ML092310031
| ML092310031 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/19/2009 |
| From: | Lyon C Plant Licensing Branch IV |
| To: | Minahan S Nebraska Public Power District (NPPD) |
| Lyon C Fred, NRR/DORL/LPL4, 301-415-2296 | |
| References | |
| TAC MD9921 | |
| Download: ML092310031 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 19, 2009 Mr. Stewart B. Minahan Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321 SUB~IECT:
COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION RE: ALTERNATIVE SOURCE TERM (TAC NO. MD9921)
Dear Mr. Minahan:
By application dated October 13, 2008, to the U.S. Nuclear Regulatory Commission (NRC)
(Agencywide Documents Access and Management System (ADAMS) Accession No. ML082910760), Nebraska Public Power District (NPPD, the licensee) requested NRC staff approval of an amendment to the Cooper Nuclear Station facility operating license and technical specifications to adopt the Alternative Source Term for use in calculating the loss-of-coolant accident dose consequences.
The NRC staff reviewed the information provided in your application and determined that additional information is required in order to complete its review. The enclosed questions were provided to Mr. D. Van Der Kamp of your staff on August 18, 2009. Please provide a response to the enclosed questions within 30 days of 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 NRC staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2296.
Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION ALTERNATIVE SOURCE TERM COOPER NUCLEAR STATION DOCKET NO. 50-298 Electrical
- 1.
Provide the loading sequence for each emergency diesel generator (EDG) at Cooper Nuclear Station (CNS). In your response, describe the changes that have been made to the EDG loading sequence to support the license amendment request (LAR) for CNS dated October 13, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082910760).
- 2.
Describe how the loads being added to the CNS EDGs (i.e., standby liquid control system (SLC) components) affect the capability and capacity of the EDGs (e.g., describe the impact of the proposed change on the EDG ratings).
- 3.
In response to question 1 in attachment 2 of the LAR, the licensee stated that SLC is a non-safety-related system. Given that the SLC is a non-safety-related system, describe how this system will be electrically separated from the safety-related system (i.e.,
provide a detailed discussion on how a fault on the non-Class 1E electrical circuit will not propagate to the Class 1E electrical circuit). Also, describe the independence (e.g.,
electrical and physical separation) and redundancy of these systems.
- 4.
Describe how the SLC meets the single failure criterion.
- 5.
Describe how the operators will be notified in the event that the SLC would become inoperable (e.g., control room annuciators).
- 6.
Provide a list and description of components being added to your Title 10 of the Code of Federal Regulations Section 50.49 (10 CFR 50.49) program due to this LAR. Confirm that these components are qualified for the environmental conditions they are expected to be exposed to.
- 7.
In response to question 1.5 in attachment 2 of the LAR, the licensee stated that the components exposed to a harsh environment have been evaluated as either qualified or identical to qualified equipment. The licensee should confirm that the identical components added to the environmental qualification (EQ) list due to this LAR were maintained as EQ components or provide the attributes, the detailed evaluation, and the documentation to upgrade these components to meet the requirements of 10 CFR 50.49.
Enclosure
- memo dated OFFICE NRR/LPL4/PM NRR/LPL4/LA DE/EEEB/BC NRR/LPL4/BC NRR/LPL4/PM NAME FLyon JBurkhardt GWilson*
MMarkley MThadani for FLyon DATE 8/19/09 8/19/09 8/18/09 8/19/09 8/19/09