CNL-18-096, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions

Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions

ML18212A277
Person / Time
Site:	Browns Ferry, Watts Bar, Sequoyah
Issue date:	07/30/2018
From:	Henderson E Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
CNL-18-096
Download: ML18212A277 (4)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-18-096 July 30, 2018 10 CFR 50.54(q) 10 CFR 72.44(f)

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, 50-296, and 72-052 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327, 50-328, and 72-034 Watts Bar Nuclear Plant, Units 1 and 2 Facility Operating License Nos. NPF-90 and NPF-96 NRC Docket Nos. 50-390, 50-391, and 72-1048

SUBJECT:

Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions

References:

1.

NRC to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendments Regarding Request to Upgrade Emergency Action Level Scheme (CAC Nos. MF9054, MF9055, MF9056, MF9057, MF9058, MF9059, and MF9060; EPID L-2017-LLA-0160), dated December 22, 2017 (ML17289A032)

2.

Nuclear Energy Institute document NEI 99-01, Revision 6, Methodology for Development of Emergency Action Levels for Non-Passive Reactors, dated November 12, 2012 (ML12326A809)

3.

NRC to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2 - Correction to an Omitted Reference for License Amendments Regarding Request to Upgrade Emergency Action Level Scheme (CAC Nos. MF9054, MF9055, MF9056, MF9057, MF9058, MF9059, and MF9060; EPID L-2017-LLA-0160), dated May 29, 2018 (ML18138A452)

U.S. Nuclear Regulatory Commission CNL-18-096 Page 2 July 30, 2018 In accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.54(q)(4) and 10 CFR 72.44(f), Tennessee Valley Authority (TVA) is submitting a description of changes to the TVA Radiological Emergency Plan (REP), Central Emergency Control Center (CECC) Emergency Plan Implementing Procedures (EPIPs), and an Emergency Preparedness Department Procedure (EPDP).

In Reference 1, the NRC approved Watts Bar Nuclear Plant (WBN), Sequoyah Nuclear Plant (SQN) and Browns Ferry Nuclear Plant (BFN) implementation of an Emergency Action Level (EAL) scheme based on the guidance contained in Reference 2, Nuclear Energy Institute (NEI) document NEI 99-01, Revision 6. The Nuclear Regulatory Commission (NRC) approval was later corrected by Reference 3 that added a reference to previously omitted TVA responses to requests for additional information. Based on the above information, TVA has updated the REP, EDPD, and EPIPs as described below.

The affected documents are the Generic REP, Appendixes A, B, and C of the REP, EPDP-1, and EPIPs 1, 6, and 7 as indicated in Table 1 below.

Table 1 Document Revision Title Effective Date Generic REP 108 Radiological Emergency Plan (Generic Part) 7/03/2018 REP, Appendix A 110 Browns Ferry Nuclear Plant Radiological Emergency Plan, Appendix A 7/03/2018 REP, Appendix B 106 Sequoyah Nuclear Plant Radiological Emergency Plan, Appendix B 7/03/2018 REP, Appendix C 113 Watts Bar Nuclear Plant Radiological Emergency Plan, Appendix C 7/03/2018 EPIP-1 65 Central Emergency Control Center (CECC)

Operations 7/03/2018 EPDP-1 15 Procedures, Maps, and Drawings 7/03/2018 EPIP-6 42 CECC Plant Assessment Staff Procedure for Alert, Site Area Emergency, and General Emergency 7/03/2018 EPIP-7 40 CECC Radiological Assessment Staff Procedure for Alert, Site Area Emergency, and General Emergency 7/03/2018

U.S. Nuclear Regulatory Commission CNL-18-096 Page 3 July 30, 2018 Description of Changes and Summary of Analysis The Generic REP was revised to update the Protective Action Recommendation (PAR) flowchart and the definition of Rapid Progressing Severe Accident (RPSA), modify the continuous assessment block, make other changes to simplify the decision logic, and reflect the relocation of the classification scheme from the REP appendices to the site specific EPIP-1. This revision also corrected references to outdated exercise cycles, removed outdated references for vendor support, and made other minor editorial changes.

REP Appendix A was revised to convert the procedure to the TVA procedure template. In addition, Sections 1.0 and 2.0 were added to state the purpose of the procedure and to discuss event classification methodology. The EAL bases were relocated from the REP Appendix A to BFN EPIP-1. Other minor editorial changes were also made.

REP Appendix B was revised to convert the procedure to the TVA procedure template. In addition, the introductory material was in some cases revised, replaced, or relocated. The EAL bases were relocated from Appendix B to the SQN EPIP-1. References were relocated to the end of the document and revised, as needed. Other minor editorial changes were also made.

REP Appendix C was revised to convert the procedure to the TVA procedure template. In addition, the introductory material was in some cases revised, replaced, or relocated. The notification process following a declaration was also updated to remove reference to the Operations Duty Specialist. The reference to the Technical Support Center Board Writer position was removed from Figure 2-C. Miscellaneous deletions, additions, and corrections of references were made. The EAL bases were relocated from Appendix C to the WBN EPIP-1. Other minor editorial changes were also made.

CECC EPIP-1 was revised to update the PAR flowchart and the definition of RPSA based on the EAL classification scheme changes, modify the continuous assessment block, and make several other changes to simplify the decision logic. In addition, this revision removed the incorrect reference to the CECC Public Information Staff, updated the title for the Alabama Governors Authorized Representative, added to the items for NRC briefs, and clarified the language related to the start time of the notification. Other minor editorial changes were also made.

EPDP-1 was revised to align this procedure with the REP by adding new review and approval requirements for each of the site EPIP-1s as a result of the relocation of the EAL bases from the REP to the site EPIP-1s.

CECC EPIP-6 was revised to update the PAR flowchart and the definition of RPSA based on the EAL classification scheme changes, modify the continuous assessment block, and make several other changes to simplify the decision logic. In addition, this revision added Flexible and Diverse (FLEX) Support Instructions to the reference material. Other minor editorial changes were also made.

U.S. Nuclear Regulatory Commission CNL-18-096 Page4 July 30, 2018 CECC EPIP-7was revised to update the PAR flowchart and to update the definition of RPSA based on the EAL classification scheme changes, modify the continuous assessment block, and make several other changes to simplify the decision logic. In addition, this revision added an item to the Radiological Assessment Manager's checklist for obtaining fixed siren radiation monitor data. Other minor editorial changes were also made.

The above changes were evaluated in accordance with 10 CFR 50.54(q)(3) and 10 CFR 72.44(f). TVA determined that the changes did not reduce the effectiveness of the TVA REP.

The TVA REP, EPIPs, and EDPD, as revised, continue to meet the requirements in Appendix E to 10 CFR 50 and the planning standards of 10 CFR 50.47(b).

There are no new regulatory commitments in this letter. If you have any questions regarding this submittal, please contact Ed Schrull at (423) 751-3850.

Respectfully,

~!Ak-E. K. Henderson Director, Nuclear Regulatory Affairs cc:

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