ML16104A055
| ML16104A055 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 04/25/2016 |
| From: | Ellen Brown Plant Licensing Branch III |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Brown E, NRR/DORL/LPLIII-2 | |
| References | |
| CAC MF7290 | |
| Download: ML16104A055 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 25, 2016 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CLINTON POWER STATION, UNIT NO. 1 -ACCEPTANCE REVIEW CONCERNING PERMANENT EXTENSION OF TYPE A AND TYPE C LEAK RATE TEST FREQUENCIES (CAC NO. MF7290)(RS-16-015)
Dear Mr. Hanson:
By letter dated Janaury 25, 2016, as supplemented by letter dated March 31, 2016 (Agencywide Document Access and Management System (ADAMS) Accession No. ML 116025A 182 and ML16076A077, respectively), Exelon Generation Company, LLC (EGC, the licensee) submitted a license amendment request for Clinton Power Station (CPS), Unit 1. The proposed amendment revises the technical specifications (TSs) to allow a permanent extension of the Type A intergrated leak rate testing and Type C leak rate testing frequencies. This request also proposes to delete information in TS 5.5.13 regarding a completed requirement to perform Type C testing in 2008. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review.
B. Hanson The NRC staff notes that the findings and observations response provided in the March 31, 2016, supplement indicate that an industry-Human Reliability Analysis (HRA) calculator is now used to quantify the human error probabilities. The NRC staff notes that this change in the HRA method may constitute a probabilistic risk assessment model upgrade and, therefore, may need a focused-scope peer review and appropriate resolution of the resulting findings, consistent with the approved risk guidance and staff endorsed industry standards.
You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. If you have any questions, please contact Ms.
Eva Brown, at (301) 415-2315.
Sincerely, Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461 cc: Distribution via Listserv
B. Hanson The NRC staff notes that the findings and observations response provided in the March 31, 2016, supplement indicate that an industry-Human Reliability Analysis (HRA) calculator is now used to quantify the human error probabilities. The NRC staff notes that this change in the HRA method may constitute a probabilistic risk assessment model upgrade and, therefore, may need a focused-scope peer review and appropriate resolution of the resulting findings, consistent with the approved risk guidance and staff endorsed industry standards.
You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. If you have any questions, please contact Ms.
Eva Brown, at (301) 415-2315.
Sincerely, IRA/
Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461 cc: Distribution via Listserv DISTRIBUTION:
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NAME EBrown SRorher SRosenberg JPoole DATE 4/14/16 4/13/16 4/14/16 4/25/16 OFFICIAL RECORD COPY