ML16357A778
| ML16357A778 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 12/23/2016 |
| From: | Kimberly Green Plant Licensing Branch III |
| To: | Bryan Hanson Exelon Nuclear Generation Corp |
| Green K, NRR/DORL/LPLIII | |
| References | |
| CAC MF8387, CAC MF8388 | |
| Download: ML16357A778 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 December 23, 2016
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - WITHDRAWAL OF REQUESTED LICENSING ACTION TO REVISE TECHNICAL SPECIFICATION 5.5.12 FOR PERMANENT EXTENSION OF TYPE A AND TYPE C LEAK RATE TEST FREQUENCIES SUBMITTED TO NRC FOR ACCEPTANCE REVIEW (CAC NOS. MF8387 AND MF8388)
Dear Mr. Hanson:
By letter dated September 19, 2016, as supplemented by letter dated December 15, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML16263A267 and ML16350A432, respectively), Exelon Generation Company, LLC submitted a license amendment request for Quad Cities Nuclear Power Station, Units 1 and 2.
The proposed amendment request would revise Technical Specification (TS) 5.5.12, "Primary Containment Leakage Rate Testing Program, to allow for the permanent extension of the Type A integrated leak rate testing and Type C leak rate testing frequencies. 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 acceptance 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.
By letter dated December 22, 2016 (ADAMS Accession No. ML16357A541), you requested to withdraw the application from NRC review. The NRC acknowledges your request to withdraw the application. NRC staff activities on the review have ceased, and the associated Cost Activity Code number has been closed.
The NRC staff notes that its review to date has identified that your application did not provide the following technical information in sufficient detail to enable the staff to complete its detailed review. Therefore, if you decide to resubmit the request, it should include the following information:
The results of a peer review of the internal events probabilistic risk assessment (PRA) that was conducted against all the supporting requirements of the PRA Standard ASME/ANS RA-Sa-2009, and Regulatory Guide 1.200, Revision 2, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities" (ADAMS Accession No. ML090410014), that were affected by any PRA upgrades; A list of the facts and observations (F&Os) from this peer review, with details of their disposition; and For any open or unresolved F&Os, justification for why not meeting the corresponding Capability Category I requirements has no impact on the requested licensing action.
If you have any questions, please contact me at (301) 415-1627 or by e-mail to Kimberly.Green@nrc.gov.
Docket Nos. 50-254 and 50-265 cc: Distribution via Listserv
/
Kimberly J. Green, Senior Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML090410014), that were affected by any PRA upgrades; A list of the facts and observations (F&Os) from this peer review, with details of their disposition; and For any open or unresolved F&Os, justification for why not meeting the corresponding Capability Category I requirements has no impact on the requested licensing action.
If you have any questions, please contact me at (301) 415-1627 or by e-mail to Kimberly.Green@nrc.gov.
Docket Nos. 50-254 and 50-265 cc: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLlll R/F RidsACRS_MailCTR Resource RidsNrrDraApla Resource RidsNrrDorllpl3 Resource RidsNrrLASRohrer Resource RidsNrrPMQuadCities Resource RidsRgn3Mai1Center Resource ADAMS Accession No.: ML16357A778 Sincerely,
/RA/ Russell Haskell for Kimberly J. Green, Senior Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- by e-mail dated OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DRA/APLA/BC* NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME RHaskell SRohrer SRosenberg DWrona RHaskell (LRonewicz for)
(CJFong for)
DATE 12/23/16 12/23/16 12/23/16 12/23/16 12/23/16