ML16244A038: Difference between revisions
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{{#Wiki_filter: | {{#Wiki_filter:1 NRR-PMDAPEm Resource From: Sreenivas, V Sent: Tuesday, August 30, 2016 1:45 PM To: Sreenivas, V | ||
==Subject:== | ==Subject:== | ||
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The licensee proposed to use sleeves as described in ASME Code Case N-786-2 to repair the degraded 3-inch drain line of the nuclear service water system piping. The temporary repair will be effective until next refueling outage. The proposed alternative took exceptions and modifications to certain requirements of Code Case N-786-2. The NRC staff has not approved Code Case N-786-2. However, the NRC staff finds that the proposed alternative with exceptions and modifications to the code case are acceptable. The NRC staff finds the licensee's hardship justification is acceptable. | The licensee proposed to use sleeves as described in ASME Code Case N-786-2 to repair the degraded 3-inch drain line of the nuclear service water system piping. The temporary repair will be effective until next refueling outage. The proposed alternative took exceptions and modifications to certain requirements of Code Case N-786-2. The NRC staff has not approved Code Case N-786-2. However, the NRC staff finds that the proposed alternative with exceptions and modifications to the code case are acceptable. The NRC staff finds the licensee's hardship justification is acceptable. | ||
The NRC staff has determined that the proposed alter native will provide reasonabl e assurance that the structural integrity and leak tightness of the degraded nuclear service water system piping until next refueling outage. | The NRC staff has determined that the proposed alter native will provide reasonabl e assurance that the structural integrity and leak tightness of the degraded nuclear service water system piping until next refueling outage. Authorization read by Michael Markley, Chief of the Plant Licensing Branch II-1, Office of Nuclear Reactor Regulation | ||
Authorization read by Michael Markley, Chief of the Plant Licensing Branch II-1, Office of Nuclear Reactor Regulation | |||
As Chief of the Plant Licensing Branch II-1, Office of Nuclear Reactor Regulation, I agree with the evaluation made by the Component Performance, Non-Destructive Examination, and Testing Branch. | As Chief of the Plant Licensing Branch II-1, Office of Nuclear Reactor Regulation, I agree with the evaluation made by the Component Performance, Non-Destructive Examination, and Testing Branch. |
Revision as of 06:23, 8 July 2018
ML16244A038 | |
Person / Time | |
---|---|
Site: | McGuire ![]() |
Issue date: | 08/30/2016 |
From: | V Sreenivas Plant Licensing Branch II |
To: | V Sreenivas Plant Licensing Branch II |
References | |
Download: ML16244A038 (3) | |
Text
1 NRR-PMDAPEm Resource From: Sreenivas, V Sent: Tuesday, August 30, 2016 1:45 PM To: Sreenivas, V
Subject:
Temporary Verbal Authorization: McGuire Nuclear Station, Unit 1: Relief Request 16-
MN-003 Alternative for the Temporary Repair of degraded Nuclear Service Water
System Piping. Date of Temporary Verbal Authorization: August 29, 2016 at 11 am Project Manager: V. Sreenivas, (301) 415-2597 VERBAL AUTHORIZATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST 16-MN-003 ALTERNATIVE REPAIR FOR NUCLEAR SERVICE WATER SYSTEM PIPING MCGUIRE NUCLEAR STATION UNIT 1 DUKE ENERGY DOCKET NO. 50-369 Technical Evaluation read by David Alley, Chief of the Component Performance, Non-Destructive Examination, and Testing Branch, Office of Nuclear Reactor Regulation
By letters dated August 10 and 18, 2016, Duke Energy (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, IWA-4420, at McGuire Nuclear Station Unit 1. Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2), the licensee requested to use the alternative in Relief Request 16-MN-003 on the basis that compliance with the specified ASME requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Relief Request 16-MN-003 provides an alternative for the temporary repair of degraded nuclear service water system piping.
The licensee proposed to use sleeves as described in ASME Code Case N-786-2 to repair the degraded 3-inch drain line of the nuclear service water system piping. The temporary repair will be effective until next refueling outage. The proposed alternative took exceptions and modifications to certain requirements of Code Case N-786-2. The NRC staff has not approved Code Case N-786-2. However, the NRC staff finds that the proposed alternative with exceptions and modifications to the code case are acceptable. The NRC staff finds the licensee's hardship justification is acceptable.
The NRC staff has determined that the proposed alter native will provide reasonabl e assurance that the structural integrity and leak tightness of the degraded nuclear service water system piping until next refueling outage. Authorization read by Michael Markley, Chief of the Plant Licensing Branch II-1, Office of Nuclear Reactor Regulation
As Chief of the Plant Licensing Branch II-1, Office of Nuclear Reactor Regulation, I agree with the evaluation made by the Component Performance, Non-Destructive Examination, and Testing Branch.
The NRC staff has determined that complying with the ASME Code requirement would result in a hardship or
unusual difficulty without a compensating increase in the level of quality and safety. Furthermore, the NRC staf f has determined that the proposed Relief Request 16-MN-003 provides reasonable assurance of structural integrity and leak tightness of the repaired piping. Acco rdingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2) and, therefore, 2authorizes the proposed alternative for the McGuire Nuclear Station Unit 1 until next refueling outage which is scheduled for Fall 2017.
This authorization is for the requested relief and repair at McGuire Nuclear Station Unit 1 and does not imply or infer the NRC's approval of ASME Code Case N-786-2.
All other requirements of ASME Code,Section XI, for which relief was not specifically requested and authorized by the NRC staff remain applicable, including the third party review by the Authorized Nuclear In-service Inspector.
This verbal authorization does not preclude the NRC sta ff from asking additional questions regarding Relief Request 16-MN-003, while preparing the subsequent written safety evaluation.
Hearing Identifier: NRR_PMDA Email Number: 3026 Mail Envelope Properties (V.Sreenivas@nrc.gov20160830134400)
Subject:
Temporary Verbal Authorization: McGuire Nuclear Station, Unit 1: Relief Request 16-MN-003 Alternative for the Temporary Repair of degraded Nuclear Service Water System Piping. Sent Date: 8/30/2016 1:44:50 PM Received Date: 8/30/2016 1:44:00 PM From: Sreenivas, V Created By: V.Sreenivas@nrc.gov Recipients: "Sreenivas, V" <V.Sreenivas@nrc.gov> Tracking Status: None
Post Office: Files Size Date & Time MESSAGE 3633 8/30/2016 1:44:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: