Source: https://www.federalregister.gov/documents/2018/07/17/2018-14779/biweekly-notice-applications-and-amendments-to-facility-operating-licenses-and-combined-licenses
Timestamp: 2019-08-23 05:06:16
Document Index: 786009284

Matched Legal Cases: ['art 2', 'art 50', 'art 50', 'art 50', 'art 50', 'art 2']

Comments must be filed by August 16, 2018. A request for a hearing must be filed by September 17, 2018.
33263-33276 (14 pages)
NRC-2018-0140
Dominion Energy Nuclear Connecticut, Inc. (DENC), Docket No. 50-423, Millstone Power Station, Unit No. 3 (MPS3), New London County, Connecticut
Duke Energy Progress, LLC, Docket Nos. 50-325 and 50-324, Brunswick Steam Electric Plant, Units 1 and 2 (Brunswick or BSEP), Brunswick County, North Carolina
Exelon FitzPatrick, LLC and Exelon Generation Company, LLC, Docket No. 50-333, James A. FitzPatrick Nuclear Power Plant (FitzPatrick), Oswego County, New York
Exelon Generation Company, LLC, Docket No. 50-289 and 50-320, Three Mile Island Nuclear Station (TMI), Unit Nos. 1 and 2, Dauphin County, Pennsylvania
Exelon Generation Company, LLC, Docket Nos. 50-352 and 50-353, Limerick Generating Station, Unit Nos. 1 and 2, Montgomery County, Pennsylvania
Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50-171, 50-277, and 50-278, Peach Bottom Atomic Power Station, Unit Nos. 1, 2, and 3, York and Lancaster Counties, Pennsylvania
Southern Nuclear Operating Company, Inc., Docket Nos. 52-025 and 52-026, Vogtle Electric Generating Plant, Unit Nos. 3 and 4, Burke County, Georgia
Tennessee Valley Authority (TVA), Docket Nos. 50-259, 50-260, and 50-296, Browns Ferry Nuclear Plant (BFN), Unit Nos. 1, 2, and 3, Limestone County, Alabama
Duke Energy Progress, LLC, Docket No. 50-400, Shearon Harris Nuclear Power Plant, Unit No. 1, Wake and Chatham Counties, North Carolina
Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Calvert County, Maryland, Exelon Generation Company, LLC, Docket Nos. 50-220 and 50-410, Nine Mile, Point, Nuclear Station, Unit Nos. 1 and 2, Oswego County, New York, Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear Power Plant, Wayne County, New York
Exelon Generation Company, LLC, Docket Nos. 50-237 and 50-249, Dresden Nuclear Power Station (DNPS), Unit Nos. 2 and 3, Grundy County, Illinois
Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457, Braidwood Station, Unit Nos. 1 and 2, Will County, Illinois and Docket Nos. STN 50-454 and STN 50-455, Byron Station, Unit Nos. 1 and 2, Ogle County, Illinois
Southern Nuclear Operating Company, Docket Nos. 50-348 and 50-364, Joseph M. Farley Nuclear Plant, Unit Nos. 1 and 2, Houston County, Alabama
Susquehanna Nuclear, LLC, Docket Nos. 50-387 and 50-388, Susquehanna Steam Electric Station, Unit Nos. 1 and 2, Luzerne County, Pennsylvania
Exelon Generation Company, LLC, Docket Nos. 50-277 and 50-278, Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 (Peach Bottom), York County, Pennsylvania
https://www.federalregister.gov/d/2018-14779 https://www.federalregister.gov/d/2018-14779
This biweekly notice includes all notices of amendments issued, or proposed to be issued, from June 18, 2018, to June 29, 2018. The last biweekly notice was published on July 3, 2018.
Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0140. Address questions about NRC dockets to Jennifer Borges; telephone: 301-287-9127; email: Jennifer.Borges@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document.
Please refer to Docket ID NRC-2018-0140, facility name, unit number(s), plant docket number, application date, and subject when contacting the NRC about the availability of information for this action. You may obtain publicly-available information related to this action by any of the following methods:
Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0140.
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.Start Printed Page 33264
Please include Docket ID NRC-2018-0140, facility name, unit number(s), plant docket number, application date, and subject in your comment submission.
If a hearing is requested, and the Commission has not made a final determination on the issue of no significant hazards consideration, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to establish when the hearing is held. If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing would take place after issuance of the amendment. If the final determination is that the Start Printed Page 33265amendment request involves a significant hazards consideration, then any hearing held would take place before the issuance of the amendment unless the Commission finds an imminent danger to the health or safety of the public, in which case it will issue an appropriate order or rule under 10 CFR part 2.
Documents submitted in adjudicatory proceedings will appear in the NRC's electronic hearing docket which is available to the public at https://adams.nrc.gov/​ehd, unless excluded pursuant to an order of the Commission or the presiding officer. If you do not Start Printed Page 33266have an NRC-issued digital ID certificate as described above, click cancel when the link requests certificates and you will be automatically directed to the NRC's electronic hearing dockets where you will be able to access any publicly available documents in a particular hearing docket. Participants are requested not to include personal privacy information, such as social security numbers, home addresses, or personal phone numbers in their filings, unless an NRC regulation or other law requires submission of such information. For example, in some instances, individuals provide home addresses in order to demonstrate proximity to a facility or site. With respect to copyrighted works, except for limited excerpts that serve the purpose of the adjudicatory filings and would constitute a Fair Use application, participants are requested not to include copyrighted materials in their submission.
Date of amendment request: April 4, 2018. A publicly-available version is in ADAMS under Accession No. ML18100A055.
Description of amendment request: The amendment would revise the MPS3 Technical Specifications (TSs). Specifically, with one Control Building Inlet Ventilation Radiation monitor channel inoperable for greater than 7 days, or if both radiation monitor channels are inoperable, DENC proposes to revise and reformat Action 18 in TS Table 3.3-3, Functional Unit 7.e, “Control Building Inlet Ventilation Radiation,” to allow control room operators to manually place one train of the Control Room Emergency Ventilation System (CREVS) in the emergency mode of operation to provide additional time to restore one channel of Control Building Inlet Ventilation Radiation monitoring to OPERABLE status.
Operation of MPS3 in accordance with the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed change removes an overly restrictive requirement and adds a conservative requirement for actions to be taken when there is a loss of operability of the CREVS actuation instrumentation. This does not increase the probability of an accident previously evaluated since the CREVS actuation itself is not an accident initiator. The proposed change is consistent with standard TSs for Westinghouse plants (NUREG-1431) and provides assurance that the CREVS is in the conservative mode of operation for a response to an accident. Analysis demonstrates that with one train of the CREVS in the emergency mode of operation, control room operators are adequately protected from the radiological consequences of design basis accident events. Therefore, the probability or consequences of an accident previously evaluated is not significantly increased.
Operation of MPS3 in accordance with the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed change does not involve a physical alteration of the plant or change in the methods governing normal plant operation. The proposed change replaces the overly restrictive shutdown requirement with a conservative action to be taken upon loss of CREVS actuation instrumentation operability, thereby avoiding the risk associated with an immediate controlled shutdown. Therefore, the possibility of a new or different kind of accident from any accident previously evaluated is not created.
With one train of CREVS in the emergency mode of operation, DENC has confirmed that MPS3 is in compliance with the current radiological analyses of record for design basis accidents with dose consequences to the control room. Therefore, the proposed change does not affect the design basis analyses and does not alter the assumptions made in the MPS3 accident analysis.
Based on the above, the proposed amendment does not create the possibility of a new or different kind of accident previously evaluated.
Operation of MPS3 in accordance with the proposed change does not involve a significant reduction in the margin of safety. The proposed change revises and reformats the Control Building lnlet Ventilation Radiation TS to place the CREVS in the conservative mode of operation for a response to an accident. The proposed change provides additional time to restore an inoperable radiation monitor channel instead of requiring an immediate controlled plant shutdown and suspension of movement of recently irradiated fuel assemblies, if applicable. A plant shutdown is a transient that may be avoided by providing a limited time to make repairs. In addition, the control room operators are adequately protected from the radiological consequences of design basis accident events with one train of the CREVS in the emergency mode of operation. The potential to avoid a plant transient in conjunction with protecting control room operators offsets any risk associated with the proposed change.
Date of amendment request: April 4, 2018, as supplemented by letter dated May 29, 2018. Publicly-available versions are in ADAMS under Accession Nos. ML18094B058 and ML18149A487, respectively.
Description of amendment request: The amendments would modify the BSEP Technical Specifications (TSs) to relocate the pressure-temperature limit curves to a licensee-controlled Pressure and Temperature Limits Report (PTLR). The amendment request was submitted in accordance with guidance provided in NRC Generic Letter 96-03, “Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protections System Limits,” dated January 31, 1996.
Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the Start Printed Page 33267licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
The proposed license amendment adopts the NRC approved methodology described in Boiling Water Reactor Owner's Group (BWROG) Licensing Topical Report (LTR) (BWROG-TP-11-022-A, SIR-05-044, Revision 1-A), “Pressure Temperature Limits Report Methodology for Boiling Water Reactors.” The BSEP PTLR was developed based on the methodology and template provided in the BWROG LTR.
10 CFR 50, Appendix G, establishes requirements to protect the integrity of the reactor coolant pressure boundary (RCPB) in nuclear power plants.
Implementing this NRC approved methodology does not reduce the ability to protect the reactor coolant pressure boundary as specified in Appendix G, nor will this change increase the probability of malfunction of plant equipment, or the failure of plant structures, systems, or components. Incorporation of the new methodology for calculating pressure and temperature limit curves, and the relocation of the pressure and temperature limit curves from the TS to the PTLR provides an equivalent level of assurance that the reactor coolant pressure boundary is capable of performing its intended safety functions.
Creation of the possibility of a new or different kind of accident requires creating one or more new accident precursors. New accident precursors may be created by modifications of plant configuration, including changes in allowable modes of operation.
The change in methodology for calculating pressure and temperature limits and the relocation of those limits to the PTLR do not alter or involve any design basis accident initiators. Reactor coolant pressure boundary integrity will continue to be maintained in accordance with 10 CFR part 50, Appendix G, and the assumed accident performance of plant structures, systems and components will not be affected. The proposed changes do not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed), and the installed equipment is not being operated in a new or different manner.
The proposed changes do not affect the function of the reactor coolant pressure boundary or its response during plant transients. Calculating the Brunswick pressure temperature limits using the NRC approved structural integrity methodology ensures adequate margins of safety relating to reactor coolant pressure boundary integrity are maintained. The proposed changes do not alter the manner in which the Limiting Conditions for Operation pressure and temperature limits for the reactor coolant pressure boundary are determined. There are no changes to the setpoints at which protective actions are initiated, and the operability requirements for equipment assumed to operate for accident mitigation are not affected.
Therefore, the proposed amendment does not result in a significant reduction in the margin of safety.
Date of amendment request: January 31, 2018. A publicly-available version is in ADAMS under Accession No. ML18037A782.
Description of amendment request: The amendment would revise FitzPatrick's emergency plan by changing the emergency action level (EAL) schemes. The proposed changes are based on the Nuclear Energy Institute's (NEI's) guidance in NEI 99-01, Revision 6, “Development of Emergency Action Levels for Non-Passive Reactors,” which was endorsed by the NRC in a letter dated March 28, 2013 (ADAMS Accession No. ML12346A463).
The proposed changes to FitzPatrick's EAL schemes to adopt the NRC-endorsed guidance in NEI 99-01, Revision 6 do not reduce the capability to meet the emergency planning requirements established in 10 CFR 50.47 and 10 CFR part 50, Appendix E. The proposed changes do not reduce the functionality, performance, or capability of FitzPatrick's ERO [emergency response organization] to respond in mitigating the consequences of any design basis accident.
The probability of a reactor accident requiring implementation of Emergency Plan EALs has no relevance in determining whether the proposed changes to the EALs reduce the effectiveness of the Emergency Plans. As discussed in Section D, “Planning Basis,” of NUREG-0654, Revision 1, “Criteria for Preparation and Evaluation of Radiological Emergency Response Plants and Preparedness in Support of Nuclear Power Plants:”
“. . . The overall objective of emergency response plans is to provide dose savings (and in some cases immediate life saving) for a spectrum of accidents that could produce offsite doses in excess of Protective Action Guides (PAGs). No single specific accident sequence should be isolated as the one for which to plan because each accident could have different consequences, both in nature and degree. Further, the range of possible selection for a planning basis is very large, starting with a zero point of requiring no planning at all because significant offsite radiological accident consequences are unlikely to occur, to planning for the worst possible accident, regardless of its extremely low likelihood. . . .”
2. Does the proposed amendment create the possibility of a new or different kind of Start Printed Page 33268accident from any accident previously evaluated?
The proposed changes to FitzPatrick's EAL schemes to adopt the NRC-endorsed guidance in NEI 99-01, Revision 6 do not involve any physical changes to plant systems or equipment. The proposed changes do not involve the addition of any new plant equipment. The proposed changes will not alter the design configuration, or method of operation of plant equipment beyond its normal functional capabilities. All FitzPatrick ERO functions will continue to be performed as required. The proposed changes do not create any new credible failure mechanisms, malfunctions, or accident initiators.
The proposed changes to FitzPatrick's EAL schemes to adopt the NRC-endorsed guidance in NEI 99-01, Revision 6 do not alter or exceed a design basis or safety limit. There is no change being made to safety analysis assumptions, safety limits, or limiting safety system settings that would adversely affect plant safety as a result of the proposed changes. There are no changes to setpoints or environmental conditions of any SSC or the manner in which any SSC is operated. Margins of safety are unaffected by the proposed changes to adopt the NEI 99-01, Revision 6 EAL scheme guidance. The applicable requirements of 10 CFR 50.47 and 10 CFR part 50, Appendix E will continue to be met.
Date of amendment request: March 19, 2018. A publicly-available version is in ADAMS under Accession No. ML18078A578.
Description of amendment request: The amendment would revise the TMI Site Emergency Plan (SEP) on-shift and emergency response organization (ERO) staffing to support the planned permanent cessation of operations and permanent defueling of TMI, Unit 1. Specifically, the proposed changes would eliminate the on-shift positions not needed for the safe storage of spent fuel in the spent fuel pool during the initial decommissioning period and eliminate the ERO positions not necessary to effectively respond to credible accidents for a permanently shutdown and defueled power reactor facility. The proposed changes will also relocate full augmentation position requirements from the SEP to the Emergency Preparedness Implementing Procedures.
The proposed changes to the TMI Emergency Plan do not impact the function of plant Structures, Systems, or Components (SSCs). The proposed changes do not involve the modification of any plant equipment or affect plant operation. The proposed changes do not affect accident initiators or precursors, nor do the proposed changes alter design assumptions. The proposed changes do not prevent the ability of the on-shift staff and ERO to perform their intended functions to mitigate the consequences of any accident or event that will be credible in the permanently defueled condition. The proposed changes only remove positions that will no longer be needed or credited in the Emergency Plan in the permanently defueled condition.
Date of amendment request: May 10, 2018. Publicly-available version is in ADAMS under Package Accession No. ML18149A290.
Description of amendment request: The amendments would revise the emergency response organization (ERO) positions identified in the emergency plan for each site.
Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards Start Printed Page 33269consideration for each site, which is presented below:
The proposed changes to the [site] Emergency Plan do not increase the probability or consequences of an accident. The proposed changes do not impact the function of plant Structures, Systems, or Components (SSCs). The proposed changes do not affect accident initiators or accident precursors, nor do the changes alter design assumptions. The proposed changes do not alter or prevent the ability of the onsite ERO to perform their intended functions to mitigate the consequences of an accident or event. The proposed changes remove ERO positions no longer credited or considered necessary in support of Emergency Plan implementation.
Therefore, the proposed changes to the [site] Emergency Plan do not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes have no impact on the design, function, or operation of any plant SSCs. The proposed changes do not affect plant equipment or accident analyses. The proposed changes do not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed), a change in the method of plant operation, or new operator actions. The proposed changes do not introduce failure modes that could result in a new accident, and the proposed changes do not alter assumptions made in the safety analysis. The proposed changes remove ERO positions no longer credited or considered necessary in support of Emergency Plan implementation.
Therefore, the proposed changes to the [site] Emergency Plan do not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed changes do not adversely affect existing plant safety margins or the reliability of the equipment assumed to operate in the safety analyses. There are no changes being made to safety analysis assumptions, safety limits, or limiting safety system settings that would adversely affect plant safety as a result of the proposed changes. Margins of safety are unaffected by the proposed changes to the ERO staffing. The proposed changes are associated with the [site] Emergency Plan staffing and do not impact operation of the plant or its response to transients or accidents. The proposed changes do not affect the Technical Specifications. The proposed changes do not involve a change in the method of plant operation, and no accident analyses will be affected by the proposed changes. Safety analysis acceptance criteria are not affected by these proposed changes. The proposed changes to the Emergency Plan will continue to provide the necessary onsite ERO response staff.
Therefore, the proposed changes to the [site] Emergency Plan do not involve a significant reduction in a margin of safety.
Date of amendment request: May 4, 2018. A publicly-available version is in ADAMS under Accession No. ML18129A219.
Description of amendment request: The proposed change would modify technical specification (TS) requirements regarding Limiting Condition for Operation (LCO) and Surveillance Requirement (SR) usage, in accordance with NRC-approved Technical Specifications Task Force (TSTF) Traveler TSTF-529, Revision 4, “Clarify Use and Application Rules.”
The proposed changes to Section 1.3 and LCO 3.0.4 have no effect on the requirement for systems to be Operable and have no effect on the application of TS actions. The proposed change to SR 3.0.3 states that the allowance may only be used when there is a reasonable expectation the surveillance will be met when performed. Since the proposed change does not significantly affect system Operability, the proposed change will have no effect on the initiating events for accidents previously evaluated and will have no significant effect on the ability of the systems to mitigate accidents previously evaluated.
Date of amendment request: May 18, 2018. A publicly-available version is in ADAMS under Accession No. ML18138A396.
Description of amendment request: The amendment request proposes to change Technical Specifications Limiting Condition for Operation 3.3.8, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, related to Safeguard Actuation Functions. Various ESFAS Functions require applicability and corresponding actions changes to more accurately reflect their operation and related safety analysis assumptions. This submittal requests approval of the license amendment necessary to implement these changes.Start Printed Page 33270
The proposed changes do not involve changes to current plant design or safety analysis assumptions. These changes provide Technical Specifications consistency with the approved plant design and safety analysis assumptions. The changes do not affect the operation of any systems or equipment that initiate an analyzed accident or alter any structures, systems, and components (SSCs) accident initiator or initiating sequence of events. The proposed changes do not result in any increase in the probability of an analyzed accident occurring. Therefore, the requested amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes do not involve changes to current plant design or safety analysis assumptions. These changes provide Technical Specifications consistency with the approved plant design and safety analysis assumptions. The proposed changes do not affect plant protection instrumentation systems, and do not affect the design function, support, design, or operation of mechanical and fluid systems. The proposed changes do not result in a new failure mechanism or introduce any new accident precursors. No design function described in the Updated Final Safety Analysis Report (UFSAR) is affected by the proposed changes. Therefore, the requested amendment does not create the possibility of a new or different kind accident from any accident previously evaluated.
The proposed changes do not involve changes to current plant design or safety analysis assumptions. These changes provide Technical Specifications consistency with the approved plant design and safety analysis assumptions. No safety analysis or design basis acceptance limit/criterion is involved. Therefore, the proposed amendment does not involve a significant reduction in a margin of safety.
Date of amendment request: May 3, 2018. A publicly-available version is in ADAMS under Accession No. ML18124A053.
Description of amendment request: The amendments would revise the BFN Units 1, 2, and 3 renewed facility operating licenses (RFOLs) to provide a correction to previously submitted information in relation to their approved fire protection program under 10 CFR 50.48(c), “National Fire Protection Association Standard NFPA 805.” Specifically, TVA requested to modify the BFN licenses to reflect changes to Item 3.3.4 in Table B-1, “Transition of Fundamental Fire Protection Program & Design Elements,” of Attachment A in its NFPA 805 license amendment request dated March 27, 2013 (ADAMS Accession No. ML13092A393).
The proposed amendment adds the reference to this letter to the BFN RFOL License Condition paragraphs 2.C.(13), 2.C.(14), and 2.C.(7) for BFN Units 1, 2, and 3, respectively. The change encompassed by the proposed amendment is to correct the entry in Attachment A Table B-1 of the BFN Transition Report.
The proposed change does not adversely affect accident initiators or precursors nor alter the design assumptions, conditions, and configuration of the facility or the manner in which the plant is operated and maintained. The proposed change does not affect the ability of structures, systems and components (SSCs) to perform their intended safety function to mitigate the consequences of an initiating event within the assumed acceptance limits.
Therefore, these proposed changes do not involve a significant increase in the probability of consequences of an accident previously identified.
There is no risk impact to Core Damage Frequency (CDF) or Large Early Release Frequency (LERF) because this is an administrative change. Plant secondary combustibles, including insulating materials, are considered in the fire modeling input to the Fire PRA [Probabilistic Risk Assessment].
The proposed amendment adds the reference to this letter to the BFN RFOL License Condition paragraphs 2.C.(13), 2.C.(14), and 2.C.(7) for BFN Units 1, 2, and 3, respectively. The change encompassed by the proposed amendment are to correct the entry in Attachment A Table B-1 of the BFN Transition Report.
This proposed change corrects erroneous information to previously approved information in the BFN Transition Report. This proposed change will have an insignificant impact on the accident analysis as it is a clarifying or administrative change. Plant secondary combustibles, including insulating materials, are considered in the fire modeling input to the Fire PRA.
The proposed change will not result in any new or different kinds of accident from that previously evaluated because it does not change any precursors or equipment that is previously credited for accident mitigation.
NRC Acting Branch Chief: Booma Venkataraman.Start Printed Page 33271
Date of amendment request: June 5, 2017, as supplemented by letters dated October 30, 2017, November 27, 2017, and January 28, 2018.
Brief description of amendment: The amendment revised the Technical Specifications (TSs) to restrict the steady-state voltage and frequency limits for emergency diesel generator (EDG) operation to ensure that accident mitigation equipment can perform as designed. In addition, the amendment revised a TS to increase the voltage limit for the EDG full load rejection test to provide additional operating margin to test acceptance criteria.
Date of issuance: June 20, 2018.
Amendment No.: 165. A publicly-available version is in ADAMS under Accession No. ML18130A270; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-63: The amendment revised the Renewed Facility Operating License and TSs.
Date of initial notice in Federal Register: September 26, 2017 (82 FR 44851). The supplemental letters dated October 30, 2017, November 27, 2017, and January 28, 2018, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated June 20, 2018.
Date of amendment request: July 13, 2017.
Date of issuance: June 27, 2018.
Effective date: As of the date the licensee notifies the NRC in writing that all spent nuclear fuel assemblies have been transferred out of the spent fuel pool and have been placed in dry storage within the independent spent fuel storage installation, and shall be implemented within 60 days of the effective date.
Amendment No.: 268. A publicly-available version is in ADAMS under Accession No. ML18145A208; documents related to this amendment are referenced in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-28: This amendment revised the License.
Date of initial notice in Federal Register: September 26, 2017 (82 FR 44852).
The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated June 27, 2018.
Date of amendment request: July 17, 2017.
Brief description of amendment: The amendment revised the Technical Specifications (TSs) for ANO-1 and established a new Completion Time in ANO-1 TS 3.7.5, “Emergency Feedwater (EFW) System,” where one steam supply to the turbine-driven EFW pump is inoperable concurrent with an inoperable motor-driven EFW train. The amendment is consistent with NRC-approved Technical Specifications Task Force (TSTF) Traveler TSTF-412, Revision 3, “Provide Actions for One Steam Supply to Turbine Driven AFW [Auxiliary Feedwater]/EFW Pump Inoperable,” with certain plant-specific deviations.
Date of issuance: June 19, 2018.
Amendment No.: 260. A publicly-available version is in ADAMS under Accession No. ML18115A282; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-51: Amendment revised the Renewed Facility Operating License and Technical Specifications.
Date of initial notice in Federal Register: October 10, 2017 (82 FR 47036).
The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated June 19, 2018.
Brief description of amendment: The amendment revised the Technical Specifications (TSs) for ANO-2 and established Actions and Allowable Outage Times in ANO-2 TS 3.7.1.2, “Emergency Feedwater System,” for several combinations of inoperable Emergency Feedwater (EFW) trains consistent with NUREG-1432, “Standard Technical Specifications—Combustion Engineering Plants,” Revision 4. The amendment includes Start Printed Page 33272changes incorporated by Technical Specifications Task Force (TSTF)-340, “Allow 7 Day Completion Time for a Turbine-Driven AFW [Auxiliary Feedwater] Pump Inoperable,” Revision 3 and TSTF-412, “Provide Actions for One Steam Supply to Turbine Driven AFW/EFW Pump Inoperable,” Revision 3.
Amendment No.: 310. A publicly-available version is in ADAMS under Accession No. ML18134A253; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment.
Date of amendment request: May 31, 2017.
Brief description of amendments: The amendments revised the emergency plans for each facility by changing the emergency action level schemes. The changes are based on the Nuclear Energy Institute's (NEI's) guidance in NEI 99-01, Revision 6, “Development of Emergency Action Levels for Non-Passive Reactors,” which was endorsed by the NRC by letter dated March 28, 2013 (ADAMS Package Accession No. ML13091A209).
Date of issuance: June 26, 2018.
Effective date: As of the date of issuance and shall be implemented on or before June 28, 2019.
Amendment Nos.: Calvert Cliffs—324/302; Nine Mile Point—230/171; and, Ginna—128. A publicly-available version is in ADAMS under Accession No. ML18137A614; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments.
Facility Operating License Nos. DPR-53, DPR-69, DPR-63, NPF-69, and DPR-18: Amendments revised the emergency plans.
Date of initial notice in Federal Register: August 1, 2017 (82 FR 35838).
The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated June 26, 2018.
Date of amendment request: May 3, 2017, as supplemented by letter dated February 14, 2018.
Brief description of amendments: The amendments revised the DNPS Technical Specification (TS) 5.5.12, “Primary Containment Leakage Rate Testing Program,” to allow for the permanent extension of the Type A integrated leak rate testing and the Type C leak rate testing frequencies.
Date of issuance: June 29, 2018.
Amendment Nos.: 257 (Unit 2) and 250 (Unit 3). A publicly-available version is in ADAMS under Accession No. ML18137A271; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-19 and DPR-25: Amendments revised the Renewed Facility Operating Licenses and TS.
Date of initial notice in Federal Register: August 1, 2017 (82 FR 35838). The supplemental letter dated February 14, 2018, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register.
The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated June 29, 2018.
Date of amendment request: June 30, 2017, as supplemented by letters dated October 25, 2017, and June 5, 2018.
Brief description of amendment: The amendment revised the license to delete the modification to install overcurrent protection on its emergency diesel generators which was required as part of Ginna's implementation of its risk-informed, performance-based fire protection program in accordance with 10 CFR 50.48(c).
Date of issuance: June 25, 2018.
Amendment No.: 127. A publicly-available version is in ADAMS under Accession No. ML18114A025; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-18: Amendment revised the Renewed Facility Operating License.
Date of initial notice in Federal Register: October 3, 2017 (82 FR 46097). The supplemental letters dated October 25, 2017, and June 5, 2018, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated June 25, 2018.
Date of amendment request: June 30, 2017, as supplemented by letters dated October 25, 2017, and May 29, 2018.
Brief description of amendments: The amendments revised Technical Specification (TS) 3.1.4, “Rod Group Alignment Limits,” TS 3.1.5, “Shutdown Bank Insertion Limits,” TS 3.1.6, “Control Bank Insertion Limits,” and TS 3.1.7, “Rod Position Indication.”
Amendment Nos: 196 (Braidwood, Unit 1) and 196 (Braidwood, Unit 2); 202 (Bryon, Unit 1) and 202 (Bryon, Unit 2). A publicly-available version is in ADAMS under Accession No. ML18065A529; documents related to these amendments are listed in the Start Printed Page 33273related Safety Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. NPF-72, NPF-77, NPF-37, and NPF-66: The amendments revised the Renewed Facility Operating Licenses and TSs.
Date of initial notice in Federal Register: August 29, 2017 (82 FR 41069). The supplemental letters dated October 25, 2017, and May 29, 2018, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register.
The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated June 27, 2018.
Date of amendment request: September 11, 2017.
Brief description of amendment: The amendment revised the requirements in Technical Specification (TS) 3.3.6.1, “Primary Containment and Drywell Isolation Instrumentation,” by adding an ACTIONS note to Limiting Condition of Operation 3.3.6.1 to allow intermittent opening, under administrative control, of containment and drywell penetration flow paths that are isolated.
Amendment No.: 181. A publicly-available version is in ADAMS under Accession No. ML18157A084; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment.
Facility Operating License No. NPF-58: Amendment revised the Facility Operating License and TS.
Date of initial notice in Federal Register: November 7, 2017 (82 FR 51652).
Date of amendment request: October 6, 2017, as supplemented by letter dated April 19, 2018.
Brief description of amendment: This amendment increased the Integrated Leak Rate Test Peak Calculated Containment Internal Pressure, Pa, listed in Technical Specification (TS) 6.8.4.g, “Containment Leakage Rate Testing Program,” from 45.1 pounds per square inch gauge (psig) to 46.0 psig. It also removed the reference to Regulatory Guide 1.163, “Performance-Based Containment Leak Test Program,” and American National Standards Institute/American Nuclear Society (ANSI/ANS)-56.8-2002, “Containment System Leakage Testing Requirements,” and replaced the reference of Nuclear Energy Institute (NEI) 94-01, Revision 3-A, “Industry Guideline for Implementing Performance-Based Option of 10 CFR part 50, Appendix J,” with NEI 94-01, Revision 2-A.
Date of issuance: June 28, 2018.
Amendment No.: 210. A publicly-available version is in ADAMS under Accession No. ML18141A668, documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-12: Amendment revised the Renewed Facility Operating License and the TS.
Date of initial notice in Federal Register: November 21, 2017 (82 FR 55409). The supplemental letter dated April 19, 2018, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated June 28, 2018.
Date of amendment request: December 21, 2017.
Brief description of amendments: The amendments modified Technical Specification (TS) 3.7.5, “Auxiliary Feedwater (AFW) System,” to establish a new Completion Time for the Condition where one steam supply to the turbine driven AFW pump is inoperable concurrent with an inoperable motor driven AFW train. In addition, the amendments added specific Conditions and Action requirements: (1) For when two motor driven AFW trains are inoperable at the same time and; (2) for when the turbine driven AFW train is inoperable either (a) due solely to one inoperable steam supply, or (b) due to reasons other than one inoperable steam supply. The proposed changes are consistent with NRC-approved Technical Specification Task Force (TSTF) Traveler, TSTF-412, Revision 3, “Provide Actions for One Steam Supply to Turbine Driven AFW/EFW [Emergency Feedwater] Pump Inoperable” dated January 10, 2007.
Amendment Nos.: 219 (Unit 1) and 216 (Unit 2). A publicly-available version is in ADAMS under Accession No. ML18151A174. Documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. NPF-2 and NPF-8: The amendments revised the Renewed Facility Operating Licenses and TS.
Date of initial notice in Federal Register: February 13, 2018 (83 FR 6234).
Date of amendment request: December 14, 2017.
Brief description of amendments: The amendments revised Technical Specification (TS) 3.6.4.1, “Secondary Containment,” Surveillance Requirement (SR) 3.6.4.1.1. The SR was revised to address conditions during which the secondary containment pressure may not meet the SR pressure requirements. The changes are based on Technical Specification Task Force (TSTF) Traveler TSTF-551, Revision 3, “Revise Secondary Containment Surveillance Requirements.”
Date of issuance: June 26, 2018.Start Printed Page 33274
Amendment Nos.: 270 (Unit 1) and 252 (Unit 2). A publicly-available version is in ADAMS under Accession No. ML18150A281. Documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. NPF-14 and NPF-22: The amendments revised the Renewed Facility Operating Licenses and TS.
Date of initial notice in Federal Register: February 27, 2018 (83 FR 8520).
Date of amendment request: November 23, 2016, as supplemented by letters dated September 29, November 16, and December 27, 2017, and May 11, 2018.
Brief description of amendments: The amendments revised the Technical Specification (TS) requirements on control and shutdown rods, and rod and bank position indication in the Units 1 and 2, TS 3.1.5, “Rod Group Alignment Limits,” TS 3.1.6, “Shutdown Bank Insertion Limits,” TS 3.1.7, “Control Bank Insertion Limits,” and TS 3.1.8, “Rod Position Indication.”
Amendment Nos.: 120 (Unit 1) and 20 (Unit 2). A publicly-available version is in ADAMS under Accession No. ML18079A029; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments.
Date of initial notice in Federal Register: March 14, 2017 (82 FR 13672). The supplemental letters dated September 29, November 16, and December 27, 2017, expanded the scope of the amendment request as originally noticed in the Federal Register. A second notice was published in the Federal Register on February 21, 2018 (83 FR 7500), which superseded the original notice in its entirety. The supplemental letter dated May 11, 2018, provided additional information that clarified the application, did not expand the scope of the application as re-noticed, and did not change the NRC staff's proposed no significant hazards consideration determination as published in the Federal Register.
During the period since publication of the last biweekly notice, the Commission has issued the following amendment. The Commission has determined for this amendment that the application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR chapter I, which are set forth in the license amendment.
The Commission has applied the standards of 10 CFR 50.92 and has made a final determination that the amendment involves no significant hazards consideration. The basis for this determination is contained in the documents related to this action. Accordingly, the amendment has been issued and made effective as indicated.
Unless otherwise indicated, the Commission has determined that this amendment satisfies the criteria for categorical exclusion in accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared for this amendment. If the Commission has prepared an environmental assessment under the special circumstances provision in 10 CFR 51.12(b) and has made a determination based on that assessment, it is so indicated.
The Commission is also offering an opportunity for a hearing with respect to the issuance of the amendment. Within 60 days after the date of publication of this notice, any persons (petitioner) whose interest may be affected by this Start Printed Page 33275action may file a request for a hearing and petition for leave to intervene (petition) with respect to the action. Petitions shall be filed in accordance with the Commission's “Agency Rules of Practice and Procedure” in 10 CFR part 2. Interested persons should consult a current copy of 10 CFR 2.309. The NRC's regulations are accessible electronically from the NRC Library on the NRC's website at http://www.nrc.gov/​reading-rm/​doc-collections/​cfr/​. Alternatively, a copy of the regulations is available at the NRC's Public Document Room, located at One White Flint North, Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. If a petition is filed, the Commission or a presiding officer will rule on the petition and, if appropriate, a notice of a hearing will be issued.
To comply with the procedural requirements of E-Filing, at least 10 days prior to the filing deadline, the participant should contact the Office of the Secretary by email at hearing.docket@nrc.gov, or by telephone at 301-415-1677, to (1) request a digital identification (ID) certificate, which allows the participant (or its counsel or representative) to digitally sign Start Printed Page 33276submissions and access the E-Filing system for any proceeding in which it is participating; and (2) advise the Secretary that the participant will be submitting a petition or other adjudicatory document (even in instances in which the participant, or its counsel or representative, already holds an NRC-issued digital ID certificate). Based upon this information, the Secretary will establish an electronic docket for the hearing in this proceeding if the Secretary has not already established an electronic docket.
Date of amendment request: June 21, 2018.
Description of amendments: The amendments revised the Peach Bottom Technical Specifications (TSs) for a one-time suspension of the emergency diesel generator (EDG) No. 4 (E-4) surveillance requirements. Specifically, the amendments revised TS Surveillance Requirements 3.8.1.2, 3.8.1.3, 3.8.1.6, and 3.8.3.4 to suspend performing required monthly surveillance testing on the E-4 EDG until the E-3 EDG is returned to operable status, not to exceed 2205 hours Eastern Time on June 27, 2018.
Date of issuance: June 23, 2018.
Effective date: June 23, 2018.
Amendment Nos.: 318 (Unit 1) and 321 (Unit 2). A publicly-available version is in ADAMS under Accession No. ML18173A042. Documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments.
The Commission's related evaluation of the amendments, finding of emergency circumstances, State consultation, and final no significant hazards consideration determination are contained in a Safety Evaluation dated June 23, 2018.
Attorney for licensee: J. Bradley Fewell, Vice President and Deputy General Counsel, Exelon Generation Company, LLC, 200 Exelon Way, Kennett Square, PA 19348.
[FR Doc. 2018-14779 Filed 7-16-18; 8:45 am]