ML24249A136
| ML24249A136 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Dresden, Nine Mile Point, Hope Creek, Susquehanna, Brunswick, Duane Arnold, Quad Cities, LaSalle  |
| Issue date: | 09/04/2024 |
| From: | Zozula C Westinghouse |
| To: | Hoc H Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LTR-NRC-24-35, EN 57304 | |
| Download: ML24249A136 (1) | |
Text
From:
Zozula, Camille T.
To:
Hoc, HOO X
Subject:
[External_Sender] Westinghouse 10 CFR 21 report Date:
Wednesday, September 4, 2024 6:51:35 PM Attachments:
image001.png LTR-NRC-24-35 Part 21 Reporting.pdf
- Hello, Please see the attached non-proprietary report for a 10 CFR 21 report from Westinghouse Electric Company.
Camille Zozula Manager, Global Nuclear Regulatory Affairs Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 15066 USA 412-374-2577 zozulact@westinghouse.com www.westinghousenuclear.com This e-mail may contain proprietary information of the sending organization. Any unauthorized or improper disclosure, copying, distribution, or use of the contents of this e-mail and attached document(s) is prohibited. The information contained in this e-mail and attached document(s) is intended only for the personal and private use of the recipient(s) named above. If you have received this communication in error, please notify the sender immediately by email and delete the original e-mail and attached document(s).
Westinghouse Non-Proprietary Class 3 Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, Pennsylvania 16066 USA
© 2024 Westinghouse Electric Company LLC. All Rights Reserved U.S. Nuclear Regulatory Commission Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Direct tel: (412) 374-2577 e-mail: zozulact@westinghouse.com LTR-NRC-24-35 September 4, 2024
Subject:
Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 The following information is provided pursuant to the requirements of 10 CFR Part 21 to report a defect that could lead to a substantial safety hazard. This issue concerns the Westinghouse designed and manufactured CR99' and Trident XTM boiling water reactor (BWR) control rod blades (CRBs).
(i)
Name and address of the individual or individuals informing the Commission.
Camille T. Zozula Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, Pennsylvania 16066 (ii) Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect.
Generations 2 and 3 CR99, CR99+, and Trident X BWR CRBs (iii) Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect.
Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, Pennsylvania 16066 USA Westinghouse Electric Sweden AB SE-721 63 Vasteras Sweden (iv) Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply.
The CR99 CRBs were designed with dimensional and material choices for mechanical stability such that the mechanical function is maintained throughout the life of the control rod. However, observed cracking at US licensees, resulting from irradiation assisted stress corrosion cracking (IASCC), occurred before the nuclear end of life. Therefore, the current depletion limits that define nuclear end of life are not sufficient to prevent cracking, and the
LTR-NRC-24-35 Page 2 of 4 continued use of uninspected CRBs can lead to further cracking. With severe cracking of the CRBs, boron loss can occur and negatively impact the shutdown margin.
To date, Westinghouse is aware that plants which experienced CRB cracking have been able to scram their cracked CRBs, safely shut down the reactor, and maintain it in a safe shutdown condition.
Trident X is susceptible to IASCC and within the scope of this notification. However, the first Trident X CRBs were installed in a US operating plant earlier in 2024 and have operated for less than one cycle.
(v)
The date on which the information of such defect or failure to comply was obtained.
The Westinghouse President and CEO was informed of this issue on September 2, 2024.
(vi) In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, supplied for, being supplied for, or may be supplied for, manufactured, or being manufactured for one or more facilities or activities subject to the regulations in this part.
Non-US licensees are not subject to the regulations in this part and are identified with (*).
Operating Plants with Generations 2 and 3 CR99 CRBs Brunswick Units 1 and 2 (194)
Dresden Unit 3 (8)
Forsmark Units 1, 2, and 3 (99)*
Hatch Units 1 and 2 (124)
Hope Creek (122)
Kernkraftwerk Leibstadt (21)*
Kuosheng Units 1 and 2 (cold shutdown) (114)*
La Salle Unit 1 (7)
Nine Mile Point Unit 2 (12)
Olkiluoto Units 1 and 2 (33)*
Oskarshamn Unit 3 (114)*
Quad Cities Unit 1 (12)
Susquehanna Units 1 and 2 (222)
Permanently Shutdown/Decommissioned Plants with Generations 2 and 3 CR99 CRBs Duane Arnold (14)
Gundremmingen B and C (4)*
Isar Unit 1 (12)*
Ringhals Unit 1 (34)*
LTR-NRC-24-35 Page 3 of 4 Operating Plants with CR99+ CRBs Forsmark Units 1 and 2 (70)*
Olkiluoto Units 1 and 2 (80)*
Oskarshamn Unit 3 (131)*
Decommissioned Plants with CR99+ CRBs Ringhals Unit 1 (16)*
Operating Plants with Trident X CRBs Brunswick Unit 1 (6)
(vii) The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action.
Westinghouse generated a CAP Issue Report (IR), and a root cause analysis is in-progress.
The CAP IR is scheduled for closure in Q1 2025 and includes the following actions:
x Review WCAP-16182 and revise accordingly; submit to NRC for review and approval.
x Develop an inspection and surveillance plan in coordination with U.S. licensees and communicate inspection results to stakeholders.
x Develop a licensing commitment management tool.
x Identify and address gaps in qualifications, training, and organizational responsibilities.
(viii) Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees.
Westinghouse continues to communicate with impacted licensees and will issue plant-specific operating recommendations.
LTR-NRC-24-35 Page 4 of 4 (ix)
In the case of an early site permit, the entities to whom an early site permit was transferred.
Not applicable Camille T. Zozula Part 21 Program Manager cc:
E. Lenning