BW210082, Notification of Deviation from Electric Power Research Institute Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-solable Reactor

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Notification of Deviation from Electric Power Research Institute Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-solable Reactor
ML21349A105
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 12/15/2021
From: Keenan J
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML21349A104 List:
References
BW210082, NEI 03-08
Download: ML21349A105 (2)


Text

Exelon Generation Company, LLC

~+ Exelon Generation Bralctwood Nuclear Power Station 35100 South R.oute 53, Suite 84 Braceville, IL 6040Nl619 www.exe!oncorp,com NEI 03-08 December 15, 2021 BW210082 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 1 Renewed Facility Operating License No. NPF-72 NRG Docket No. STN 50-456

Subject:

Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) 2019-008, "Interim Guidance for NEI 03-08 Needed Requirements for US PWR Plants for Management of Thermal Fatigue in Non-lsolable Reactor Coolant System Branch Lines" In accordance with Appendix B, Section 8.1.c of Nuclear Energy Institute (NEI) 03-08,

. "Guideline for the Management of Materials Issues," Revision 4, Exelon Generation Company, LLC (EGG) is notifying the U.S. Nuclear Regulatory Commission (NRG) that Braidwood Station, Unit 1 has processed a deviation from "Needed" interim guidance (IG)#2 in EPRI Document MRP 2019-008, "Interim Guidance for NEI 03-08 Needed Requirements for US PWR Plants for Management of Thermal Fatigue in Non-lsolable Reactor Coolant System (RCS) Branch Lines,"

with appropriate justification and documentation.

MRP 2019-008 "Needed" requirements IG#2 requires a one-time examination of the Residual Heat Removal (RHR) suction lines that branch off the Reactor Coolant System (RCS) hot legs (1A and 1C) . The one-time examination for the RHR suction line from the 1A RCS hot leg will not be performed by the required time frame of within two refueling outages after August 1, 2019. The examination has been deferred to refueling outage A 1R23 (Fall 2022).

NEI 03-08 allows deviation from "Needed" elements with the appropriate justification and documentation. The deviation has been documented in accordance with EGC's corrective action program and approved by the appropriate levels of EGG management. The Attachment provides the EGG Braidwood Unit 1 technical justification for the deviation from MRP 2019-008.

In accordance with NEI 03-08, this letter is being transmitted for information only. EGG is not requesting any action from the NRG.

December 15, 2021 BW210082 Page2 This letter contains no new regulatory commitments.

If you have any questions concerning this letter, please contact Richard Schliessmann, acting Regulatory Assurance Manager, at (815) 417-2820.

Respectfully, Keenan JQ h n P* DN:cn=Keenan,John Dig. ita. lly signed by Keenan, John P.

P.

1 Date: 2021.12.14 06:21 :39-06'00' John Keenan Site Vice President .

Braidwood Nuclear Generating Station

Attachment:

Braidwood Unit 1 Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273 cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector- Braidwood Station NRC Project Manager - Braidwood Station Illinois Emergency Management Agency- Division of Nuclear Safety