ML16139A030
| ML16139A030 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 06/10/2016 |
| From: | Pickett D Plant Licensing Branch 1 |
| To: | Entergy Nuclear Operations |
| Pickett D, NRR/DORL/LPL1-1, 415-1364 | |
| References | |
| CAC MF7193, CAC MF7194 | |
| Download: ML16139A030 (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 June 10, 2016
SUBJECT:
INDIAN POINT NUCLEAR GENERATING, UNIT NOS. 2 AND 3-REQUEST FOR ADDITIONAL INFORMATION REGARDING CONDITIONAL EXEMPTION FROM END-OF-LIFE MODERATOR TEMPERATURE COEFFICIENT MEASUREMENT (CAC NOS. MF7193 AND MF7194)
Dear Sir or Madam:
By letter dated December 10, 2015, as supplemented on March 2, 2016, Entergy Nuclear Operations, Inc., the licensee, submitted a license amendment request to modify the near-end of life moderator temperature coefficient (MTC) Technical Specification (TS) Surveillance Requirement 3.1.3.2 and TS 5.6.5 for Indian Point Nuclear Generating Unit Nos. 2 and 3 by placing a set of conditions on reactor core operation which, if met, would allow exemption from the required MTC measurement.
The Nuclear Regulatory Commission staff is reviewing the submittal 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 Nos. 50-247 and 50-286
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 OFFICE OF NUCLEAR REACTOR REGULATION ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NOS 2 AND 3 DOCKET NOS. 50-247 AND 50-286 In the application of December 10, 2015, as supplemented, the licensee stated that a comparison of PARAGON/ANC, without the application of the intermediate NEXUS code, would result in similar calculated values since NEXUS automates multiple PARAGON lattice transport calculations to generate a suite of cross-sections for ANC calculation. Since the licensee is seeking approval for use of the end of life moderator temperature coefficient (EOL MTC)
Exemption Methodology with PARAGON, the Nuclear Regulatory Commission staff is asking the licensee to provide additional justification for this statement by providing the results for PARAGON for the same benchmarking data points provided in the licensee's letter dated December 10, 2015, Attachment 5, Table 1 of the Beaver Valley Power Station request for additional information Question 2.
In lieu of providing additional benchmarking results, a more detailed justification could be provided on how the results of the benchmarking of PHOENIX-P to PARAGON in the NRC approved methodology WCAP-16045 and the results of the benchmarking of PARAGON to NEXUS in the NRC approved methodology WCAP-16045 1-A can be used to support the use of PARAGON for the EOL MTC Exemption Methodology.
Enclosure
ML16139A030 OFFICE DORL/LPL 1-1/PM DORL/LPL 1-1/LA NAME DPickett KGoldstein DATE 5/20/2016 5/19/2016 RidsNrrPMlndianPoint RidsAcrsAcnw_MailCTR GDentel, R1 NDomenico, SRXB DSS/SRXB/BC (A)
DORL/LPL 1-1/BC EOesterle (BMozafari for) TTate 5/25/2016 6/10/2016