ML110341664
| ML110341664 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/04/2011 |
| From: | Peter Bamford Plant Licensing Branch 1 |
| To: | Chernoff H Plant Licensing Branch 1 |
| Bamford, Peter J., NRR/DORL 415-2833 | |
| References | |
| TAC ME4808 | |
| Download: ML110341664 (3) | |
Text
February 4, 2011 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, PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING NUMBER OF REQUIRED OPERABLE MAIN STEAM SAFETY VALVES (TAC NO.
ME4808)
The attached draft request for additional information (RAI) was transmitted by electronic transmission on February 3, 2011, to Ms. Wendi Croft, 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 the number of main steam safety valves allowed to be inoperable as a function of power level. The draft RAI is related to the licensees submittal dated September 24, 2010. 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 No. 50-289
Enclosure:
As stated
February 4, 2011 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, PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING NUMBER OF REQUIRED OPERABLE MAIN STEAM SAFETY VALVES (TAC NO.
ME4808)
The attached draft request for additional information (RAI) was transmitted by electronic transmission on February 3, 2011, to Ms. Wendi Croft, 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 the number of main steam safety valves allowed to be inoperable as a function of power level. The draft RAI is related to the licensees submittal dated September 24, 2010. 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 No. 50-289
Enclosure:
As stated DISTRIBUTION:
Public RidsNrrPMThreeMileIsland Resource LPL1-2 R/F Accession No.: ML110341664
- via email OFFICE LPL1-2/PM SRXB/BC NAME PBamford AUlses*
DATE 02/04/2011 01/28/2011 OFFICIAL RECORD COPY
DRAFT Enclosure REQUEST FOR ADDITIONAL INFORMATION THREE MILE ISLAND NUCLEAR STATION, UNIT 1 PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING NUMBER OF REQUIRED OPERABLE MAIN STEAM SAFETY VALVES DOCKET NO. 50-289 By letter dated September 24, 2010 (Agencywide Documents Access and Management System Accession No. ML102780570), Exelon Generation Company, LLC (the licensee), submitted a license amendment request (LAR) for Three Mile Island Nuclear Station, Unit 1 (TMI-1). The licensee proposes to modify TMI-1 Technical Specification 3.4.1.2.3 regarding the number of main steam safety valves allowed to be inoperable as a function of power level. In order for the NRC staff to complete its review of the LAR, a response to the following request for additional information is requested.
- 1. to the submittal, document number 86-9054640-02, page 47, assigns a value of 6.9% full power (FP) uncertainty to the overpower trip setpoint, independent of power level. Please provide justification that this uncertainty is applicable to all of the power levels analyzed.