View source for RS-20-116, License Amendment Request - Proposed Changes to Unit 1 Technical Specifications Section 6.1, Responsibility, and Units 2 and 3 Technical Specifications 1.1, Definitions, and 5.0, Administrative

{{Adams
| number = ML20269A404
| issue date = 09/24/2020
| title = License Amendment Request - Proposed Changes to Unit 1 Technical Specifications Section 6.1, Responsibility, and Units 2 and 3 Technical Specifications 1.1, Definitions, and 5.0, Administrative
| author name = Simpson P
| author affiliation = Exelon Generation Co, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NMSS, NRC/NRR
| docket = 05000010, 05000237, 05000249
| license number = DPR-002, DPR-019, DPR-025
| contact person = 
| case reference number = RS-20-116
| document type = Letter type:RS, License-Application for Facility Operating License (Amend/Renewal) DKT 50
| page count = 32
| project = 
| stage = Request
}}

=Text=
{{#Wiki_filter:4300 Winfield Road Warrenville, IL 60555 Exelon Generation                                         630 65 7 2000 Office RS-20-116 10 CFR 50.90 September 24, 2020 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 1, 2, and 3 Amended Facility Operating License No. DPR-2 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-010. 50-237. and 50-249

==Subject:==
License Amendment Request- Proposed Changes to Unit 1 Technical Specifications Section 6.1, "Responsibility," and Units 2 and 3 Technical Specifications 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 Dresden Nuclear Power Station, Units 2 and 3,"
dated September 2, 2020 (NRC Accession No. ML20246G627)
: 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 Amended Facility Operating License No. DPR-2 and Renewed Facility Operating License Nos. DPR-19 and DPR-25 for Dresden Nuclear Power Station, Units 1, 2, and 3, (Dresden) respectively.
On August 27, 2020, Exelon announced that it plans to close Dresden, Units 2 and 3 due to severe economic challenges. By {{letter dated|date=September 2, 2020|text=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 Dresden on or before November 30, 2021.
Once the certifications for permanent cessation of operations and 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 Dresden, Units 2 and 3 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 6.1, "Responsibility," of the Dresden, Unit 1 TS and Section 5.0, "Administrative Controls," of the Dresden, Units 2 and 3 TS and defines two new positions for Certified Fuel Handler and Non-Certified Operator in Section 1.1, "Definitions," of the Dresden, Units 2 and 3 TS. The proposed amendments also support implementation of the Certified Fuel Handler Training and Retraining Program that was 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 Dresden, marked up to show the proposed changes.
The proposed changes have been reviewed by the Dresden Plant Operations Review Committee in accordance with the requirements of the Exelon Quality Assurance Program.
Exelon requests review and approval of these proposed amendments by September 24, 2021, to support the current schedule for the Dresden 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 the submittal of the certifications required by 10 CFR 50.82(a)(1), informing the NRC that Dresden, Units 2 and 3 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 amendments 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 Mr. Mitchel Mathews at (630) 657-2819.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 241h day of September 2020.
Respectfully, Poi;lR~
Patrick R. Simpson Sr. Manager - Licensing Exelon Generation Company, LLC

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Responsibility 6.1 6.0 ADMINISTRATIVE CONTROLS RESPONSIBILITY             ~
6.1.A The OresEfen etation Manager shall have the responsibility for a8ministrati9n 9f all Unit 1 functions. This responsibility includes site support activities such as the overall                 OFFSITE DOSE CALCULATION MANUAL, Site Fire Protection Program, the facility                Radioactive Effluent Controls Program and Emergency Preparedness.
operation .
6.1.B (DELETED)
* IMan,er I 6.1 .C The Unit 2/3 Shift Manger shall be responsible for directing and commanding the safe overall operation of the Dresden Station Site under all conditions. This shall include immediate notification of the NRC if required for a REPORT ABLE EVENT.
DRESDEN - UNIT 1                                                        Amendment No. 59, 4.:1

Definitions 1.1 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.
AVERAGE PLANAR LINEAR            The APLHGR shall be applicable to a specific HEAT GENERATION RATE             planar height and is equal to the sum of the (APLHGR)                         LHGRs for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.
CHANNEL CALIBRATION              A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel
&(57,),(' )8(/                            monitors. The CHANNEL CALIBRATION shall encompass
+$1'/(5                                   all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST.
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, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.
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Dresden 2 and 3                           1.1-1              Amendment No. 266/259

Definitions 1.1 1.1   Definitions LEAKAGE                    c. Total LEAKAGE (continued)
Sum of the identified and unidentified LEAKAGE; and
: d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.
LINEAR HEAT GENERATION     The LHGR shall be the heat generation rate per RATE (LHGR)                unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
LOGIC SYSTEM FUNCTIONAL    A LOGIC SYSTEM FUNCTIONAL TEST shall be a test TEST                       of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.
MINIMUM CRITICAL POWER     The MCPR shall be the smallest critical power RATIO (MCPR)               ratio (CPR) that exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the 121&(57,),('                          appropriate correlation(s) to cause some point in the assembly to experience boiling transition, 23(5$725                               divided by the actual assembly operating power.
MODE                       A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.
OPERABLEOPERABILITY       A system, subsystem, division, component, or
$ 121&(57,),(' 23(5$725 LV D          device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety QRQOLFHQVHG RSHUDWRU ZKR FRPSOLHV function(s) and when all necessary attendant ZLWK WKH TXDOLILFDWLRQ UHTXLUHPHQWV RI instrumentation, controls, normal or emergency 6SHFLILFDWLRQ  EXW LV QRW D      electrical power, cooling and seal water,
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Dresden 2 and 3                     1.1-6              Amendment No. 266/259

Responsibility 5.1 5.0   ADMINISTRATIVE CONTROLS SODQW                                                  IDFLOLW\
5.1   Responsibility 5.1.1        The station manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.            VKLIW VKLIW PDQDJHU 5.1.2        A unit supervisor shall be responsible for the control room command function (Since the control room is common to both units, the control room command function for both units can be satisfied by a single unit supervisor). During any absence of the unit supervisor from the control room while the unit is in MODE 1, 2, or 3, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the unit supervisor from the control room while the unit is in MODE 4 or 5 or defueled, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.
Dresden 2 and 3                       5.1-1               Amendment No. 185/180

Organization 5.2 5.0    ADMINISTRATIVE CONTROLS 5.2    Organization 5.2.1           Onsite and Offsite Organizations                                           IDFLOLW\
VWDII Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.
WKH VDIH VWRUDJH                                                                              IDFLOLW\
DQG KDQGOLQJ RI               a. Lines of authority, responsibility, and communication shall LUUDGLDWHG IXHO                    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
([HORQ                        descriptions of departmental responsibilities and relationships, and job descriptions for key personnel
     'HFRPPLVVLRQLQJ               positions, or in equivalent forms of documentation. These requirements, including the generic titles of those personnel fulfilling the responsibilities of the positions SODQW delineated in these Technical Specifications, shall be documented in the Quality Assurance Manual.                 3URJUDP IDFLOLW\
: b. The station manager shall be responsible for overall safe            VWRUDJH KDQGOLQJ                  operation of the plant and shall have control over those onsite activities necessary for safe operation and UHVSRQVLEOH                  maintenance of the plant.
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: d. The individuals who train the operating staff, or perform IDFLOLW\ WR HQVXUH          radiation protection or quality assurance functions, may VDIH VWRUDJH DQG            report to the appropriate onsite manager; however, these KDQGOLQJ RI                 individuals shall have sufficient organizational freedom to LUUDGLDWHG IXHO             ensure their independence from operating pressures.
                    )DFLOLW\                                    DELOLW\ WR SHUIRUP WKHLU DVVLJQHG IXQFWLRQV 5.2.2           Unit Staff The unit staff organization shall include the following:
(continued)
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Dresden 2 and 3                          5.2-1                    Amendment No. 225/217

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5.2   Organization 5.2.2          Unit Staff      (continued)
        )DFLOLW\           a. A total of three non-licensed l         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.
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: c. A radiation protection technician shall be on site when fuel 2YHUVLJKW RI                      is in the reactor. The position may be vacant for not more LUUDGLDWHG IXHO                   than 2 hours, in order to provide for unexpected absence, provided immediate action is taken to fill the required KDQGOLQJ RSHUDWLRQV position.
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: e. The T     operations manager or shift operations supervisor shall 7KHVKLIWPDQDJHUVKDOO          hold an SRO license.
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+$1'/(5                   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 unit. In addition, the STA shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
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7KLV SURYLVLRQ GRHV QRW SHUPLW DQ\ VKLIW FUHZ SRVLWLRQ WR EH XQVWDIIHG XSRQ VKLIW FKDQJH GXH WR WKH DEVHQFH RU WDUGLQHVV RI DQ RQFRPLQJ VKLIW FUHZ PHPEHU Dresden 2 and 3                              5.2-2                   Amendment No. 231/224

                                                   )DFLOLW\   Unit Staff Qualifications 5.3
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5.0   ADMINISTRATIVE CONTROLS 5.3   Unit Staff Qualifications         IDFLOLW\
5.3.1        Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions as specified in the Exelon Quality Assurance Topical Report.
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Dresden 2 and 3                       5.3-1                Amendment No. 258/251

Procedures 5.4 5.0   ADMINISTRATIVE CONTROLS        DSSOLFDEOH WR WKH VDIH VWRUDJH DQG 5.4   Procedures                     KDQGOLQJ RI LUUDGLDWHG IXHO 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;
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: 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.
Dresden 2 and 3                        5.4-1               Amendment No. 185/180}}