ML17087A203

NRR E-mail Capture - Comanche Peak, Unit 2 - Final Request for Additional Information Regarding Request No. 2B3-1

ML17087A203
Person / Time
Site:	Comanche Peak
Issue date:	03/28/2017
From:	Watford M Plant Licensing Branch IV
To:	Hope T Luminant Generation Co
References
MF9282
Download: ML17087A203 (3)

Text

NRR-PMDAPEm Resource From: Watford, Margaret Sent: Tuesday, March 28, 2017 10:19 AM To: Hope, Timothy Cc: Hicks, Jack

Subject:

Comanche Peak, Unit 2 - FINAL Request for Additional Information Regarding Request No. 2B3-1 (CAC No. MF9282)

Attachments: Comanche Peak, Unit 2 - Request for Additional Information Regarding Request for Alternative (CAC No. MF9282).pdf Good afternoon Mr. Hope, By letter dated February 14, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17054C361), TEX Operations Company LLC (TEX OpCo, the licensee) requested relief from the volumetric inspection coverage of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-729-1 (N-729-1), "Alternative Examination Requirements for PWR [Pressurized-Water Reactor] Reactor Vessel Upper Heads with Nozzles Having Pressure Retaining Partial-Penetration WeldsSection XI, Division 1," as conditioned in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a, for the examination of five control rod drive mechanism penetration nozzles on the reactor vessel closure head at the Comanche Peak Nuclear Power Plant, Unit 2.

On March 27, 2017, the U.S. Nuclear Regulatory Commission (NRC) sent TEX OpCo the draft Request for Additional Information (RAI) provided in the attached document. TEX OpCo subsequently informed the NRC staff that the information requested by the NRC staff was understood and no additional clarification on of the RAI was necessary. Mr. Hicks agreed to provide a response to this final RAI by March 31, 2017. The NRC staff also informed the licensee that a publicly available version of this final RAI would be placed in the NRCs Agencywide Documents Access and Management System.

Thank you, Maggie Watford Project Manager, Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Phone: 301-415-1233 Email: Margaret.Watford@nrc.gov 1

Hearing Identifier: NRR_PMDA Email Number: 3418 Mail Envelope Properties (Margaret.Watford@nrc.gov20170328101900)

Subject:

Comanche Peak, Unit 2 - FINAL Request for Additional Information Regarding Request No. 2B3-1 (CAC No. MF9282)

Sent Date: 3/28/2017 10:19:04 AM Received Date: 3/28/2017 10:19:00 AM From: Watford, Margaret Created By: Margaret.Watford@nrc.gov Recipients:

"Hicks, Jack" <Jack.Hicks@luminant.com>

Tracking Status: None "Hope, Timothy" <Timothy.Hope@luminant.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 1709 3/28/2017 10:19:00 AM Comanche Peak, Unit 2 - Request for Additional Information Regarding Request for Alternative (CAC No.

MF9282).pdf 93955 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST NUMBER 2B3-1 EXAMINATION OF REACTOR VESSEL CLOSURE HEAD PENETRATION NOZZLES TEX OPERATIONS COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT UNIT 2 DOCKET NO. 50-446 By letter dated February 14, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17054C361), TEX Operations Company LLC (the licensee) requested relief from the volumetric inspection coverage of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-729-1 (N-729-1), "Alternative Examination Requirements for PWR [Pressurized-Water Reactor] Reactor Vessel Upper Heads with Nozzles Having Pressure-Retaining Partial-Penetration WeldsSection XI, Division 1," as conditioned in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a, for the examination of five control rod drive mechanism penetration nozzles on the reactor vessel closure head at the Comanche Peak Nuclear Power Plant, Unit 2.

The NRC staff has reviewed and evaluated the information provided by the licensee and has determined that the following information is needed in order to complete its review of the request for alternative.

1) The current proposed alternative is submitted under 10 CFR 50.55a(z)(1). However, the licensee has provided sufficient basis to demonstrate a hardship. This basis cannot be considered unless the licensee submits this proposed alternative under 10 CFR 50.55a(z)(2). In order to complete the review by evaluating the hardship identified by the licensee, the NRC requests the licensee change the applicable regulation under which this proposed alternative is submitted. Performing this change will not slow down or impede the NRC staff review.

ENCLOSURE