ML22271A914
| ML22271A914 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Watts Bar, Sequoyah  |
| Issue date: | 12/07/2022 |
| From: | Kimberly Green NRC/NRR/DORL/LPL2-2 |
| To: | Jim Barstow Tennessee Valley Authority |
| Green K, NRR/DORL/LPL2-2 | |
| References | |
| EPID L-2022-LLA-0021 | |
| Download: ML22271A914 (23) | |
Text
December 7, 2022 Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
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 AMENDMENT NOS. 324, 347, AND 307; 360 AND 354; 157 AND 65 REGARDING A REVISION TO THE EMERGENCY ACTION LEVEL SCHEME (EPID L-2022-LLA-0021)
Dear Mr. Barstow:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment Nos. 324, 347, and 307 to Renewed Facility Operating Licenses Nos. DPR-33, DPR-52, and DPR-68 for the Browns Ferry Nuclear Plant, Units 1, 2, and 3, respectively; Amendment Nos. 360 and 354 to Renewed Facility Operating License Nos. DPR-77 and DPR-79, for the Sequoyah Nuclear Plant, Units 1 and 2, respectively; and Amendment Nos. 157 and 65 to Facility Operating License Nos. NPF-90 and NPF-96 for the Watts Bar Nuclear Plant, Units 1 and 2, respectively. These amendments are in response to your application dated January 27, 2022, as supplemented by letter dated June 9, 2022.
The amendments revise the Tennessee Valley Authority Radiological Emergency Plan emergency action level threshold value for HU2 to provide an additional method to declare this event.
A copy of the NRC staffs Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Kimberly J. Green, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, 50-296, 50-327, 50-328, 50-390, and 50-391
Enclosures:
- 1. Amendment No. 324 to DPR-33
- 2. Amendment No. 347 to DPR-52
- 3. Amendment No. 307 to DPR-68
- 4. Amendment No. 360 to DPR-77
- 5. Amendment No. 354 to DPR-79
- 6. Amendment No. 157 to NPF-90
- 7. Amendment No. 65 to NPF-96
- 8. Safety Evaluation cc: Listserv
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 324 Renewed License No. DPR-33
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Tennessee Valley Authority (TVA or the licensee) dated January 27, 2022, as supplemented by letter dated June 9, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, Renewed Facility Operating License No. DPR-33 is hereby amended by revision to the TVA Radiological Emergency Plan as set forth in TVAs application dated January 27, 2022, as supplemented by letter dated June 9, 2022, and evaluated in the NRC staffs safety evaluation for this amendment.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 180 days from the date of issuance or July 27, 2023, whichever occurs later.
FOR THE NUCLEAR REGULATORY COMMISSION Andrea D. Veil, Director Office of Nuclear Reactor Regulation Date of Issuance: December 7, 2022 Michael King Digitally signed by Michael King Date: 2022.12.07 15:06:51 -05'00'
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 347 Renewed License No. DPR-52
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Tennessee Valley Authority (TVA or the licensee) dated January 27, 2022, as supplemented by letter dated June 9, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, Renewed Facility Operating License No. DPR-52 is hereby amended by revision to the TVA Radiological Emergency Plan as set forth in TVAs application dated January 27, 2022, as supplemented by letter dated June 9, 2022, and evaluated in the NRC staffs safety evaluation for this amendment.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 180 days from the date of issuance or July 27, 2023, whichever occurs later.
FOR THE NUCLEAR REGULATORY COMMISSION Andrea D. Veil, Director Office of Nuclear Reactor Regulation Date of Issuance: December 7, 2022 Michael King Digitally signed by Michael King Date: 2022.12.07 15:07:09 -05'00'
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 307 Renewed License No. DPR-68
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Tennessee Valley Authority (TVA or the licensee) dated January 27, 2022, as supplemented by letter dated June 9, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, Renewed Facility Operating License No. DPR-68 is hereby amended by revision to the TVA Radiological Emergency Plan as set forth in TVAs application dated January 27, 2022, as supplemented by June 9, 2022, and evaluated in the NRC staffs safety evaluation for this amendment.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 180 days from the date of issuance or July 27, 2023, whichever occurs later.
FOR THE NUCLEAR REGULATORY COMMISSION Andrea D. Veil, Director Office of Nuclear Reactor Regulation Date of Issuance: December 7, 2022 Michael King Digitally signed by Michael King Date: 2022.12.07 15:07:21 -05'00'
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 360 Renewed License No. DPR-77
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Tennessee Valley Authority (TVA or the licensee) dated January 27, 2022, as supplemented by letter dated June 9, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, Renewed Facility Operating License No. DPR-77 is hereby amended by revision to the TVA Radiological Emergency Plan as set forth in TVAs application dated January 27, 2022, as supplemented by letter dated June 9, 2022, and evaluated in the NRC staffs safety evaluation for this amendment.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 180 days from the date of issuance or July 27, 2023, whichever occurs later.
FOR THE NUCLEAR REGULATORY COMMISSION Andrea D. Veil, Director Office of Nuclear Reactor Regulation Date of Issuance: December 7, 2022 Michael King Digitally signed by Michael King Date: 2022.12.07 15:07:34 -05'00'
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 354 Renewed License No. DPR-79
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Tennessee Valley Authority (TVA or the licensee) dated January 27, 2022, as supplemented by letter dated June 9, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, Renewed Facility Operating License No. DPR-79 is hereby amended by revision to the TVA Radiological Emergency Plan as set forth in TVAs application dated January 27, 2022, as supplemented by letter dated June 9, 2022, and evaluated in the NRC staffs safety evaluation for this amendment.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 180 days from the date of issuance or July 27, 2023, whichever occurs later.
FOR THE NUCLEAR REGULATORY COMMISSION Andrea D. Veil, Director Office of Nuclear Reactor Regulation Date of Issuance: December 7, 2022 Michael King Digitally signed by Michael King Date: 2022.12.07 15:07:47 -05'00'
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 157 License No. NPF-90
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Tennessee Valley Authority (TVA or the licensee) dated January 27, 2022, as supplemented by letter dated June 9, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, Facility Operating License No. NPF-90 is hereby amended by revision to the TVA Radiological Emergency Plan as set forth in TVAs application dated January 27, 2022, as supplemented by letter dated June 9, 2022, and evaluated in the NRC staffs safety evaluation for this amendment.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 180 days from the date of issuance or July 27, 2023, whichever occurs later.
FOR THE NUCLEAR REGULATORY COMMISSION Andrea D. Veil, Director Office of Nuclear Reactor Regulation Date of Issuance: December 7, 2022 Michael King Digitally signed by Michael King Date: 2022.12.07 15:08:01 -05'00'
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-391 WATTS BAR NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. NPF-96
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Tennessee Valley Authority (TVA or the licensee) dated January 27, 2022, as supplemented by letter dated June 9, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, Facility Operating License No. NPF-96 is hereby amended by revision to the TVA Radiological Emergency Plan as set forth in TVAs application dated January 27, 2022, as supplemented by letter dated June 9, 2022, and evaluated in the NRC staffs safety evaluation for this amendment.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 180 days from the date of issuance or July 27, 2023, whichever occurs later.
FOR THE NUCLEAR REGULATORY COMMISSION Andrea D. Veil, Director Office of Nuclear Reactor Regulation Date of Issuance: December 7, 2022 Michael King Digitally signed by Michael King Date: 2022.12.07 15:09:34 -05'00'
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMENDMENT NO. 324 TO RENEWED FACILITY OPERATING LICENSE DPR-33 AMENDMENT NO. 347 TO RENEWED FACILITY OPERATING LICENSE DPR-52 AMENDMENT NO. 307 TO RENEWED FACILITY OPERATING LICENSE DPR-68 AMENDMENT NO. 360 TO RENEWED FACILITY OPERATING LICENSE DPR-77 AMENDMENT NO. 354 TO RENEWED FACILITY OPERATING LICENSE DPR-79 AMENDMENT NO. 157 TO FACILITY OPERATING LICENSE NPF-90 AMENDMENT NO. 65 TO FACILITY OPERATING LICENSE NPF-96 BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 TENNESSEE VALLEY AUTHORITY DOCKET NOS. 50-259, 50-260, 50-296, 50-327, 50-328, 50-390, AND 50-391
1.0 INTRODUCTION
By application dated January 27, 2022 (Reference 1), as supplemented by letter dated June 9, 2022 (Reference 2), the Tennessee Valley Authority (TVA or the licensee) requested changes to the TVA Radiological Emergency Plan (REP) pursuant to section 50.54(q) of Title 10 of the Code of Federal Regulations (10 CFR) for the Browns Ferry Nuclear Plant (Browns Ferry), Units 1, 2, and 3; Sequoyah Nuclear Plant (Sequoyah), Units 1 and 2; and Watts Bar Nuclear Plant (Watts Bar), Units 1 and 2. The proposed amendments would revise the emergency action level (EAL) threshold value for HU2, which is an unusual event declaration due to a seismic event, to provide an additional method to declare this event.
The supplement dated June 9, 2022, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC or the Commission) staffs original proposed no significant hazards consideration determination as published in the Federal Register on March 22, 2022 (87 FR 16253).
2.0 REGULATORY EVALUATION
2.1 Regulatory Requirements Section 50.47 of 10 CFR Part 50, Emergency plans, sets forth emergency plan requirements for nuclear power plant facilities. The regulations in 10 CFR 50.47(a)(1)(i) state, in part, that:
... no initial operating license for a nuclear power reactor will be issued unless a finding is made by the NRC that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency.
Section 50.47(b) establishes the planning standards that the onsite and offsite emergency response plans must meet for the NRC staff to make a finding that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. Planning standard (4) of this section requires that onsite and offsite emergency response plans meet the following standard:
A standard emergency classification and action level scheme, the bases of which include facility system and effluent parameters, is in use by the nuclear facility licensee, and State and local response plans call for reliance on information provided by facility licensees for determinations of minimum initial offsite response measures.
Section 50.47(b)(4) requires the use of a standard emergency classification and action level scheme, assuring that implementation methods are relatively consistent throughout the industry for a given reactor and containment design while simultaneously providing an opportunity for a licensee to modify its EAL scheme as necessary to address plant-specific design considerations or preferences.
Section IV.B.1 of Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities, to 10 CFR Part 50, states, in part:
The means to be used for determining the magnitude of, and for continually assessing the impact of, the release of radioactive materials shall be described, including emergency action levels that are to be used as criteria for determining the need for notification and participation of local and State agencies, the Commission, and other Federal agencies, and the emergency action levels that are to be used for determining when and what type of protective measures should be considered within and outside the site boundary to protect health and safety. The emergency action levels shall be based on in-plant conditions and instrumentation in addition to onsite and offsite monitoring. By June 20, 2012, for nuclear power reactor licensees, these action levels must include hostile action that may adversely affect the nuclear power plant.
2.2 Regulatory Guidance The industry provided the Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors, (Reference 3) to the NRC, which the NRC staff endorsed by letter dated March 28, 2013, (Reference 4) as acceptable generic (i.e., not plant-specific) EAL scheme development guidance.
Although the EAL development guidance contained in NEI 99-01, Revision 6, is generic and may not be entirely applicable for some non-passive, large light-water reactor designs, it bounds the most typical accident and or event scenarios for which emergency response is necessary, in a format that allows for industry standardization and consistent regulatory oversight. Licensees may choose to develop plant-specific EAL schemes using NEI 99-01, Revision 6, with appropriate plant-specific alterations as applicable.
NRC Regulatory Issue Summary (RIS) 2003-18, including Supplements 1 and 2, Use of NEI 99-01, Methodology for Development of Emergency Action Levels (Reference 5), also provides guidance for developing or changing a standard EAL scheme. In addition, this RIS and its supplements provide recommendations to assist licensees, consistent with Section IV.B of Appendix E to 10 CFR Part 50, in determining whether to seek prior NRC approval of deviations from the guidance.
In summary, the NRC staff considers that NEI 99-01, Revision 6, is an acceptable method to develop plant-specific EALs that meet the requirements of Section IV.B of Appendix E to 10 CFR Part 50 and 10 CFR 50.47(b)(4), with the understanding that licensees may want to develop EALs that differ from the guidance document as allowed in Regulatory Guide 1.101, Emergency Response Planning and Preparedness for Nuclear Power Reactors (Reference 6).
3.0 TECHNICAL EVALUATION
The NRC staff evaluated the licensees application to determine if the proposed changes are consistent with the regulations and guidance discussed in sections 2.1 and 2.2 of this safety evaluation.
In its application and supplemental letter, the licensee submitted the proposed change to EAL HU2, the technical basis containing an evaluation and rationale for the proposed EAL change, and a line-by-line comparison of the proposed initiating condition, mode applicability, and EAL wording to that found in the currently approved TVA REP. The application states that the licensee used the terms difference and deviation as defined in RIS 2003-18, as supplemented, when comparing its proposed plant-specific EALs to the generic EALs in NEI 99-01, Revision 6.
The NRC staff verified that the proposed EAL change is consistent with the guidance provided in NEI 99-01, Revision 6 to assure that the proposed EAL change meets the requirements of Section IV.B of Appendix E to 10 CFR Part 50 and 10 CFR 50.47(b)(4). The NRC staff reviewed the proposed change to HU2, technical basis, and all additional information provided in the licensees application and supplemental letter.
Although the EALs must be plant-specific, the NRC staff reviewed the proposed HU2 for the following key characteristics of an effective EAL scheme to ensure consistency and regulatory stability:
Consistency, including standardization of intent, if not in actual wording (i.e., the EALs would lead to similar decisions under similar circumstances at different plants);
Human factors engineering and user friendliness; Potential for emergency classification level upgrade only when there is an increasing threat to public health and safety; Ease of upgrading and downgrading the emergency classification level; Thoroughness in addressing and disposing of the issues of completeness and accuracy raised in Appendix 1 to NUREG-0654 (Reference 7);
Technical completeness for each classification level; Logical progression in classification for multiple events, and The use of objective and observable values.
To aid in understanding the nomenclature used in this safety evaluation, the following convention is used:
The schemes generic information is organized by Recognition Category in the following order.
The Recognition Category letter is the first letter for EALs; o R - Abnormal Radiation Levels / Radiological Effluent; o C - Cold Shutdown / Refueling System Malfunction; o H - Hazards and Other Conditions Affecting Plant Safety; o S - System Malfunction.
The second letter signifies the emergency classification level; o U - Notification of Unusual Event (UE);
o A - Alert; o S - Site Area Emergency (SAE); and The number denotes the sequential subcategory designation from the plant-specific EAL scheme.
3.1 EAL HU2 The intent of this EAL is to ensure that an emergency classification is declared based upon a seismic event that results in accelerations at the plant site greater than specified for an operating basis earthquake. This EAL is primarily intended to ensure that key emergency response organization members and offsite response organizations are aware of the earthquake magnitude at the site and that post-event damage assessments are promptly implemented. This EAL is considered part of an EAL set containing EALs CA6 and SA9, depending on the operating mode applicable at the time of the event. Indications of earthquake induced damage to components containing radioactive materials are bounded by Recognition Category F, as well as EALs RA1, RS1, or RG1.
The NRC staff verified that the numbering, sequencing, formatting, logical progression, and instrumentation and setpoints for this EAL are consistent with the overall EAL scheme development guidance provided by NEI 99-01, Revision 6, and address the site-specific implementation strategies provided, and are, therefore, consistent with a standard EAL scheme, as required by 10 CFR 50.47(b)(4). The NRC staff also verified that the EAL is worded in an unambiguous manner that addresses human factors engineering and user-friendliness concerns; is technically complete for this classification level, addresses completeness and accuracy issues raised in Appendix 1 to NUREG-0654; and uses objective and observable values based on site-specific indications.
Based on the above, the NRC staff concludes that the plant-specific implementation method for this EAL for each plant is in alignment with the key characteristics of an effective EAL scheme (identified in Section 3.0 above) and meets the requirements of 10 CFR 50.47(b)(4) and Section IV.B of Appendix E to 10 CFR Part 50. Therefore, the NRC staff finds this EAL acceptable.
3.2 Review Summary The NRC staff has reviewed the technical bases for the proposed changes to the Browns Ferry, Sequoyah, and Watts Bar EAL HU2, and the licensees evaluation of the proposed changes.
The licensee chose to modify EAL HU2 from its currently approved EAL schemes, which are based on the generic EAL scheme development guidance provided in NEI 99-01, Revision 6, to provide an alternative method to assess HU2. This alternate method applies when seismic monitoring equipment is not available and control room personnel feel an actual or potential seismic event that is confirmed using site-specific procedures for earthquakes or by the Shift Manager or Site Emergency Director within 15 minutes of the event. The NRC staff verified that this modification remains consistent with the guidance provided in NEI 99-01, Revision 6, and the licensees EAL schemes. Therefore, the proposed changes continue to meet the requirements in Section IV.B.1 to 10 CFR Part 50 and the planning standard of 10 CFR 50.47(b)(4).
The NRC staff determined that the proposed EAL changes, continue to use objective and observable values, are worded in a manner that addresses human factors engineering and user friendliness concerns, follow logical progressions for escalating events, and allow for event downgrading and upgrading based upon the potential risk to the public health and safety.
Based on its review, the NRC staff finds that the licensees proposed EAL schemes, as revised, are acceptable and provide reasonable assurance that the licensee can and will take adequate protective measures in the event of a radiological emergency. Specifically, the staff concludes that the licensees proposed EAL schemes and site-specific EAL technical basis documents provided with the license amendment request, are acceptable for implementation.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Alabama State official and Tennessee State official were notified of the proposed issuance of the amendments on September 27, 2022. The State officials had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission previously issued a proposed finding that the amendments involve no significant hazards consideration published in the Federal Register on March 22, 2022 (87 FR 16253), and there has been no public comment on such finding. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
- 1.
Polickoski, J.T., Tennessee Valley Authority (TVA), letter to the U.S. Nuclear Regulatory Commission (NRC), Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change, dated January 27, 2022 (Agencywide Documents Access and Management System Accession No. ML22027A835).
- 2.
Barstow, J., TVA, letter to the U.S. NRC, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change, dated June 9, 2022 (ML22160A666).
- 3.
NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors, dated November 21, 2012 (ML13091A209).
- 4.
Thaggard, M., U.S. NRC, letter to Perkins-Grew, S., Nuclear Energy Institute, U.S.
Nuclear Regulatory Commission Review and Endorsement of NEI 99-01, Revision 6, dated November 2012 (TAC No. D92368), dated March 28, 2013 (ML12346A463).
- 5.
U.S. Nuclear Regulatory Commission, Regulatory Issue Summary 2003-18, Use of NEI 99-01, Methodology for Development of Emergency Action Levels, Revision 4, dated January 2003, dated October 8, 2003, including Supplement 1, dated July 13, 2004, and Supplement 2, dated December 12, 2005 (ML032580518, ML041550395, and ML051450482, respectively).
- 6.
U.S. Nuclear Regulatory Commission, Regulatory Guide 1.101, Revision 6, Emergency Response Planning and Preparedness for Nuclear Power Reactors (ML21111A090).
- 7.
U.S. Nuclear Regulatory Commission and Federal Emergency Management Agency, NUREG-0654/FEMA-REP-1, Revision 2, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, dated December 2019 (ML19347D139).
Principal Contributor: R. Hoffman, NSIR Date: December 7, 2022
ML22271A914 OFFICE NRR/DORL/LPLII-2/PM NRR/DORL/LPLII-2/LA NSIR/DPR/RLB/BC (A)
OGC - NLO w/edits NAME KGreen RButler FSacko LShrum DATE 09/27/2022 10/04/2022 09/08/2022 10/18/2022 OFFICE NRR/DORL/LPLII-2/BC NRR/DORL/D NRR/D NRR/DORL/LPLII-2/PM NAME DWrona BPham (GSuber for)
AVeil (MKing for)
KGreen DATE 11/10/2022 11/16/2022 12/07/2022 12/07/2022