RS-20-114, License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition

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License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition
ML20269A401
Person / Time
Site: Byron  Constellation icon.png
Issue date: 09/24/2020
From: Simpson P
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-20-114
Download: ML20269A401 (31)
v • d • e


Text

Exelon Generation RS-20-114 4300 Winfield Road Warrenville, IL 60555 630 65 7 2000 Office 10 CFR 50.90 September 24, 2020 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455

Subject:

License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, "Definitions," and 5.0, "Administrative Controls," for Permanently Defueled Condition

References:

1. Letter from J. Bradley Fewell (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Certification of Permanent Cessation of Power Operations for Byron Station, Units 1 and 2," dated September 2, 2020 (NRC Accession No. ML20246G613)
2. Letter from Patrick R. Simpson (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Request for Approval of Certified Fuel Handler Training and Retraining Program," for Byron Station, Units 1 and 2, and Dresden Nuclear Power Station, Units 1, 2 and 3, dated September 24, 2020 In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (Exelon) requests amendments to the Technical Specifications (TS) of Renewed Facility Operating License Nos. NPF-37 and NPF-66 for Byron Station, Units 1 and 2 (Byron).

On August 27, 2020, Exelon announced that it plans to close Byron due to severe economic challenges. By letter dated September 2, 2020 (Reference 1), Exelon provided formal notification to the U.S. Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 50.4(b)(8) and 10 CFR 50.82(a)(1)(i) that it would permanently cease operations at Byron on or before September 30, 2021.

Once the certifications for permanent cessation of operations and permanent removal of fuel from the reactor vessels are submitted to the NRC in accordance with 10 CFR 50.82(a)(1)(i) and (ii), then pursuant to 10 CFR 50.82(a)(2), the 10 CFR 50 licenses will no longer authorize operation of the reactors or emplacement or retention of fuel in the reactor vessels.

September 24, 2020 U.S. Nuclear Regulatory Commission Page 2 The basis for this proposed License Amendment Request (LAR) is that certain TS administrative controls may be revised or removed to reflect the permanently defueled condition. Specifically, this LAR proposes changes to the organization, staffing, and training requirements contained in Section 5.0, "Administrative Controls," of the Byron TS and defines two new positions for Certified Fuel Handler and Non-Certified Operator in Section 1.1, "Definitions." The proposed amendments also support implementation of the Certified Fuel Handler Training and Retraining Program that was submitted to the NRC on September 24, 2020 (Reference 2). to this letter provides a detailed description and evaluation of the proposed changes to the TS. Attachment 2 provides the existing TS pages for Byron, marked up to show the proposed changes.

The proposed changes have been reviewed by the Byron Plant Operations Review Committee in accordance with the requirements of the Exelon Quality Assurance Program.

Exelon requests approval of the proposed amendments by August 16, 2021, to support the current schedule for the Byron transition to a permanently defueled facility. Once approved, the amendments shall be implemented within 60 days from the effective date of the amendments.

Exelon requests that the approved amendments become effective following submittal of the certifications required by 10 CFR 50.82(a)(1), informing the NRC that the Byron Units have been permanently shutdown and defueled.

In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b),

Exelon is notifying the State of Illinois of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Officials.

There are no regulatory commitments contained within this submittal.

Should you have any questions concerning this submittal, please contact Ms. Lisa Simpson at (630) 657-2815.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 24th day of September 2020.

Patrick R. Simpson Sr. Manager - Licensing Exelon Generation Company, LLC Attachments: 1.

Evaluation of Proposed Changes

2. Markup of Technical Specifications Pages

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Definitions 1.1 BYRON UNITS 1 & 2 1.1 1 Amendment 213 1.0 USE AND APPLICATION 1.1 Definitions

NOTE-------------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

ACTUATION LOGIC TEST An ACTUATION LOGIC TEST shall be the application of various simulated or actual input combinations in conjunction with each possible interlock logic state and the verification of the required logic output. The ACTUATION LOGIC TEST, as a minimum, shall include a continuity check of output devices.

AXIAL FLUX DIFFERENCE AFD shall be the difference in normalized flux (AFD) signals between the top and bottom halves of a two section excore neutron detector.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel so that it responds within the required range and accuracy to known inputs. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, interlock, display, and trip functions.

Calibration of instrument channels with Resistance Temperature Detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping calibrations or total channel steps so that the entire channel is calibrated, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

CERTIFIED FUEL HANDLER INSERT 1

Definitions 1.1 BYRON UNITS 1 & 2 1.1 5 Amendment 106 1.1 Definitions MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

OPERABLE-OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.

These tests are:

a. Described in Chapter 14, Initial Test Program, of the UFSAR;
b. Authorized under the provisions of 10 CFR 50.59; or
c. Otherwise approved by the Nuclear Regulatory Commission.

INSERT 2 NON-CERTIFIED OPERATOR

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Responsibility 5.1 BYRON UNITS 1 & 2 5.1 1 Amendment 106 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The station manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

5.1.2 A Senior Reactor Operator (SRO) shall be responsible for the control room command function while either unit is in MODE 1, 2, 3, or 4. For each unit, an SRO may be designated as responsible for the control room command function. While both units are in MODE 5 or 6, or defueled, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

shift shift manager plant

Organization 5.2 BYRON UNITS 1 & 2 5.2 1 Amendment 152 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for facility operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.

a.

Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements, including the generic titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the Quality Assurance Program;

b.

The station manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant;

c.

The Chief Nuclear Officer shall be responsible for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and

d.

The individuals who train the operating staff, or perform health physics or quality assurance functions, may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.

the safe storage and handling of irradiated fuel.

storage irradiated fuel safe storage and handling of irradiated fuel CERTIFIED FUEL HANDLERS ability to perform their assigned functions.

facility facility staff A responsible officer have corporate responsibility facility radiation protection the safe storage and handling of irradiated fuel Exelon Decommissioning plant handling

Organization 5.2 BYRON UNITS 1 & 2 5.2 2 Amendment 162 5.2 Organization 5.2.2 Facility Staff The facility staff organization shall include the following:

a.

A total of three non-licensed operators for the two units is required in all conditions. At least one of the required non-licensed operators shall be assigned to each unit.

b.

Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

c.

A radiation protection technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d.

Deleted.

e.

The operations manager or the supervisor in charge of the operations shift crews shall hold an SRO license.

f.

The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Manager in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the facility. In addition, the STA shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

Specification Each duty shift shall be composed of at least one shift manager and two NON-CERTIFIED OPERATORS. The NON-CERTIFIED OPERATOR position may be filled by a CERTIFIED FUEL HANDLER.

Oversight of irradiated fuel handling operations shall be provided by a CERTIFIED FUEL HANDLER.

The shift manager shall be a CERTIFIED FUEL HANDLER.

At all times when irradiated fuel is stored in the spent fuel pool, at least one person qualified to stand watch in the control room (NON-CERTIFIED OPERATOR or CERTIFIED FUEL HANDLER) shall be present in the control room.

during the movement of irradiated fuel and during movement of loads over irradiated fuel and the following conditions are met:

1) No movement of irradiated fuel is in progress;
2) No movement of loads over irradiated fuel is in progress.

This provision does not permit any shift crew position to be unstaffed upon shift change due to the absence or tardiness of an oncoming shift crew member

Facility Staff Qualifications 5.3 BYRON UNITS 1 & 2 5.3 1 Amendment 2030 5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications referenced for comparable positions as specified in the Exelon Quality Assurance Topical Report.

5.3.2 An NRC-approved training and retraining program for the CERTIFIED FUEL HANDLERS shall be maintained.

Decommissioning Quality Assurance Program

Procedures 5.4 BYRON UNITS 1 & 2 5.4 1 Amendment 106 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities:

a.

The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978; b.

The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1, as stated in Generic Letter 82-33, Section 7.1; c.

Fire Protection Program implementation; and d.

All programs specified in Specification 5.5.

Deleted applicable to the safe storage and handling of irradiated fuel

Retrieved from "https://kanterella.com/w/index.php?title=RS-20-114,_License_Amendment_Request_-_Proposed_Changes_to_Technical_Specifications_Sections_1.1,_Definitions,_and_5.0,_Administrative_Controls,_for_Permanently_Defueled_Condition&oldid=3849369"