ML17360A055

NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 7 to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program (CAC Nos. MF8844, MF8845; EPID No. L-2016-LLA-0015)

ML17360A055
Person / Time
Site:	Farley
Issue date:	12/20/2017
From:	Shawn Williams Plant Licensing Branch II
To:	Mcelroy G Southern Nuclear Operating Co
References
L-2016-LLA-0015, MF8844, MF8845
Download: ML17360A055 (3)

Text

NRR-DMPSPEm Resource From: Williams, Shawn Sent: Wednesday, December 20, 2017 12:20 PM To: 'gkmcelro@southernco.com' Cc: Jackson, Nicole D.

Subject:

Joseph M. Farley Nuclear Plant, Units 1 and 2 - Supplemental RAI request No. 7 to License Amendment Request to revise TS 5.5.17 "Containment Leakage Rate Testing Program." (CAC Nos. MF8844, MF8845; EPID No. L-2016-LLA-0015)

Dear Mr. McElroy,

By letter dated November 15, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16320A540), as supplemented by letters dated June 22, 2017 (ADAMS Accession No. ML17173A652), September 11, 2017 (ADAMS Accession No. ML17255A159), and October 12, 2017 (ADAMS Accession No. ML17285B308), the Southern Nuclear Operating Company, Inc., (SNC) submitted an amendment request to revise the Joseph M. Farley Nuclear Plant, Unit 1 and Unit 2, Technical Specifications, related to a request to revise TS 5.5.17 "Containment Leakage Rate Testing Program."

NRC Staff has determined that additional information is needed related to SNCs response to RAI No. 7 in the October 12, 2017, supplement. This information was discussed with you on December 19 and December 20, 2017.

Supplement to RAI No. 7 The final CDF and LERF risk values provided in SNCs October 12, 2017, supplement, in response to RAI No. 7, included credit for the Westinghouse Generation III Reactor Coolant Pump (RCP) seals.

Please confirm that the revised values followed the August 23, 2017, Topical Report [TR] PWROG-14001-P, Revision 1, PRA Model for the Generation III Westinghouse Shutdown Seal and the associated NRC Safety Evaluation including the Limitations and Conditions (ADAMS Package Accession No. ML17200A116). If the Limitations and Conditions in the TR were not followed completely, please identify the exceptions and perform a sensitivity analysis to demonstrate quantitatively that the revised Integrated Leak Rate Test (IRLT) risk metrics remain bounded by the values from the October 12, 2017, supplement, i.e., they do not exceed the previous values.

Or 1

Propose a licensee condition that would specify compliance with the TR PWROG-14001-P, Revision 1, the NRC Safety Evaluation, and associated Limitations and Conditions. The license condition must include a requirement that the final values for the ILRT risk metrics submitted in the October 12, 2017, supplement, be recalculated and fully compliant with the TR PWROG-14001-P, Revision 1, associated Safety Evaluation and verified to not exceed the ILRT risk metrics submitted in the October 12, 2017, RAI response, prior to extending ILRT from 10 to 15 years.

Sincerely, Shawn Williams 301-415-1009 2

Hearing Identifier: NRR_DMPS Email Number: 71 Mail Envelope Properties (CY4PR09MB2232A160D9171B469D106CA7900C0)

Subject:

Joseph M. Farley Nuclear Plant, Units 1 and 2 - Supplemental RAI request No.

7 to License Amendment Request to revise TS 5.5.17 "Containment Leakage Rate Testing Program."

(CAC Nos. MF8844, MF8845; EPID No. L-2016-LLA-0015)

Sent Date: 12/20/2017 12:19:50 PM Received Date: 12/20/2017 12:19:51 PM From: Williams, Shawn Created By: Shawn.Williams@nrc.gov Recipients:

"Jackson, Nicole D." <NDJACKSO@southernco.com>

Tracking Status: None

"'gkmcelro@southernco.com'" <gkmcelro@southernco.com>

Tracking Status: None Post Office: CY4PR09MB2232.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 2380 12/20/2017 12:19:51 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

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