ML14161A351: Difference between revisions

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{{#Wiki_filter:1NRR-PMDAPEm ResourceFrom:Miller, EdSent:Tuesday, June 10, 2014 11:02 AMTo:'Vu, Phong T (Phong.Vu@duke-energy.com)'
==Subject:==
Draft RAI for Relief Request 13-MN-003Attachments:Draft EPNB RAI.docxPT, The NRC staff's draft RAI for the subject relief request is attached to this e-mail. The draft RAI is not an official NRC staff request and is being provided to you to facilitate a subsequent conference call to determine: 1) If the questions clearly convey the NRC staff information needs; 2) Whether the regulatory basis for the questions is understood; 3) Whether the information is already available in existing, docketed, correspondence; and 4) To determine an appropriate response time-frame. After you've had a chance to review the draft information request, please contact me to schedule the conference call. 
Ed Miller (301) 415-2481 Hearing Identifier:  NRR_PMDA  Email Number:  1352  Mail Envelope Properties  (9C2386A0C0BC584684916F7A0482B6CAFD0D8A321D) 
==Subject:==
Draft RAI for Relief Request 13-MN-003  Sent Date:  6/10/2014 11:02:20 AM  Received Date:  6/10/2014 11:02:00 AM  From:    Miller, Ed  Created By:  Ed.Miller@nrc.gov  Recipients:    "'Vu, Phong T (Phong.Vu@duke-energy.com)'" <Phong.Vu@duke-energy.com>  Tracking Status: None Post Office:  HQCLSTR02.nrc.gov  Files    Size      Date & Time  MESSAGE    669      6/10/2014 11:02:00 AM Draft EPNB RAI.docx    27397  Options  Priority:    Standard  Return Notification:    No  Reply Requested:    No  Sensitivity:    Normal  Expiration Date:      Recipients Received:
DRAFT REQUEST FOR ADDITIONAL INFORMATION  MCGUIRE NUCLEAR STATION, UNITS 1 AND 2  THIRD 10-YEAR INSERVICE INSPECTION INTERVAL  RELIEF REQUEST NO. 13-MN-003  DOCKET NOS. 50-369 AND 50-370 By letter dated February 6, 2014, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14055A402), Duke Energy Carolinas (Duke) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI for the third 10-year Inservice Inspection (ISI) Program for McGuire Nuclear Station, Unit 2 (McGuire 2). In order for the NRC staff to complete its review of the relief request, the following additional information is requested. 1. What is the normal operating temperature and pressure for the subject welds (2ELDHX-HD-FLG & 2RCHPSS-OUT-1). 2. What environmental conditions are the subject welds, (2ELDHX-HD-FLG & 2RCHPSS-OUT-1), exposed to (e.g., system transients, vibration, flow)?  3. Describe the materials of construction for the stainless steel head, weld metal, and carbon steel flange in weld 2ELDHX-HD-FLG. 4. Describe the weld metal used in 2RCHPSS-OUT-1. 5. Has Duke performed a review of applicable operating experience for the subject welds?  If so, did this review identify any industry operating experience of similar system welds developing service induced cracking or failure?}}

Revision as of 06:24, 28 June 2018

2014/06/10 NRR E-mail Capture - Draft RAI for Relief Request 13-MN-003
ML14161A351
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 06/10/2014
From: Ed Miller
Division of Operating Reactor Licensing
To: Vu P T
Duke Energy Corp
References
Download: ML14161A351 (3)


Text

1NRR-PMDAPEm ResourceFrom:Miller, EdSent:Tuesday, June 10, 2014 11:02 AMTo:'Vu, Phong T (Phong.Vu@duke-energy.com)'

Subject:

Draft RAI for Relief Request 13-MN-003Attachments:Draft EPNB RAI.docxPT, The NRC staff's draft RAI for the subject relief request is attached to this e-mail. The draft RAI is not an official NRC staff request and is being provided to you to facilitate a subsequent conference call to determine: 1) If the questions clearly convey the NRC staff information needs; 2) Whether the regulatory basis for the questions is understood; 3) Whether the information is already available in existing, docketed, correspondence; and 4) To determine an appropriate response time-frame. After you've had a chance to review the draft information request, please contact me to schedule the conference call.

Ed Miller (301) 415-2481 Hearing Identifier: NRR_PMDA Email Number: 1352 Mail Envelope Properties (9C2386A0C0BC584684916F7A0482B6CAFD0D8A321D)

Subject:

Draft RAI for Relief Request 13-MN-003 Sent Date: 6/10/2014 11:02:20 AM Received Date: 6/10/2014 11:02:00 AM From: Miller, Ed Created By: Ed.Miller@nrc.gov Recipients: "'Vu, Phong T (Phong.Vu@duke-energy.com)'" <Phong.Vu@duke-energy.com> Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 669 6/10/2014 11:02:00 AM Draft EPNB RAI.docx 27397 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:

DRAFT REQUEST FOR ADDITIONAL INFORMATION MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 THIRD 10-YEAR INSERVICE INSPECTION INTERVAL RELIEF REQUEST NO. 13-MN-003 DOCKET NOS. 50-369 AND 50-370 By letter dated February 6, 2014, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14055A402), Duke Energy Carolinas (Duke) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI for the third 10-year Inservice Inspection (ISI) Program for McGuire Nuclear Station, Unit 2 (McGuire 2). In order for the NRC staff to complete its review of the relief request, the following additional information is requested. 1. What is the normal operating temperature and pressure for the subject welds (2ELDHX-HD-FLG & 2RCHPSS-OUT-1). 2. What environmental conditions are the subject welds, (2ELDHX-HD-FLG & 2RCHPSS-OUT-1), exposed to (e.g., system transients, vibration, flow)? 3. Describe the materials of construction for the stainless steel head, weld metal, and carbon steel flange in weld 2ELDHX-HD-FLG. 4. Describe the weld metal used in 2RCHPSS-OUT-1. 5. Has Duke performed a review of applicable operating experience for the subject welds? If so, did this review identify any industry operating experience of similar system welds developing service induced cracking or failure?