ML16005A629
| ML16005A629 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 01/14/2016 |
| From: | Pickett D Plant Licensing Branch 1 |
| To: | Entergy Nuclear Operations |
| Douglas Pickett, NRR/DORL | |
| References | |
| CAC MF7124, IP2-RR-19 | |
| Download: ML16005A629 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 January 14, 2016
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST IP2-RR-19 (CAC NO. MF7124)
Dear Sir or Madam:
By letter dated November 23, 2015 (Agencywide Documents Access and Management System Accession No. ML15342A027), Entergy Nuclear Operations, Inc., the licensee, submitted relief request IP2-ISl-RR-19 for Indian Point Nuclear Generating Unit No. 2. The application requested relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code specifically related to the system leakage test of ASME Class 1 piping conducted at the end of each inspection interval.
The Nuclear Regulatory Commission staff is reviewing the relief request and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). Based on our discussions we understand that a response to the RAI will be provided within 30 days of the date of this letter.
Please contact me at (301) 415-1364 if you have any questions on this issue.
Docket No. 50-247
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
REQUEST FOR ADDITIONAL INFORMATION ENTERGY NUCLEAR OPERATIONS. INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247
- 1. (a) Are there any portions of the subject piping segments inaccessible for inspection and/or insulated?
(b) For the VT-2 visual examinations, discuss whether the licensee will comply with all the requirements of the ASME Code,Section XI, IWA-5240 (e.g., inaccessible and/or insulated).
- 2. (a) Are there any welded connections (e.g., butt weld and socket weld) in the subject piping segments?
(b) Discuss any plant-specific, fleet, and industry operating experience regarding potential degradation (e.g., fatigue, thermal fatigue, and corrosion) and potential severe loading (e.g., vibration, water hammer, and overloading) of the subject piping and associated welded connections.
- 3. The Nuclear Regulatory Commission (NRC) staff notes that NRC Information Notice 2011-04, "Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized water Reactors," discusses potential stress corrosion cracking (SCC) in stainless steel piping. Discuss any adverse operating experience with respect to sec of the welds in the subject piping segments.
- 4. In an unlikely event of a through-wall flaw and leakage, discuss the consequences and significance of the leak and structural failure of the subject piping and associated welded connections.
- 5. (a) For the segments of piping for which relief is being requested, discuss any previous pressure boundary leakage regardless of how it was identified (e.g., from the ASME Code,Section XI, Table IWB-2500-1, Category B-P pressure testing requirements, boric acid corrosion control program walkdowns, or reactor restart walkdowns).
(b) If leakage occurred in the subject piping, discuss the extent of condition assessment and any compensatory measure(s) taken.
- 6. Given the reduced pressure used for system leakage testing: (a) Discuss any walkdowns (e.g., under Boric Acid Corrosion Control program or normal operator round) performed to monitor and identify leakage; and (b) Discuss reactor coolant system leakage detection system capabilities and any measures taken at the plant to monitor and identify leakage for the subject piping segments and associated welded connections.
Enclosure
January 14, 2016 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST IP2-RR-19 (CAC NO. MF7124)
Dear Sir or Madam:
By letter dated November 23, 2015 (Agencywide Documents Access and Management System Accession No. ML15342A027), Entergy Nuclear Operations, Inc., the licensee, submitted relief request IP2-ISl-RR-19 for Indian Point Nuclear Generating Unit No. 2. The application requested relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code specifically related to the system leakage test of ASME Class 1 piping conducted at the end of each inspection interval.
The Nuclear Regulatory Commission staff is reviewing the relief request and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). Based on our discussions we understand that a response to the RAI will be provided within 30 days of the date of this letter.
Please contact me at (301) 415-1364 if you have any questions on this issue.
Docket No. 50-247
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL 1-1 Reading File RidsNrrDorlDpr RidsNrrDeEpnb RidsNrrDorlLpl 1-1 RidsNrrLAKGoldstein RidsRgn1 MailCenter ARezai, EPNB ADAMS ACCESSION NO ML16005A629 OFFICE LPL 1-1/PM LPL 1-1/LA Sincerely, IRA!
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation EPNB/(A)BC*
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- 1 (ML15364A002) 1yema1 LPL 1-1/BC NAME DPickett KGoldstein JTsao TT ate DATE 01 /17/ 16 01/11/16 12 I 29 /15 01/14/16 OFFICIAL RECORD COPY