ML16168A261

Supplement No. 2 to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Rev. 3)....

ML16168A261
Person / Time
Site:	Ginna
Issue date:	06/16/2016
From:	David Gudger Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML16168A261 (5)

Text

{{#Wiki_filter:Exelon Generation 200 Exelon Way Kennett Square, PA 19348 www.exeloncorp.com 10 CFR 50.90 June 16, 2016 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555 R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket No. 50-244

Subject:

Supplement No. 2 to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) Supplemental Information Regarding TSTF-425 License Amendment Request

References:

1. Letter from James Barstow (Exelon) to U.S. Nuclear Regulatory Commission, dated June 4, 2015, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3).

2. Letter from James Barstow (Exelon) to U.S. Nuclear Regulatory Commission, dated October 2, 2015, "Supplemental Information Regarding TSTF-425 License Amendment Request."

On June 4, 2015, Exelon submitted a license amendment request(Reference 1)forthe Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of Technical Specification Task Force-425, Revision 3). (TSTF-425) On October 2, 2015, Exelon submitted a Supplement to Reference 1 to incorporate into the Surveillance Frequency Control Program (SFCP) newly approved Surveillance Requirements (SRs) by the issuance of Amendment 118 (Adoption of TSTF-523 - Gas Accumulation). While preparing camera ready pages tor the issuance of TSTF-425, Exelon identified two inadvertent omissions in the revised marked-up pages included in Reference 2. Specifically, SR 3.5.2.1 on page 3.5.2-2, the 12 hours frequency should have been crossed out and the INSERT 1 box added as it was marked in the original submittal. Similarly, SR 3.6.6.11 on page 3.6.6-3, the INSERT 1 box should have been added as it was included in the original submittal. Attachment 1 contains the corrected pages.

Supplement No. 2 to License Amendment Request Adoption of TSTF-425, Rev. 3 June 16, 2016 Page2 Exelon has reviewed the information supporting a finding of No Significant Hazards consideration provided to the NRC in Reference 1. The additional information provided in this letter does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. Furthermore, the additional information provided in this letter does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment. No regulatory commitments are contained in this letter. If you should have any questions regarding this submittal, please contact Enrique Villar at 610-765-5736. I declare under penalty of perjury that the foregoing is true and correct. Executed on the 161h day of June 2016. Respectfully, David T. Gudger Manager - Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments: 1. Corrected Technical Specifications Pages cc: USNRC Region I Regional Administrator w/attachments USNRC Senior Resident Inspector - Ginna USNRC Project Manager, NRA - Ginna A. L. Peterson, NYSERDA

ATTACHMENT 1 Supplement No. 2 to License Amendment Request R.E. Ginna Nuclear Power Plant Docket No. 50-244 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) Corrected Technical Specifications Pages

ECCS - MODES 1, 2, and 3 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify the following valves are in the listed position. 12 hours Number 825A Position Open Function RWST Suction to SI Pumps

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8258 Open RWST Suction to SI Pumps 826A Closed BAST Suction to SI Pumps 826B Closed BAST Suction to SI Pumps 826C Closed BAST Suction to SI Pumps 8260 Closed BAST Suction to SI Pumps 851A Open Sump 8 to RHR Pumps 8518 Open Sump B to RHR Pumps 856 Open RWST Suction to RHR Pumps 878A Closed SI Injection to RCS Hot Leg 8788 Open SI Injection to RCS Cold Leg 878C Closed SI Injection to RCS Hot Leg 8780 Open SI Injection to RCS Cold Leg 896A Open RWST Suction to SI and Containment Spray 8968 Open RWST Suction to SI and Containment Spray SR 3.5.2.2 -----------------NOTE-----------------------  ::!"' ..J ., _ Not required to be met for system vent flow paths opened under administrative control. INSERT 1 Verify each ECCS manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position. R.E. Ginna Nuclear Power Plant 3.5.2-2 Amendment :1.18

CS, CRFC, and NaOH Systems 3.6.6 SURVEILLANCE FREQUENCY 24~ SR 3.6 .6.10 Verify each automatic CS valve in the flow path that is not locked, sealed, or otherwise secured in position actuates to the correct position on an actual or simulated actuation signal. INSERT 1 I SR 3.6.6.11 Verify each CS pump starts automatically on an actual 24 ffieAtAs or simulated actuation signal.

                                                                                   ~INSERT11 SR 3.6 .6.12       Verify each CRFC unit starts automatically on an 24fflO~

actual or simulated actuation signal. INSERT 1 I SR 3.6.6.13 Verify each automatic NaOH System valve in the flow 24 ffieAtAS

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path that is not locked, sealed, or otherwise secured in position actuates to the correct position on an actual or simulated actuation signal. SR 3.6 .6.14 Verify spray additive flow through each eductor path. ~z--~ SR 3.6.6 .15 Verify each spray nozzle is unobstructed. Following --ilNSERT 1 I maintenance which could result in nozzle blockage SR 3.6.6.16 Verify CS locations susceptible to gas accumulation ,, ...,*-

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are sufficiently filled with water. --{INSERT 1 I R. E. Ginn a Nuclear Power Plant 3.6.6-3 Amendment 1.18}}