ML16011A517

NRR E-mail Capture - Millstone Power Station, Unit 3, Reactor Vessel Surveillance Capsule Withdrawal Schedule - Request for Additional Information

ML16011A517
Person / Time
Site:	Millstone
Issue date:	01/11/2016
From:	Richard Guzman Plant Licensing Branch 1
To:	Craft W Dominion Nuclear Connecticut
Guzman R
References
CAC MF6476
Download: ML16011A517 (2)

Text

From: Guzman, Richard Sent: Monday, January 11, 2016 6:00 PM To: 'Wanda D Craft (Generation - 6)'

Subject:

Millstone 3, Reactor Vessel Surveillance Capsule Withdrawal Schedule -

Request for Additional Information

Wanda, The NRC staff has reviewed the information provided in the subject letter dated July 2, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15194A061), and has determined that additional information is needed to complete its review. Shown below is the NRC staffs request for additional information (RAI) questions. The information was discussed with your staff on January 7, 2016. As agreed, please provide your formal response by January 29, 2016. Please contact me if you have any questions.

~~~~~~~~~

Rich Guzman Sr. Project Manager NRR/DORL USNRC 301-415-1030 REQUEST FOR ADDITIONAL INFORMATION PROPOSED CHANGES TO REVISE REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE MILLSTONE POWER STATION, UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC DOCKET NO. 50-423 (CAC NO.: MF6476)

BACKGROUND 10 CFR Part 50, Appendix H requires licensees to maintain reactor vessel material surveillance programs The purpose of these programs is to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region that result from the exposure of these materials to neutron irradiation and the thermal environment. The surveillance capsules are withdrawn periodically and tested in accordance with the approved schedule and the requirements of Appendix H to 10 CFR Part 50.

ISSUE

Appendix H to 10 CFR Part 50 includes the requirement of dosimetry monitoring as part of the reactor vessel material surveillance program. In addition, for the period of extended operation for license renewal, NUREG-1801, Generic Aging Lessons Learned (GALL) Report, Aging Management Program, XIM31 Reactor Vessel Surveillance, states that programs without in-vessel capsules use alternative dosimetry to monitor neutron fluence during the period of extended operation, as part of the aging management program for reactor vessel neutron embrittlement. The submittal states, Concurrent reinsertion of Capsule Y will maintain continuous reactor vessel fluence monitoring as required by 10 CFR 50 Appendix H. Capsule Y was withdrawn after 13.8 effective full power years in October 2005 and placed into storage.

REQUEST Describe the analyses planned for Capsule Y, including a description of how the dosimetry analysis will account for the exposure and decay from the spent fuel pool storage when the withdrawal and testing of Capsule Y is performed.