ML17108A456
| ML17108A456 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point |
| Issue date: | 05/26/2017 |
| From: | Marshall M Plant Licensing Branch 1 |
| To: | |
| Marshall M, NRR/DORL/LPL1, 415-2871 | |
| References | |
| CAC MC3272, CAC MC3273 | |
| Download: ML17108A456 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 25, 2017 MEMORANDUM TO:
File
~~
FROM:
Michael L. Marshall, Jr., Senior Project Manager Y 7
Plant Licensing Branch 1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
CLARIFICATION RE LICENSE RENEWAL SAFETY EVALUATION REPORT FOR NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 (CAC NOS. MC3272 AND MC3273)
The U.S. Nuclear Regulatory Commission (NRC) published NUREG-1900, "Safety Evaluation Report Related to the License Renewal of Nine Mile Point Nuclear Station, Units 1 and 2" (Agencywide Documents Access and Management System Accession Nos. ML062890129 and ML062890236), in September 2006. The safety evaluation report contains apparent discrepancies in the NRC staff's description of site dewatering system and the use of porous concrete at Nine Mile Point Nuclear Station (Nine Mile Point), Unit 2.
Pages 3-98, 3-485, and 3-491 of the safety evaluation report contain statements that are inconsistent with the license renewal application, as amended, and the Nine Mile Point, Unit 2, Updated Safety Analysis Report (USAR). Specifically, the NRC staff states that porous concrete was not used and that there is no site dewatering system at Nine Mile Point, which is inconsistent with the Nine Mile Point, Unit 2, USAR. In USAR Section 2.5.4.5.2.2, the licensee clearly states:
Lean and porous concrete was used beneath and around seismic Category 1 structures[... ] Porous concrete was used under the reactor building mat as part of the dewatering system.
With regard to porous concrete, the licensee clearly states in USAR Section 3.4.1.2:
Although no permanent Category 1 dewatering system is used in the Unit 2 design, a nonsafety-related dewatering system is provided for the reactor building and vicinity area to control the groundwater drainage around the reactor building.
Notwithstanding the apparent discrepancies in the safety evaluation report, the relevant aging effects associated with porous concrete were dispositioned appropriately by the NRC staff (see pages 3-474 and 3-476 of NUREG-1900). The Structures Monitoring Program at Nine Mile Point, Unit 2, is credited for monitoring concrete components for potential age-related degradation. Because the relevant aging effects were appropriately dispositioned, the apparent discrepancies discussed above do not impact the conclusions documented in the safety evaluation report.
Docket Nos. 50-220 and 50-410 cc: Distribution via Listserv
SUBJECT:
CLARIFICATION TO LICENSE RENEWAL SAFETY EVALUATION REPORT FOR NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 (CAC NOS. MC3272 AND MC3273), DATED MAY 25, 2017.
DISTRIBUTION:
Public LPL 1 R/F RidsNrrDorlLpl 1 RidsRgn1 MailCenter RidsACRS_MailCTR RidsNrrLALRonewicz RidsNrrPMNineMilePoint RidsNrrDlrRasb KKolaczyk, R-1 GThomas, NRR APrinaris, NRR ADAMS A ccess1on N b
ML17108A456 um er:
OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DLR/RASB/BC*
NAME MMarshall LRonewicz BWittick DATE 04/24/2017 04/18/2017 03/10/2017
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- 1 iy e-ma1 DORL/LPL 1/BC DORL/LPL 1/PM JDanna MMarshall 05/25/2017 05/26/2017 OFFICIAL RECORD COPY