ML18338A235

R. E. Ginna Nuclear Power Plant - Relief Request ISI-18 to Extend the Reactor Pressure Vessel Inservice Inspection Interval

ML18338A235
Person / Time
Site:	Ginna
Issue date:	12/04/2018
From:	Jim Barstow Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML18338A235 (4)

Text

Exelon Generation ~) 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp com 10 CFR 50.55a December 4, 2018 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 R. E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRG Docket No. 50-244

Subject:

Relief Request ISl-18 to Extend the Reactor Pressure Vessel lnservice Inspection Interval

References:

1) Letter from J. Barstow (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission), "Relief Request ISl-18 to Extend the Reactor Pressure Vessel lnservice Inspection Interval,"

dated August 1, 2018

2)

• Email from V. Sreenivas (U.S. Nuclear Regulatory Commission) to T. Loomis (Exelon Generation Company, LLC), "Relief Request ISl-18 Requesting to Extend the Fifth lnservice Inspection Program Interval from 1O Years to 20 Years for B-A and B-D Welds - EPID:

L-2018-LLR-0104," dated November 19, 2018 In the Reference 1 letter, Exelon Generation Company, LLC (Exelon) requested your review and approval of Relief Request ISl-18 associated with the lnservice Inspection (ISi) Program for the R. E. Ginna Nuclear Power Plant (Ginna). Specifically, this relief request is associated with extending the reactor pressure vessel ISi interval.

In the Reference 2 email, the U.S. Nuclear Regulatory Commission Staff requested additional information. Attached is our response.

There are no commitments contained in this letter.

Should you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510.

James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC

U.S. Nuclear Regulatory Commission Relief Request ISl-18 to Extend the Reactor Pressure Vessel lnservice Inspection Interval December 4, 2018 Page2

Attachment:

Response to Request for Additional Information - Relief Request ISl-18 cc: USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, Ginna USNRC Senior Project Manager, Ginna A. L. Peterson, NYSERDA

Attachment Response to Request for Additional Information - Relief Request ISl-18

Response to Request for Additional Information Relief Request ISl-18 Page 1 of 1 Question 1:

(1) Confirm whether, by 2019, Exelon has completed 100% of the volumetric examination of the affected Category 8-A and 8-D welds, as required by ASME Code, IW8-2412, "Inspection Program 8," for the fourth ISi interval, which was approved by the NRC to extend to 20-years.

Response

The R. E. Ginna Nuclear Power Plant (Ginna) has completed 100% of the volumetric examination of the affected Category 8-A and 8-D welds, as required by ASME Code, IW8-2412, "Inspection Program 8," for the fourth lnservice Inspection interval. The fourth interval lnservice Inspection Program for Category 8-A and Category 8-D examinations were performed during the 2011 refueling outage.

Question 2:

(2) Confirm whether Exelon has performed any inspection of the affected Category 8-A and 8-D welds in the fifth 10-year ISi interval. Please note that examinations performed to satisfy the ASME Code requirements for the fourth 20-year ISi interval cannot be recounted as examinations related to the fifth 10-year ISi interval.

Response

Ginna has not performed or credited any Category 8-A and Category 8-D examinations to the current fifth Interval lnservice Inspection Program.

Question 3:

(3) The SE for WCAP-16168-NP-A, Revision 3 requires the licensees seeking second or additional interval extensions provide the information and analyses requested in Section (e) of 10 CFR 50.61a. Since the relief request stated that no indications were identified in the RPV beltline during the last ISi, only a certain part of Section (e) applies, i.e., the ultrasonic results must be obtained using procedures, equipment and personnel that have been qualified under the ASME Code,Section XI, Supplement 4 and Supplement 6, as specified in 10 CFR 50.55a(b)(2)(xv). Please provide information demonstrating that the last ISi data were obtained in accordance with the above requirement.

Response

A review was performed of the NDE reports generated for the Ginna 2011 refueling outage. All automated examinations (implementation of Appendix VIII) were conducted using procedures, equipment and personnel that have been qualified in accordance with the ASME Code,Section XI, 1995 Edition with 1996 Addenda, Supplement 4 and Supplement 6, as modified by 10 CFR 50.55a(b)(2)(xiv, xv, and xvi).