ML15182A231
| ML15182A231 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/01/2015 |
| From: | Richard Guzman Plant Licensing Branch 1 |
| To: | Craft W Dominion Nuclear Connecticut |
| Guzman R | |
| References | |
| TAC MF3402 | |
| Download: ML15182A231 (2) | |
Text
From:
Guzman, Richard Sent:
Wednesday, July 01, 2015 7:37 AM To:
'Wanda D Craft (Generation - 6)'
Subject:
RE: NRC letter of May 29, 2015 MPS2 - Reactor Vessel Internals Aging Management Program and Inspection Plan for License Renewal Commitment No. 13 (Tac. No. MF3402)
- Wanda, I have discussed these apparent inconsistencies and/or errors with the technical staff. We agree that the items identified below are indeed editorial errors in the safety assessment; however, they do not affect the staffs assessment determination or change the stated safety conclusions. Please consider this e-mail as documented acknowledgement from the NRR technical staff of these identified errors in the May 29, 2015, subject safety assessment.
- Thanks, Rich Rich Guzman Sr. Project Manager NRR/DORL US NRC 301-415-1030 From: Wanda D Craft (Generation - 6) [1]
Sent: Monday, June 22, 2015 5:02 PM To: Guzman, Richard
Subject:
[External_Sender] NRC letter of May 29, 2015 MPS2 - Reactor Vessel Internals Aging Management Program and Inspection Plan for License Renewal Commitment No. 13 (Tac. No. MF3402)
- Rich, In review of the subject letter, a few differences were noted between the DNC submittal and the NRC safety assessment letter. The differences are described in the table below:
Safety Assessment Comment Suggested resolution Page 2, para 3, last sentence Reference is made to modification/rework package (MRP)-227-A. The phrase modification/rework package is not the meaning of MRP. The correct meaning of the acronym is Materials Reliability Program.
Delete modification/rework package since the meaning of MRP is already explained prior to this occurrence.
Page 19, Staff Evaluation, first para, 3rd sentence Sentence states The licensee's maximum allowable gap corresponds to a linear growth of 4 percent or a volumetric swelling amount of 12 percent. DNC did not provide these values in its submittals and the analysis described by DNC was not predicated on specific values of void swelling.
Page 22, last para The staff summarizes the DNC submittal for the core support plate flow holes as being (less than 2-inch Correct to less than 2 1/4 inch
except for one 3-inch flow hole per quadrant). The 2-inch value is not correct. Page 6 of the DNC submittal dated July 27, 2014 stated that the flow holes are less than 2 1/4 inch.
If you have any questions, please let me know. Thanks.
Wanda D. Craft Nuclear Licensing and Operations Support Dominion Resources Services, Inc (804) 273-4687 tie-line 730-4687 CONFIDENTIALITY NOTICE: This electronic message contains information which may be legally confidential and or privileged and does not in any case represent a firm ENERGY COMMODITY bid or offer relating thereto which binds the sender without an additional express written confirmation to that effect. The information is intended solely for the individual or entity named above and access by anyone else is unauthorized. If you are not the intended recipient, any disclosure, copying, distribution, or use of the contents of this information is prohibited and may be unlawful. If you have received this electronic transmission in error, please reply immediately to the sender that you have received the message in error, and delete it. Thank you.