ML092120612
| ML092120612 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/04/2009 |
| From: | Peter Bamford Plant Licensing Branch 1 |
| To: | Chernoff H Plant Licensing Branch 1 |
| Bamford, Peter J., NRR/DORL 415-2833 | |
| References | |
| Download: ML092120612 (5) | |
Text
August 4, 2009 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
Peter Bamford, Project Manager /RA/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
THREE MILE ISLAND, UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED TECHNICAL SPECIFICATION CHANGES TO REFLECT CONTROL ROD DRIVE CONTROL SYSTEM REPLACEMENT The attached draft request for additional information (RAI) was transmitted by electronic transmission on August 3, 2009 to Mr. Frank Mascitelli and Mr. David Helker, at Exelon Generation Company, LLC (Exelon, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with Exelon in order to clarify the licensees amendment request regarding technical specification changes to reflect the planned replacement of the Control Rod Drive Control System. The draft RAI is related to the licensees submittal dated September 29, 2008 and supplements dated May 6, 2009 and June 23, 2009. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow Exelon to evaluate and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.
Docket Nos. 50-289
Enclosure:
As stated
August 4, 2009 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
Peter Bamford, Project Manager /RA/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
THREE MILE ISLAND, UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED TECHNICAL SPECIFICATION CHANGES TO REFLECT CONTROL ROD DRIVE CONTROL SYSTEM REPLACEMENT The attached draft request for additional information (RAI) was transmitted by electronic transmission on August 3, 2009 to Mr. Frank Mascitelli and Mr. David Helker, at Exelon Generation Company, LLC (Exelon, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with Exelon in order to clarify the licensees amendment request regarding technical specification changes to reflect the planned replacement of the Control Rod Drive Control System. The draft RAI is related to the licensees submittal dated September 29, 2008 and supplements dated May 6, 2009 and June 23, 2009. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow Exelon to evaluate and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.
Docket Nos. 50-289
Enclosure:
As stated DISTRIBUTION:
Public RidsNrrPMPBamford LPL1-2 R/F Accession No.: ML092120612
- via correspondence OFFICE LPL1-2/PM EICB NAME PBamford WKemper*
DATE 8/3/09 07/31/2009 OFFICIAL RECORD COPY
Enclosure REQUEST FOR ADDITIONAL INFORMATION THREE MILE ISLAND NUCLEAR STATION, UNIT 1 CONTROL ROD DRIVE CONTROL SYSTEM REPLACEMENT AND AXIAL POWER SHAPING ROD REMOVAL DOCKET NO. 50-289 By letter dated September 29, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082800174, AmerGen Energy Company, LLC, the licensee1, submitted a license amendment request (LAR) for Three Mile Island Nuclear Station, Unit 1 (TMI-1). The LAR proposes to modify Technical Specifications (TSs) related to the Control Rod Drive Control System (CRDCS), Reactor Trip Breakers (RTBs) and Axial Power Shaping Rods (ASPRs). These proposed changes reflect a planned CRDCS upgrade to a digitally based system that will result in the replacement of the TMI-1 reactor trip breakers and elimination of the APSRs. On May 6, 2009 (ADAMS Accession No. ML091260765), and June 23, 2009 (ADAMS Accession No. ML091750846), the licensee provided supplemental information.
Included in the May 6, 2009 submittal was new information that the RTBs contain microcontrollers. In order for the NRC staff to complete its review of the LAR, a response to the following request for additional information concerning the microcontrollers is requested.
- 1.
The licensee has stated that the Square D MasterPact NT RTBs contain a firmware microcontroller in the undervoltage and shunt trip devices. What is the full model number of the MasterPact NT breakers that are being used?
- 2.
Have other plants installed this model of Square D MasterPact NT breakers in safety system applications? If so, please provide a list of known users and the associated applications.
- 3.
Provide the common cause analysis and resulting plant coping analysis for the breakers.
- 4.
Is the software in the breakers fully tested or was the software programmed using a high quality process that meets the requirements for development of safety-related software?
- 5.
Is the microcontroller capable of being reprogrammed? How can the program be implemented (i.e., online, offline)?
1 The operating license for TMI-1 has been transferred from AmerGen Energy Company, LLC to Exelon Generation Company, LLC as of January 8, 2009.
- 6.
Is the microcontroller connected or capable of being connected to any other circuit, network, programming device, or other equipment that can have an impact on the programming?
- 7.
Does the microcontroller include a communications interface, such as a Modbus? If so, is it, or will it, be used?
- 8.
Please describe the interfaces between the RTBs and any other devices and address their compliance with Nuclear Energy Institute (NEI) 04-04, Cyber Security Program for Power Reactors.
- 9.
Was the commercial dedication process in accordance with Electric Power Research Institute (EPRI) Topical Report (TR)-106439, Guideline on Evaluation and Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Applications?