mission to protect the requirement as decommissioning
10 CFR 51.22(c)(25)(vi).
The NRC has determined that public health and safety by ensuring records until the termination of the CR–
approval of the exemption request that the licensing and design basis of the 3 license.
This exemption is effective upon
involves no significant hazards facility is understood, documented,
preserved and retrievable in such a way issuance.
consideration because allowing the
licensee exemption from the record that will aid the NRC in determining Dated at Rockville, Maryland, this 30th day
keeping requirements of 10 CFR compliance and noncompliance, taking of November 2016.
50.71(c); 10 CFR part 50, appendix B, action on possible noncompliance, and For the Nuclear Regulatory Commission.
Criterion XVII; and 10 CFR 50.59(d)(3) examining facts following an incident. Andrea Kock,
at the decommissioning CR–3 does not Since the CR–3 SSCs that were safety- Deputy Director, Division of
(1) involve a significant increase in the related or important to safety during Decommissioning, Uranium Recovery and
probability or consequences of an operations have been or will be removed Waste Programs, Office of Nuclear Material
accident previously evaluated; (2) create from the licensing basis and removed Safety and Safeguards.
the possibility of a new or different kind from the plant, the staff finds that the [FR Doc. 2016–29712 Filed 12–9–16; 8:45 am]
of accident from any accident records associated with (1) the CR–3 BILLING CODE 7590–01–P
previously evaluated; or (3) involve a licensing basis requirements previously
significant reduction in a margin of applicable to the nuclear power unit
safety (§ 50.92(c)). Likewise, there is no and associated systems, structures and NUCLEAR REGULATORY
significant change in the types or components (SSCs) that are no longer COMMISSION
significant increase in the amounts of effective (i.e., removed from the Final [Docket Nos. 50–387, 50–388, and 72–28;
any effluents that may be released Safety Analysis Report and/or Technical NRC–2016–0187]
offsite, and no significant increase in Specifications by appropriate change
individual or cumulative public or mechanisms); or (2) for SSCs associated In the Matter of Susquehanna Nuclear,
occupational radiation exposure. with safe storage of fuel in the SFPs LLC; Susquehanna Steam Electric
The exempted regulations are not when spent fuel has been completely Station, Units 1 and 2; Order
mstockstill on DSK3G9T082PROD with NOTICES
associated with construction, so there is removed from the SFPs, and the Approving Indirect Transfer of Facility
no significant construction impact. The associated licensing bases are no longer Operating Licenses
exempted regulations do not concern effective will no longer be required to AGENCY: Nuclear Regulatory
the source term (i.e., potential amount achieve the underlying purpose of the Commission.
of radiation involved in an accident) or records retention rule. ACTION: Indirect transfer of licenses;
accident mitigation; therefore, there is Accordingly, the Commission has
order.
no significant increase in the potential determined that, pursuant to § 50.12, the
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Document Created: 2018-02-14 09:05:20
Document Modified: 2018-02-14 09:05:20
| 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 | The exemption was issued on November 30, 2016. | |
| Contact | John Hickman, Office of Nuclear Material Safety and Safeguards; U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-3017; email: [email protected] | |
| FR Citation | 81 FR 89511 |
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