ML24185A260
| ML24185A260 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/04/2024 |
| From: | Mahesh Chawla Plant Licensing Branch IV |
| To: | Entergy Operations |
| Wengert T | |
| References | |
| EPID L-2024-LLA-0045 | |
| Download: ML24185A260 (1) | |
Text
October 4, 2024 ANO Site Vice President Arkansas Nuclear One Entergy Operations, Inc.
N-TSB-58 1448 S.R. 333 Russellville, AR 72802
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 2 - ISSUANCE OF AMENDMENT NO. 335 RE: TO REVISE TYPOGRAPHICAL ERRORS IN TECHNICAL SPECIFICATIONS (EPID L-2024-LLA-0045)
Dear Site Vice President:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 335 to Renewed Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit 2 (ANO-2). The amendment consists of changes to the technical specifications (TSs) in response to your application dated April 4, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24095A063).
The amendment corrects three typographical errors in TS 6.5.18, Surveillance Frequency Control Program, and TS 6.6.8, Specific Activity, that were inadvertently introduced into the TSs by License Amendment Nos. 315 (ML19063B948) and 326 (ML21313A008). Since these errors were present in their respective notices to the public and were present during review, correction of the errors does not fall within the scope of the guidance provided by SECY-96-238, Proposed Guidance for Correction of Technical Specification Typographical Errors (ML20134M324); therefore, a license amendment request is required.
A copy of the related safety evaluation is also enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA - J. Drake for/
Mahesh L. Chawla, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-368
Enclosures:
- 1. Amendment No. 335 to NPF-6
- 2. Safety Evaluation cc: Listserv
ENTERGY OPERATIONS, INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 335 Renewed License No. NPF-6
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee), dated April 4, 2024, 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 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, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-6 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 335, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jennivine K. Rankin, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-6 and the Technical Specifications Date of Issuance: October 4, 2024 Jennivine K. Rankin Digitally signed by Jennivine K. Rankin Date: 2024.10.04 08:38:30 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 335 RENEWED FACILITY OPERATING LICENSE NO. NPF-6 ARKANSAS NUCLEAR ONE, UNIT 2 DOCKET NO. 50-368 Replace the following pages of Renewed Facility Operating License No. NPF-6 and the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Renewed Facility Operating License REMOVE INSERT Technical Specifications REMOVE INSERT 6-18a 6-18a 6-22a 6-22a
Renewed License No. NPF-6 Amendment No. 335 3
(4)
EOI, pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)
EOI, pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)
EOI, pursuant to the Act and 10 CFR Parts 30 and 70 to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed license shall be deemed to contain and is subject to conditions specified in the following Commission regulations in 10 CFR Chapter I; Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level EOI is authorized to operate the facility at steady state reactor core power levels not in excess of 3026 megawatts thermal. Prior to attaining this power level EOI shall comply with the conditions in Paragraph 2.C.(3).
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 335, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
Exemptive 2nd paragraph of 2.C.2 deleted per Amendment 20, 3/3/81.
(3)
Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following issuance of the renewed license or within the operational restrictions indicated.
The removal of these conditions shall be made by an amendment to the renewed license supported by a favorable evaluation by the Commission.
2.C.(3)(a)
Deleted per Amendment 24, 6/19/81.
ARKANSAS - UNIT 2 6-18a Amendment No. 273,315, 335 ADMINISTRATIVE CONTROLS 6.5.17 Metamic Coupon Sampling Program A coupon surveillance program will be implemented to maintain surveillance of the Metamic absorber material under the radiation, chemical, and thermal environment of the SFP. The purpose of the program is to establish the following:
Coupons will be examined on a two year basis for the first three intervals with the first coupon retrieved for inspection being on or before October 31, 2009 and thereafter at increasing intervals over the service life of the inserts.
Measurements to be performed at each inspection will be as follows:
a.
Physical observations of the surface appearance to detect pitting, swelling or other degradation, b.
Length, width, and thickness measurements to monitor for bulging and swelling c.
Weight and density to monitor for material loss, and d.
Neutron attenuation to confirm the B-10 concentration or destructive chemical testing to determine the boron content.
The provisions of SR 4.0.2 are applicable to the Metamic Coupon Sampling Program.
The provisions of SR 4.0.3 are not applicable to the Metamic Coupon Sampling Program.
6.5.18 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.
a.
The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.
b.
Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.
c.
The provisions of Surveillance Requirements 4.0.2 and 4.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.
ARKANSAS - UNIT 2 6-22a Amendment No. 326, 335 ADMINISTRATIVE CONTROLS 6.6.8 Specific Activity The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded the results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 335 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-6 ENTERGY OPERATIONS, INC.
ARKANSAS NUCLEAR ONE, UNIT 2 DOCKET NO. 50-368
1.0 INTRODUCTION
By application dated April 4, 2024 (Agencywide Documents Access and Management System Accession No. ML24095A063), Entergy Operations, Inc. (the licensee), requested changes to the technical specifications (TSs) for Arkansas Nuclear One, Unit 2 (ANO-2).
The proposed amendment would correct three typographical errors in TS 6.5.18, Surveillance Frequency Control Program, and TS 6.6.8, Specific Activity, that were inadvertently introduced into the TSs by License Amendment Nos. 315 (ML19063B948) and 326 (ML21313A008). Since these errors were present in their respective notices to the public and were present during review, correction of the errors does not fall within the scope of the guidance provided in SECY-96-238, Proposed Guidance for Correction of Technical Specification Typographical Errors (ML20134M324); therefore, a license amendment request is required.
2.0 REGULATORY EVALUATION
2.1 Description of Changes 2.1.1 Proposed Technical Specification Changes In the current ANO-2 TSs, limiting conditions for operation (LCOs) begin with the number three (3) and surveillance requirements (SRs) begin with the number four (4). In the Standard Technical Specifications (STS), including in NUREG-1432, Standard Technical Specifications, Combustion Engineering Plants, Volume 1, Specifications, Revision 5 (ML21258A421), which has not been adopted by ANO-2, LCOs and SRs both begin with the number three (3).
Technical Specifications Task Force (TSTF) travelers are written based on the STS and as such, TSTF-425 refers to SRs using the STS SR numbering scheme.
In the ANO-2 license amendment request dated February 6, 2018, related to TSTF-425 (ML18038B354), the licensee proposed, and the license was amended to state, at TS 6.5.18, Surveillance Frequency Control Program, Item c. the following:
The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.
The licensee now proposes to change this TS to reflect the numbering scheme of the ANO-2 TSs as opposed to the numbering scheme of the STS as follows, with changes in bold:
The provisions of Surveillance Requirements 4.0.2 and 4.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.
The licensee also proposes to insert the space that is missing between the words primary and coolant in the last sentence of TS 6.6.8, Specific Activity so that it states the following, with changes in bold:
and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.
2.2 Applicable Regulatory Requirements Section 182a of the Atomic Energy Act of 1954, as amended, requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The U.S. Nuclear Regulatory Commission (NRC, the Commission) requirements related to the content of TSs are in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Technical specifications. Pursuant to that regulation, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3) SRs; (4) design features; and (5) administrative controls.
Under 10 CFR 50.90, Application for amendment of license, construction permit, or early site permit, whenever a holder of an operating license desires to amend the license, application for an amendment must be filed with the Commission fully describing the changes desired, and following as far as applicable, the form prescribed for original applications. Under 10 CFR 50.92, Issuance of amendment, in determining whether an amendment to a license will be issued to the applicant, the Commission will be guided by the considerations which govern the issuance of initial licenses to the extent applicable and appropriate. Both the common standards for licenses and construction permits in 10 CFR 50.40(a), and those specifically for issuance of operating licenses in 10 CFR 50.57(a)(3), provide that there must be reasonable assurance that the activities at issue will not endanger the health and safety of the public.
3.0 TECHNICAL EVALUATION
The proposed amendment contains no technical changes; all the proposed changes are editorial or corrective changes that improve the clarity and accuracy of the existing TSs.
Therefore, there is reasonable assurance that the health and safety of the public will remain unaffected following the approval of these proposed changes.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Arkansas State official was notified of the proposed issuance of the amendment on September 18, 2024. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment makes editorial, corrective or other minor revisions to the license. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration published in the Federal Register on June 11, 2024 (89 FR 49238), and there has been no public comment on such finding.
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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Jason Drake, NRR Date: October 4, 2024
- concurrence via email OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DSS/STSB/BC OGC - NLO NAME JDrake PBlechman SMehta ALeatherman DATE 7/3/2024 8/28/2024 9/26/2024 9/19/2024 OFFICE NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME JRankin MChawla (JDrake for)
DATE 10/3/2024 10/4/2024