NL-15-1221, Withdrawal of RR-V-2 and Response to Request for Additional Information on RR-V-1

Withdrawal of RR-V-2 and Response to Request for Additional Information on RR-V-1

ML15198A158
Person / Time
Site:	Hatch
Issue date:	07/16/2015
From:	Pierce C Southern Co, Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-15-1221
Download: ML15198A158 (2)

Text

Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.

40 Inverness Center Parkway A

Post Office Box 1295 Birmingham, AL 35201 Tel 205.992.7872 Fax 205.992.7601 SOUTHERN COMPANY July 16, 2016 2015 Docket Nos.: 50-321 NL-15-1221 50-366 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant - Units 1 and 2 Withdrawal of RR-V-2 and Response to Request for Additional Information on RR-V-1 Ladies and Gentlemen:

By letter dated May 4, 2015, Southern Nuclear Operating Company requested approval, pursuant to 10 CFR 50.55(a)(z) and 10 CFR 50.55(a)(f), of several relief requests, two of which were RR-V-1 and RR-V-2, "Scram Discharge AOV Ganged Test Timing", and Traversing In-Core Probe (TIP) Shear Valve Leak Rate Testing", respectively.

On June 29, 2015, a telephone conference was held between NRC and members of SNC staff to discuss these two relief requests.

Based on those discussions, SNC and NRC agreed that sufficient information is contained within the SNC Local Leak Rate Testing (LLRT) Program and procedures to document the requirements and testing of the TIP system explosive actuated shear valves. The In-Service Testing (1ST} program needs to refer to the LLRT program and no relief is required from the Code. Therefore, SNC withdraws RR-V-2.

Regarding RR-V-1, NRC required clarification as to whether the relief request applied to both Units or only to Unit 1. Relief Request RR-V-1 applies only to Unit

1. The Unit 1 Control Rod Drive system timing is adjustable by manipulating needle valves which would also change the stroke times for the applicable Unit 1 valves; therefore, stroke timing the Unit 1 valves would not provide any meaningful information with respect to valve degradation. The Unit 2 system does not contain the needle valves and cannot be adjusted like Unit 1.

Consequently, the Unit 2 valves can be stroke time tested and no relief is needed from the requirements of ROJ-V-29.

U.S. Nuclear Regulatory Commission NL-15-1221 Page2 This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.

Rc.*ttrt.itted.

C. R. Pierce Regulatory Affairs Director CRP/OCV cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, Executive Vice President & Chief Nuclear Officer Mr. D. R. Vineyard, Vice President- Hatch Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. J. Adams, Vice President- Engineering Mr. G. L. Johnson, Regulatory Affairs Manager- Hatch RTYPE: CHA02.004 U.S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Senior Project Manager- Hatch Mr. D. H. Hardage, Senior Resident Inspector- Hatch