ML110760361
| ML110760361 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 03/22/2011 |
| From: | Nicholas Difrancesco Plant Licensing Branch III |
| To: | Pacilio M Exelon Generation Co |
| DiFrancesco N, NRR/DORL/LPL3-2, 415-1115 | |
| References | |
| TAC ME4949 | |
| Download: ML110760361 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 22, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CLINTON POWER STATION, UNIT NO.1 - REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST FOR THE REMOVAL OF DIVISION 3 ALTERNATING CURRENT MODE RESTRICTIONS FOR PERFORMING HIGH PRESSURE CORE SPRAY EMERGENCY DIESEL GENERATOR SURVEILLANCE TESTING (TAC NO. ME4949)
Dear Mr. Pacilio:
By letter to the Nuclear Regulatory Commission (NRC) dated October 28, 2010 (Agencywide Documents and Management System (ADAMS) Accession No. ML103020155), Exelon Generation Company, LLC submitted a request for removal of Division 3 Mode Restrictions for Performing High Pressure Core Spray Emergency Diesel Generator, for Clinton Power Station, Unit No.1.
The NRC staff is reviewing your submittals, and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on March 17, 2011, it was agreed that you would provide a response within 30 days from the date of this letter.
Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, we may reject your request for approval under the provisions of 10 CFR 2.108.
The NRC staff considers that timely responses to requests for additional information help ensure that sufficient time is available for the NRC staff to review and contribute toward the NRC's goal of efficient and effective use of staff resources.
M. J. Pacilio
- 2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3154.
Sincerely,
~
Nicholas J. DiFrancesco, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461 Enclosure Request for Additional Information Cc w/enclosure: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION REGARDING CLINTON POWER STATION. UNIT NO.1 LICENSE AMENDMENT REQUEST FOR THE REMOVAL OF MODE RESTRICTIONS FOR PERFORMING HIGH PRESSURE CORE SPRAY EMERGENCY DIESEL GENERATOR SURVEILLANCE TESTING DOCKET NO. 50-461
- 1.
In Section 2.1, surveillance requirement (SR) 3.8.1.8, of license amendment request (LAR), the licensee states, "Revise Note 2 to remove restriction that prohibits performance of the SR in Modes 1 or 2 for Division 3 AC Sources only." However, the technical specification (TS) markup sheet for SR 3.8.8 attached to the LAR does not show Note 2. Please provide clarification to this discrepancy.
2., page 17 of 25, of the LAR states, "Lastly, the Division 3 power system is an independent electrical distribution system with a dedicated DG. Division 3 loads such as Division 3 Source Range Monitor and Reactor Protection System isolation features are supported by a battery that is designed to carry these loads for four hours; therefore, there is minimal opportunity for the performance of this SR for the Division 3 DG to have any impact on other safety-related plant equipment or normal plant operation. The simulated LOOP signal is generated only at the Division 3 switchgear and does not affect the other two safety-related electrical divisions or their associated loads."
Please explain in detail the "minimal opportunity" which could have impact on other safety-related plant equipment or normal plant operation for the performance of this SR for Division 3 DG.
- 3.
The upper portion of relays DG 1C lAC, DG 1C FCV, and 251-221C1-51 on of the LAR are shown with dotted lines and lower portion with continuous lines. Please provide a detailed discussion on how the upper (dotted) portion of time current plot of relays DG 1 C lAC, DG 1 C FCV, and 251-221 C1 - 5 were determined and confirm that they were concurred by relay manufacturers.
- 4., page 6 of 25, of the LAR, states, "All safety related continuous duty motors have the ability to deliver their rated horsepower continuously without damage when the voltage at the terminals is 10% above or below rated voltage with rated frequency."
Please confirm that when the Division 3 DG (1 C) is allowed to deliver maximum voltage output (4580 Volt (V)) per Clinton's TSs SR 3.8.1.2, all the safety-related continuous duty motors, including motors fed from 4160 V buses, will have the ability to deliver the rated horsepower continuously without damage.
Enclosure
M. J. Pacilio
- 2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3154.
Sincerely, IRA!
Nicholas J. DiFrancesco, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461 Enclosure Request for Additional Information Cc w/enclosure: Distribution via Listserv DISTRIBUTION:
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