ML120720196
| ML120720196 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 03/12/2012 |
| From: | Balwant Singal Plant Licensing Branch IV |
| To: | Hope T Luminant Generation Co |
| Singal, Balwant, 415-3016, NRR/DORL/LPL4 | |
| References | |
| TAC ME7345 | |
| Download: ML120720196 (2) | |
Text
From:
Singal, Balwant Sent:
Monday, March 12, 2012 10:15 AM To:
'Hope, Timothy' Cc:
'jack.hicks@luminant.com'
Subject:
Request for Additional Information - Comanche Peak Nuclear Power Plant, Unit 2 Steam Generator 180 Day Report - TAC ME7345 Tim:
Luminant Generation Company LLC (Luminant) submitted the Comanche Peak Nuclear Power Plant (CPNPP), Unit 2 steam generator (SG) tube inspection report for the twelfth refueling outage by letter dated October 12, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11306A012). The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information and determined that the following additional information is needed for NRC staff to complete its review.
Request for Additional Information:
- 1. Please clarify the following:
- a. Please clarify if Footnote 1 on Page 6 of the Enclosure should refer to preheater baffle plate D (C3), not C (C3).
- b. Please clarify if Table 2-7 (Page 14) of the Enclosure should refer to tube R8C3 or R8C4, in the object description of object number EC 1-01.
- c. Page 31 of the Enclosure provides Operational Assessment Conclusion in Section 4.4. Please clarify if as part of the operational assessment for the next operating cycle, the calculated accident induced leakage rate from the portion of the tubes below 16.95 inches from the top of the tubesheet for the most limiting accident in the most limiting SG was zero.
- 2. Page 20 of the Enclosure describes Secondary Side Integrity in Section 3.3. Please provide the scope and results of your upper bundle inspection in SG4 (e.g., was any degradation observed of any of the secondary side internals, were the tube support openings clear of deposits, etc)
- 3. Table 3-1 (Page 21) and Table 3-4 (Page 24) of the Enclosure provide Summary of Anti-Vibration Bar (AVB) Wear Indications and Summary of Loose Part Wear Indications.
Please provide the location, orientation (if linear), and measured sizes (if available) of the service induced indications. Your submittal does not contain the information for the wear indications at the AVBs.
The Draft request for additional information (RAI) was transmitted on February 29, 2012.
Clarification to RAI No. 3 was provided to Mr. Jim Barnette on March 1, 2012 and it was agreed that Luminant will provide their response within 30 days from the date of this e-mail. Please treat this e-mail communication as formal transmittal of RAIs.
Thanks.
Balwant K. Singal
Senior Project Manager (Comanche Peak, STP, and Palo Verde)
Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.gov Tel: (301) 415-3016 Fax: (301) 415-1222