WBL-21-034, Emergency Plan Implementing Procedure Revision

Emergency Plan Implementing Procedure Revision

ML21182A040
Person / Time
Site:	Watts Bar
Issue date:	07/01/2021
From:	Anthony Williams Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
WBL-21-034
Download: ML21182A040 (2)

Text

TENNESSEE 1\14 VALLEY AUTHORITY Post Office Box 2000, Spring City, Tennessee 37381 WBL-21-034 July 1, 2021 10 CFR 50.54(q)(5) 10 CFR 72.44(f)

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 and Unit 2 Facility Operating License Nos. NPF-90 and NPF-96 NRC Docket Nos. 50-390, 50-391, and 72-1048

Subject:

Emergency Plan Implementing Procedure Revision Pursuant to Title 10, Code of Federal Regulations (10 CFR) 50.54(q)(5), and 10 CFR 72.44(f),

the Tennessee Valley Authority (TVA) is submitting a description of change to the Watts Bar Nuclear Plant (WBN) Radiological Emergency Plan (REP). The affected document is the WBN Emergency Plan Implementing Procedure (EPIP) listed below:

EPIP Revision Title Effective Date 1 54 Emergency Plan Classification Logic 06/22/2021 Description of Changes EPIP-1 revision 54 enacted the following changes:

Revised the Emergency Action Level (EAL) threshold value in Attachment 1 (Emergency Classification Wallboards) Tables R1 in both Hot and Cold Initiating Conditions Wall Boards and in Initiating Condition (IC) RU1 (Release of gaseous or liquid radioactivity greater than 2 times the ODCM (Offsite Dose Calculation Manual) limits for 60 minutes or longer) due to replacement of Unit 1 Steam Generator Blow Down (SGBD) radiation monitors and revision of calculation WBNTSR115 (Radiological Emergency Plan Effluent Radiation Monitor EALs and Radiation Alert Levels) to revision 23.

IC SU3 (Reactor coolant activity greater than Technical Specification allowable limits) was updated to remove mode applicability statement since it is now applicable in all hot modes in IC discussion and on both Attachment 1 Wall boards.

U.S. Nuclear Regulatory Commission WBL-21-034 Page 2 July 1, 2021

• Reactor Coolant System (RCS) gross specific activity was replaced with Dose Equivalent Xenon (XE-133) in the IC SU3 discussion and on both Attachment 1 Wall boards .

• Wording for ICs CA1 (Loss of RCS inventory) and CU1 (Unplanned loss of RCS inventory for 15 minutes or longer) was updated to clarify ICs in accordance with the Nuclear Regulatory Commission's (NRC) response to EPFAQ 2019-01 (Emergency Preparedness Program Frequently Asked Question) in both Attachment 1 Wall boards and ICs' discussions.

• Minor editorial changes were made to revision log page numbers for revision 52 and IC Table of Contents page numbers.

The above change was evaluated in accordance with 10 CFR 50 .54(q)(3) and 10 CFR 72.44(f) .

TVA determined that the change did not reduce the effectiveness of the WBN REP. The WBN REP , as revised , continues to meet the requirements in Appendix E to 10 CFR 50 and the plann ing standards of 10 CFR 50.47(b).

There are no new regulatory commitments in this letter. Please direct all questions concerning this matter to Mike White , Emergency Preparedness Manager, at (423) 365-3232.

Anthony L. Williams IV Site Vice President Watts Bar Nuclear Plant cc:

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRC Project Manager - Watts Bar Nuclear Plant NRC Director - Division of Spent Fuel Management, NMSS