ML16279A043
| ML16279A043 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 10/06/2016 |
| From: | Kimberly Green Plant Licensing Branch III |
| To: | Hamilton D FirstEnergy Nuclear Operating Co |
| Green K | |
| References | |
| CAC MF7476, L-16-083 | |
| Download: ML16279A043 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. David Hamilton Site Vice President October 6, 2016 FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR UPPER CONTAINMENT POOL GATE INSTALLATION DURING MODES 1, 2, AND 3 AND DRAIN DOWN OF UPPER CONTAINMENT POOL DURING MODE 3 (CAC NO. MF7476) (L-16-083)
Dear Mr. Hamilton:
By application dated March 15, 2016, FirstEnergy Nuclear Operating Company submitted a license amendment request for Perry Nuclear Power Plant, Unit 1 (PNPP). The proposed request would revise PNPP technical specifications to allow the installation of the upper containment pool gate during MODEs 1, 2, and 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 determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. A draft request for additional was transmitted on September 16, 2016. During a discussion with your staff on October 4, 2016, it was agreed that you would provide a response within 30 days from the date of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1627.
Docket No. 50-440 License No. NPF-58
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, KJ~~
Kimberly Green, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
REQUEST FOR ADDITIONAL INFORMATION FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY NUCLEAR POWER PLANT. UNIT NO. 1 DOCKET NO. 50-440 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, and 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 staff's continued technical review of the license amendment request (LAR).
- 1. General Design Criteria (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 LAR do not impact the CSS set points described in Section 6 of the 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 for the steam line break with steam bypass of the suppression pool transient as referenced in the LAR.
Enclosure
ML16279A043 NRR/DORL/LPL3-NRR/DORL/LPL3-OFFICE 2/PM 2/LA NAME KGreen SRohrer DATE 10/5/16 10/5/16 Sincerely,
/RAJ Kimberly Green, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrLASRohrer Resource RidsNrrPMPerry Resource RidsRgn3MailCenter Resource FForsaty, NRR DKi, NRR NRR/DSS/SRXB/B NRR/DORL/LPL3-c 1/BC EOesterle DWrona 09/14/16 10/6/16 NRR/DORL/LPL3-1/PM KGreen 10/6/16