ML20013C686
| ML20013C686 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/09/2020 |
| From: | Michael Mahoney Plant Licensing Branch II |
| To: | Nair A State of SC, Dept of Health & Environmental Control |
| References | |
| : L-2019-LLA-0191 | |
| Download: ML20013C686 (3) | |
Text
From:
Mahoney, Michael Sent:
Thursday, January 9, 2020 1:20 PM To:
Nair, Anuradha
Subject:
State Notification of Amendments to Catawba Nuclear Station, Units 1 & 2:
Revise TS 3.0.5 Attachments:
84 FR 59657.pdf Mrs. Nair, We are near completion of amendments for the Catawba Nuclear Station (Catawba),
Units 1 & 2, to revise their Technical Specifications (TS). The amendments would modify TS 3.0, Surveillance Requirement (SR) Applicability, to correct a typographical error introduced by license amendment nos. 235 and 231. Specifically, SR 3.0.5 is proposed to be revised to refer to limiting condition of operation (LCO) 3.0.9, instead of 3.0.8. The proposed change is administrative in nature.
The application is September 2, 2019, (ADAMS Accession No. ML19247B321).
The no significant hazards consideration determination was noticed in the Federal Register on November 5, 2019 (84 FR 59657). Attached.
Please respond if you have any or no comments.
Thanks Mike Michael Mahoney McGuire and Catawba Project Manager, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Desk: (301)-415-3867 Email: Michael.Mahoney@NRC.GOV
Hearing Identifier:
NRR_DRMA Email Number:
382 Mail Envelope Properties (BL0PR0901MB326647B8FC8627DD6CA1C8F6E5390)
Subject:
State Notification of Amendments to Catawba Nuclear Station, Units 1 & 2:
Revise TS 3.0.5 Sent Date:
1/9/2020 1:19:40 PM Received Date:
1/9/2020 1:19:42 PM From:
Mahoney, Michael Created By:
Michael.Mahoney@nrc.gov Recipients:
"Nair, Anuradha" <naira@dhec.sc.gov>
Tracking Status: None Post Office:
BL0PR0901MB3266.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 1024 1/9/2020 1:19:42 PM 84 FR 59657.pdf 42343 Options Priority:
Normal Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
59657 Federal Register / Vol. 84, No. 214 / Tuesday, November 5, 2019 / Notices hearing docket. Participants are requested not to include personal privacy information, such as social security numbers, home addresses, or personal phone numbers in their filings, unless an NRC regulation or other law requires submission of such information. For example, in some instances, individuals provide home addresses in order to demonstrate proximity to a facility or site. With respect to copyrighted works, except for limited excerpts that serve the purpose of the adjudicatory filings and would constitute a Fair Use application, participants are requested not to include copyrighted materials in their submission.
For further details with respect to these license amendment applications, see the application for amendment which is available for public inspection in ADAMS and at the NRCs PDR. For additional direction on accessing information related to this document, see the Obtaining Information and Submitting Comments section of this document.
Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, Catawba Nuclear Station, Units 1 and 2, York County, South Carolina Date of amendment request:
September 4, 2019. A publicly available version is in ADAMS under Accession No. ML19247B321.
Description of amendment request:
The amendments would modify Technical Specification (TS) 3.0, Surveillance Requirement (SR)
Applicability, to correct a typographical error introduced by License Amendment Nos. 235 and 231.
Specifically, SR 3.0.5 is proposed to be revised to refer to Limiting Condition for Operation (LCO) 3.0.9, instead of 3.0.8. The proposed change is administrative in nature.
Basis for proposed no significant hazards consideration determination:
As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change to revise SR 3.0.5 to refer to LCO 3.0.9 is administrative in nature and does not change the technical content of the TS. The proposed change does not adversely affect accident initiators or precursors nor alter the design assumptions, conditions or configurations of the facility.
The proposed change does not alter or prevent the capability of structures, systems and components (SSCs) to perform their intended function to mitigate the consequences of an initiating events within the assumed acceptance limits.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed change to revise SR 3.0.5 to refer to LCO 3.0.9 is administrative in nature and does not change the technical content of the TS. The proposed change does not alter the design requirements of any SSC or its function during accident conditions. The proposed change does not involve a physical alteration to the plant or any changes in methods governing normal plant operation.
The proposed change does not alter any assumptions made in the safety analysis.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in the margin of safety?
Response: No.
The proposed change to revise SR 3.0.5 to refer to LCO 3.0.9 is administrative in nature and does not change the technical content of the TS. The proposed change does not alter the way safety limits, limiting safety system settings or limiting conditions for operation are determined. The safety analysis acceptance criteria are not affected by the proposed change. The proposed change will not result in plant operation in a configuration outside the design basis and does not adversely affect systems that respond to safely shutdown the plant and maintain the plant in a safety shutdown condition.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
The NRC staff has reviewed the licensees analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.
Attorney for licensee: Kate B. Nolan, Deputy General Counsel, Duke Energy Carolinas, LLC., 550 South Tryon StreetDEC45A, Charlotte, NC 28202-1802.
NRC Branch Chief: Michael T.
Markley.
Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, Catawba Nuclear Station (Catawba), Units 1 and 2, York County, South Carolina Date of amendment request: July 2, 2019. A publicly available version is in ADAMS under Accession No. ML19183A038.
Description of amendment request:
The amendments would modify Technical Specification (TS) 3.4.3, RCS
[Reactor Coolant System] Pressure and Temperature (P/T) Limits. Specifically, the P/T limit curves in Figures 3.4.3-1 and 3.4.3-2 for Unit 1 would be updated since the existing Unit 1 curves are only applicable up to 30.7 full power effective years (EFPY), which is expected to be reached during Operating Cycle 26 (early 2021). The new Unit 1 (P/T) limit curves will be applicable until 42.7 EFPY. Although the proposed change only impacts Unit 1, the request is docketed under both Catawba, Units 1 and 2, since the TSs are common to both Units 1 and 2.
Basis for proposed no significant hazards consideration determination:
As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change revises TS 3.4.3 to reflect updated P/T limit curves in Figures 3.4.3-1 (UNIT 1 ONLY) and 3.4.3-2 (UNIT 1 ONLY) that are applicable until 42.7 EFPY.
The proposed change does not involve physical changes to the plant or alter the reactor coolant system (RCS) pressure boundary (i.e., there are no changes in operating pressure, materials or seismic loading). The proposed P/T limit curves and Adjusted Reference Temperature (ART) values for TS 3.4.3 with an applicability term of 42.7 EFPY provide continued assurance that the fracture toughness of the reactor pressure vessel (RPV) is consistent with analysis assumptions and NRC regulations.
The methodology used to develop the proposed P/T limit curves provides assurance that the probability of a rapidly propagating failure will be minimized. The proposed P/T limit curves, with the applicability term of 42.7 EFPY, will continue to prohibit operation in regions where it is possible for brittle fracture of reactor vessel materials to occur, thereby assuring that the integrity of the RCS pressure boundary is maintained.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed change revises TS 3.4.3 to reflect updated P/T limit curves in Figures 3.4.3-1 (UNIT 1 ONLY) and 3.4.3-2 (UNIT 1 ONLY) that are applicable until 42.7 EFPY.
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