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MONTHYEARML16035A0152016-02-0404 February 2016 Application to Revise Technical Specifications to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec. Project stage: Request ML16053A1272016-03-0303 March 2016 Acceptance of Requested Licensing Action Application to Review Technical Specifications to Adopt TSTF-490 Project stage: Acceptance Review ML16075A1192016-03-17017 March 2016 Request for Additional Information Regarding: Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specifications Project stage: RAI ML16180A4482016-06-28028 June 2016 Supplement to Response to Request for Additional Information for the Review of TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec Project stage: Supplement ML16279A3812016-10-0505 October 2016 NRR E-mail Capture - Ginna Nuclear Power Plant - Request for Additional Information Regarding: Deletion of E BAR Definition and Revision to Reactor Coolant System Specific Activity Technical Specifications Project stage: RAI ML16278A0772016-11-0707 November 2016 Request for Additional Information Regarding: Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specifications Project stage: RAI ML16336A0482016-11-30030 November 2016 Response to Request for Additional Information for the Review of TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec. Project stage: Response to RAI ML16358A4242017-02-0909 February 2017 R. E. Ginna Nuclear Power Plant - Issuance of Amendment to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec Project stage: Approval 2016-02-04
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Category:Letter
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 M:u:d1 17I 2016 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear R. E. Ginna Nuclear Power Plant 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
R.E. GINNA NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING: DELETION OF E BAR DEFINITION AND REVISION TO REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY TECHNICAL SPECIFICATIONS (CAC NO. MF7339)
Dear Mr. Hanson:
On February 4, 2016, Exelon Generation Company, LLC submitted an application (Agencywide Documents Access and Management System Accession No. ML16035A015) proposing an amendment for R. E. Ginna Nuclear Power Plant, to replace the current Technical Specifications limit for Reactor Coolant System (RCS) gross specific activity with a new limit for RCS noble gas specific activity.
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). On March 14, 2016, Exelon staff indicated that a response to the RAI would be provided within 30 days of the date of this letter.
Please contact me at (301) 415-3629 if you have any questions on this issue.
Diane Render, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosures:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION REGARDING DELETION OF E BAR DEFINITION AND REVISION TO REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY TECHNICAL SPECIFICATIONS R. E. GINNA NUCLEAR POWER PLANT, LLC EXELON GENERATION COMPANY, LLC DOCKET NOS. 50-244 R. E. GINNA NUCLEAR POWER PLANT In an application dated February 4, 2016 (Agencywide Documents Access and Management System Accession No. ML16035A015), Exelon Generation Company, LLC, (Exelon, the licensee), submitted a proposed amendment to the Technical Specifications (TSs) for R. E.
Ginna Nuclear Power Plant (Ginna), which would replace the current TSs limit for Reactor Coolant System (RCS) gross specific activity with a new limit for RCS noble gas specific activity.
The Nuclear Regulatory Commission staff is reviewing the submittal and has the following question.
The proposed change deletes Condition C of TS 3.4.16 requiring gross specific activity of the coolant less than or equal to 100/E µCi/gm and proposes to replace it with Dose Equivalent Xenon-133 (DEX) not within limits. In the current TS 3.4.16, when the gross specific activity of the coolant is greater than 100/E µCi/gm, the required action is to take immediate action to begin shutdown of the reactor (be in mode 3 with Tavg less than 500 °F) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
[emphasis added]. Ginna proposes 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> [emphasis added] to restore DEX within limits.
Technical Specification Task Force (TSTF)-490, Revision 0 provided the following justification for this change:
The Completion Time for revised TS 3.4.16 Required Action B.1 will require restoration of Dose Equivalent Xe-133 to within limit in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. This is consistent with the Completion Time for current Required Action A.2 for Dose Equivalent 1-131. The Completion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for revised Required Action B.1 is acceptable since it is expected that, ifthere were a noble gas spike, the normal coolant noble gas concentration would be restored within this time period.
Also, there is a low probability of an accident occurring during this time period.
For the following reasons the NRC staff needs additional justification for the proposed change:
While it is a correct statement that the proposed change makes the Completion Times of TS 3.4.16 Required Action A.2 and B.1 in NUREG-1431, "Standard Technical Specifications Enclosure
[STS] Westinghouse Plants," consistent, it is not clear to the NRC staff why the Completion Times should be consistent. The plant Conditions for these Required Actions are different.
Ginna's TS 3.4.16 Required Action A.2 is required when the plant is in a condition analyzed in the design basis accident analyses (reactor coolant dose equivalent 1-131 is between 1 and 60 µCi/gm). The new proposed TS 3.4.16 Required Action 8.1 is required when the plant is in a condition not analyzed [emphasis added] in the design basis accident analyses (DEX is greater than 650 µCi/gm). Typically, the Required Action for a condition not analyzed requires the plant to take immediate actions to begin shutdown of the plant. The proposed change does not take immediate actions to begin shutdown of the plant, but allows 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> before the plant is required to begin shutting down.
Therefore, please provide additional justification for the proposed change to increase the Completion Time of TS 3.4.16 Required Action 8.1 to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and why it is acceptable to be in an unanalyzed condition for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
ML16075A119 OFFICE LPL 1-1/PM LPL 1-1/LA DRA/ARCB LPL 1-1/BC LPL 1-1/PM NAME DRender KGoldstein UShoop TT ate DRender DATE 3/16/16 03/16/16 2/26/2016 3/16/16 3/17/16