ML13086A589

From kanterella
Jump to navigation Jump to search

RAI Related to License Amendment Request to Revise Technical Specifications Section 3.5.3, ECCS (Emergency Core Cooling System) - Shutdown (TAC Nos. ME9134-9135 and ME9136 & ME9137)
ML13086A589
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 03/28/2013
From: Michael Mahoney
Plant Licensing Branch III
To: Pacilio M
Exelon Generation Co
Mahoney M NRR/DORL/LPL3-1 301-415-6606
References
TAC ME9134, TAC ME9135, TAC ME9136, TAC ME9137
Download: ML13086A589 (4)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 28, 2013 Mr. Michael J. Pacilio Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)

Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BYRON STATION, UNIT NOS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS (TS)

SECTION 3.5.3, "ECCS [EMERGENCY CORE COOLING SYSTEM]

SHUTDOWN" (TAC NOS. ME9134, ME9135, ME9136, AND ME9137)

Dear Mr. Pacilio:

By letter to the U.S. Nuclear Regulatory Commission (NRC) dated July 23, 2013, (Agencywide Document Access and Management System (ADAMS) Accession No. ML12206A057), Exelon Generation Company, LLC (the licensee), submitted a license amendment request to revise the technical specifications (TS) of Byron Station; Unit Nos. 1 and 2 and Braidwood Station, Unit 1 and 2.

The proposed amendments would delete the limiting condition for operation (LCO) note associated with TS Section 3.5.3, "ECCS [Emergency Core Cooling System] - Shutdown," to reflect current plant configuration and ensure the Residual Heat Removal system operability meets the TS 3.5.3 LCO requirement.

The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on March 13, 2013, it was agreed that your staff would provide a response within 30 days from the date of this letter.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for NRC staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.

M. Pacilio

- 2 If you have any questions regarding this matter, please contact me at (301 )-415-3867.

7~ ~/..

Michael Mt Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456, and STN 50-457

Enclosure:

Request for additional information cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION BYRON STATION. UNIT NOS 1 AND. 2 BRAIDWOOD STATION. UNITS 1 AND 2 DOCKET NOS. STN 50-454, STN 50-45. STN 50-456. and STN 50-457 By letter to the U.S. Nuclear Regulatory Commission (NRC) dated July 23, 2013, (Agencywide Document Access and Management System (ADAMS) Accession No. ML12206A057). Exelon Generation Company. LLC (the licensee), submitted a license amendment request (LAR) to revise the technical specifications (TS) of Byron Station. Unit Nos. 1 and 2. and Braidwood Station, Unit 1 and 2.

The proposed amendments would delete the Limiting Condition for Operation (LCO) Note associated with TS Section 3.5.3, "ECCS [Emergency Core Cooling System] - Shutdown," to reflect current plant configuration and ensure the Residual Heat Removal system operability meets the TS 3.5.3 LCO requirement.

In Section 4.0, "No Significant Hazards Consideration", in response to question 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?," the licensee states "Since the ECCS and RHR systems are not accident initiators, the proposed changes do not impact the initiators or assumptions of analyzed accidents.... "

The NRC staff requests the following information to complete its review:

1. Provide an explanation of accidents that have occurred that were initiated by operator error such as inappropriate valve manipulations.

ML13086A589

  • Memo Dated March 1 2013 OFFICE LPL3-2/PM LPL3-2/LA DSS/SRXB/BC LPL3-2/BC MMahoney SRohrer SMiranda*

JBowen MMahoney NAME 03/28/13 03/28113 DATE 03/28/13 03/28/13 03/01/13