Text

NRR E-mail Capture - Followup RAI Regarding Westinghouse Infogram (Ig) 14-1 Relating to Braidwood UHS Amendment
	ML15348A017
Person / Time
Site:	Braidwood
Issue date:	11/30/2015
From:	Joel Wiebe; Plant Licensing Branch III
To:	Krejcirik J; Exelon Corp
References
	Download: ML15348A017 (2)
	v • d • e

NRR-PMDAPEm Resource From: Wiebe, Joel Sent: Monday, November 30, 2015 10:43 AM To: Jessica Krejcie Cc: Joseph Bauer

Subject:

Followup RAI Regarding Westinghouse InfoGram (IG) 14-1 Relating to Braidwood UHS Amendment

Jessica, Let me know if you would like a clarification call regarding this RAI. Also let me know if there is any proprietary information in this RAI.

Joel SCVB-RAI-15 Exelon response to SCVB-RAI-11 in the above reference letter did not provide Braidwood Units 1 and 2 plant specific information regarding the impact of the corrections resulting from Westinghouse InfoGram (IG) 14-1 on the loss-of-coolant accident (LOCA) mass and energy (M&E) release, containment pressure and temperature response, sump net positive suction head (NPSH) analysis, and minimum containment pressure for emergency core cooling system (ECCS) analysis. Exelon response refers to analysis performed for a generic large containment plant which only addresses the impact on the containment peak pressure and temperature.

The response does not provide a comparison of the related parameters of the generic plant with the Braidwood plant.

Without additional quantitative information, the NRC staff evaluation of Braidwood Units 1 and 2 containment performance due to increase in ultimate heat sink (UHS) temperature cannot be completed. After correcting the RCS metal specific heat and density to ASME values reported in IG 14-1, the NRC staff requests the following:

(a) Revise the analyses of record for the above containment analyses, and provide results. As an alternative, by performing Braidwood Units 1 and 2 plant specific sensitivity analysis, provide increase in containment peak pressure, peak temperature, sump water temperature and decrease in the available NPSH for the pumps that draw suction flow from the sump during the LOCA recirculation phase..

(b) Revised Technical Specification (TS) values of Integrated Leak Rate Test (ILRT) pressure Pa. In case Pa increases from its current TS value, provide an evaluation of the impact on the current ILRT and Local Leak Rate Test (LLRT) results.

(c) Impact on the residual heat removal (RHR) heat exchanger heat load and on the discharge temperature of the closed cooling water (CC) from the RHR heat exchanger.

(d) Impact on the reactor containment fan cooler (RCFC) heat load and on the exit temperature of the essential service water (SX) from the RCFC.

(e) Overall impact on the temperature of SX exiting the CC heat exchanger.

(f) Overall impact on the temperature of SX returning to the UHS.

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Hearing Identifier: NRR_PMDA Email Number: 2549 Mail Envelope Properties (f4fe93e55f9e49cab744ac92c088ec57)

Subject:

Followup RAI Regarding Westinghouse InfoGram (IG) 14-1 Relating to Braidwood UHS Amendment Sent Date: 11/30/2015 10:42:32 AM Received Date: 11/30/2015 10:42:00 AM From: Wiebe, Joel Created By: Joel.Wiebe@nrc.gov Recipients:

"Joseph Bauer" <Joseph.Bauer@exeloncorp.com>

Tracking Status: None "Jessica Krejcie" <Jessica.Krejcie@exeloncorp.com>

Tracking Status: None Post Office: HQPWMSMRS07.nrc.gov Files Size Date & Time MESSAGE 2370 11/30/2015 10:42:00 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received: