ML16271A302

NRR E-mail Capture - Draft RAI for Perry LAR Regarding Installation of Ucp Gate and Ucp Drain Down (MF7476)

ML16271A302
Person / Time
Site:	Perry
Issue date:	09/16/2016
From:	Kimberly Green Plant Licensing Branch III
To:	Lashley P FirstEnergy Nuclear Operating Co
References
MF7476
Download: ML16271A302 (3)

Text

NRR-PMDAPEm Resource From: Green, Kimberly Sent: Friday, September 16, 2016 3:29 PM To: Lashley, Phil H. (phlashley@firstenergycorp.com)

Subject:

Draft RAI for Perry LAR Regarding Installation of UCP Gate and UCP Drain Down (MF7476)

Attachments: Draft RAI from SRXB.docx

Dear Mr. Lashley:

By letter dated March 15, 2016, FirstEnergy Nuclear Operating Company submitted an amendment request for Perry Nuclear Power Plant, Unit 1 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML16075A411). The proposed amendment would modify technical specifications to permit the installation of the upper containment pool gate in MODES 1, 2, or 3, and the drain-down of the reactor well portion of the upper containment pool during MODE 3.

The U.S Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has identified areas where additional information is needed to complete its review. Attached, please find a draft request for additional information (RAI).

The draft RAI is being sent to ensure that the questions are understandable and the regulatory basis for the questions is clear. This email and the attachment do not convey or represent an NRC staff position regarding the FENOC's request.

Please let me know if you need a call to clarify the staffs request.

Sincerely, Kimberly Green (301) 415-1627 kimberly.green@nrc.gov 1

Hearing Identifier: NRR_PMDA Email Number: 3084 Mail Envelope Properties (Kimberly.Green@nrc.gov20160916152900)

Subject:

Draft RAI for Perry LAR Regarding Installation of UCP Gate and UCP Drain Down (MF7476)

Sent Date: 9/16/2016 3:29:21 PM Received Date: 9/16/2016 3:29:00 PM From: Green, Kimberly Created By: Kimberly.Green@nrc.gov Recipients:

"Lashley, Phil H. (phlashley@firstenergycorp.com)" <phlashley@firstenergycorp.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 1149 9/16/2016 3:29:00 PM Draft RAI from SRXB.docx 36778 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

DRAFT REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST UPPER CONTAINMENT POOL GATE INSTALLATION AND DRAIN DOWN PERRY NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-440 (CAC MF7476)

By letter dated March 15, 2016, FirstEnergy Nuclear Operating Company submitted an amendment request for Perry Nuclear Power Plant, Unit 1 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16075A411). The proposed amendment would modify technical specifications to permit the installation of the upper containment pool gate in MODES 1, 2, or 3, and the drain-down of the reactor well portion of the upper containment pool during MODE 3.

The additional information listed below is needed to support NRC staffs continued technical review of the amendment request.

1. GDC 16 requires that the reactor containment and associated systems shall be provided to establish an essentially leak-tight barrier against the uncontrolled release of radioactivity to the environment and to assure that the containment design conditions important to safety are not exceeded for as long as postulated accident conditions require. Describe the containment spray system (CSS) actuation timing and summary of inputs used in calculating CSS set point. Confirm that the GOTHIC analyses performed in support of this license amendment request (LAR) do not impact the CSS set points described in Section 6 of PNPP Updated Safety Analysis Report.

2. GDC 50 requires that the reactor containment structure, including access openings, penetrations, and the containment heat removal system shall be designed so that the containment structure and its internal compartments can accommodate, without exceeding the design leakage rate and with sufficient margin, the calculated pressure and temperature conditions resulting from any loss-of-coolant accident. Describe the conservatisms used in the assumptions and the benchmarking performed for the GOTHIC model specific to this LAR.