L-20-298, Supplement to License Amendment Request: Proposed Change to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition

Supplement to License Amendment Request: Proposed Change to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition

ML20315A004
Person / Time
Site:	Beaver Valley
Issue date:	11/09/2020
From:	Penfield R Energy Harbor Nuclear Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
EPID L-2020-LLA-0025, L-20-298
Download: ML20315A004 (5)

Text

Energy Harbor Nuclear Corp.

Beaver Valley Power Station P. O. Box 4 Shippingport, PA 15077 Rod L. Penfield 724-682-5234 Site Vice President, Beaver Valley Nuclear November 9, 2020 L-20-298 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Beaver Valley Power Station, Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Supplement to License Amendment Request - Proposed Change to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition (EPID L-2020-LLA-0025)

By letter dated February 11, 2020 (Accession No. ML20043F441), an amendment to Appendix A, Technical Specifications (TS), of Renewed Facility Operating License Nos.

DPR-66 and NPF-73 for Beaver Valley Power Station, Unit Nos. 1 (BVPS-1) and 2 (BVPS-2) was requested. The purpose for this proposed license amendment request (LAR) is that certain TS administrative controls may be added to reflect the permanently defueled condition of one unit at the dual unit site, while maintaining the operational requirements for the other unit until such time similar certifications are docketed for the second unit. Specifically, this LAR proposes changes to the organization, staffing, and training requirements contained in Section 5.0, Administrative Controls of the BVPS-1 and BVPS-2 TS and defines two new positions for Certified Fuel Handler and Non-Certified Operator in Section 1.1, Definitions.

It was recently identified that the two proposed definitions refer to incorrect TS numbers. In Section 2.0, Detailed Description, of the LAR, the definition for Certified Fuel Handler refers to Specification 5.3A.4, and the definition of Non-Certified Operator refers to Specification 5.3A.3. The definition for Certified Fuel Handler should refer to Specification 5.3A.2, and the definition of Non-Certified Operator should refer to Specification 5.3A.1. Corrected TS page markups are attached to supplement the LAR. This correction has no impact on the no significant hazards consideration under the standards set forth in 10 CFR 50.92, Issuance of amendment.

Beaver Valley Power Station, Unit Nos. 1 and 2 L-20-298 Page 2 There are no regulatory commitments contained in this submittal. If there are any questions, or if additional information is required, please contact Mr. Phil H. Lashley, Manager - Fleet Licensing, at (330) 696-7208.

I declare under penalty of perjury that the foregoing is true and correct. Executed on 9

November ____, 2020.

Sincerely, Rod L. Penfield

Attachment:

Technical Specification Page Markups cc: NRC Region I Administrator NRC Resident Inspector NRR Project Manager Director BRP/DEP Site BRP/DEP Representative

Attachment L-20-298 Technical Specification Page Markups (2 pages follow)

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.

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 required for OPERABILITY of a logic circuit 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 signals (AFD) between the top and bottom halves of a two section excore neutron detector.

CERTIFIED FUEL HANDLER A CERTIFIED FUEL HANDLER is an individual who complies with the provisions of the CERTIFIED FUEL HANDLER training and retraining program required by Specification 5.3A.2.

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 monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY. 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.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

Beaver Valley Units 1 and 2 1.1 - 1 Amendments 278 / 161

Definitions 1.1 1.1 Definitions MASTER RELAY TEST A MASTER RELAY TEST shall consist of energizing all master relays in the channel required for channel OPERABILITY and verifying the OPERABILITY of each required master relay. The MASTER RELAY TEST shall include a continuity check of each associated required slave relay. The MASTER RELAY TEST may be performed by means of any series of sequential, overlapping, or total steps.

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.

NON-CERTIFIED OPERATOR A NON-CERTIFIED OPERATOR is a non-licensed operator who complies with the qualification requirements of Specification 5.3A.1, but is not a CERTIFIED FUEL HANDLER.

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 Unit 2 UFSAR, and Chapter 13, Initial Tests and Operation, of the Unit 1 UFSAR,

b. Authorized under the provisions of 10 CFR 50.59, or

c. Otherwise approved by the Nuclear Regulatory Commission.

PRESSURE AND The PTLR is the unit specific document that provides the TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including REPORT (PTLR) heatup and cooldown rates and the Overpressure Protection System setpoint and enable temperature, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.4.

Beaver Valley Units 1 and 2 1.1 - 4 Amendments 278 / 161