ML051600049
| ML051600049 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/09/2005 |
| From: | Chernoff H NRC/NRR/DLPM/LPD3 |
| To: | Koehl D Nuclear Management Co |
| Chernoff, H, NRR/DLPM, 301-415-4018 | |
| References | |
| Download: ML051600049 (4) | |
Text
June 9, 2005 Dennis L. Koehl Site Vice President Point Beach Nuclear Plant Nuclear Management Company, LLC 6590 Nuclear Road Two Rivers, WI 54241
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 & 2 - REQUEST FOR ADDITIONAL INFORMATION RE: TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS SR 3.8.4.6 AND SR 3.8.4.7, DC SOURCES - OPERATING
Dear Mr. Koehl:
By letter to the Nuclear Regulatory Commission (NRC) dated April 8, 2004, you submitted a proposed amendment to the Technical Specifications (TS) for Point Beach Nuclear Plant, Units 1 and 2. The proposed amendment would revise TS Surveillance Requirements (SR) 3.8.4.6 and 3.8.4.7, DC Sources - Operating, changing the values for battery charger amperage, adding a new allowance for the method of verifying battery charger capacity, and removing a restriction on the conduct of a modified performance discharge test.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information is addressed in the enclosure and has been discussed with Mr. Jack Gadzalla of your staff. Mr. Gadzalla has agreed to provide a response to this request for additional information within 45 days from the date of this letter.
If you have any questions, please contact me at (301)415-4018.
Sincerely,
/RA/
Harold K. Chernoff, Sr. Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosure:
Request for Additional Information cc w/encl: See next page
ML051600049 OFFICE PDIII-1/PM PDIII-1/PM PDIII-1/LA PDIII-1/SC NAME SRay HChernoff DClarke LRaghavan DATE 06/09/05 06/09/05 06/09/05 06/09/05
Point Beach Nuclear Plant, Units 1 and 2 cc:
Jonathan Rogoff, Esquire Vice President, Counsel & Secretary Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Mr. F. D. Kuester President & Chief Executive Officer WE Generation 231 West Michigan Street Milwaukee, WI 53201 Regulatory Affairs Manager Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, WI 54228 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241 Mr. Jeffery Kitsembel Electric Division Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 Nuclear Asset Manager Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, WI 53201 John Paul Cowan Executive Vice President & Chief Nuclear Officer Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Douglas E. Cooper Senior Vice President - Group Operations Palisades Nuclear Plant Nuclear Management Company, LLC 27780 Blue Star Memorial Highway Covert, MI 49043 Site Director of Operations Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241
REQUEST FOR ADDITIONAL INFORMATION RELATED TO NUCLEAR MANAGEMENT COMPANY, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 & 2 DOCKET NOS. 50-266 AND 50-301
- 1)
In your November 15, 2004, response to a staff request for additional information (RAI),
you stated that proposed battery charger testing limits provide ample margin between the set capacity of the chargers and the surveillance requirements (SRs) to account for drift in the charger output from the setpoint. You also stated that these setpoints were based on not exceeding the current rating of the 480 VAC charger supply breakers.
(1) Explain how charger output drift is an issue with battery charger testing. (2) With regard to the battery chargers, describe how the functionality of the 480 VAC supply breakers is verified.
- 2)
In your November 15, 2004, response to a staff RAI, you stated:
Upon loss of offsite power, the chargers AC contactors open.
Manual operator action is required to restart the chargers. The system design is such that a coincident safety injection signal would prevent restoration of the battery chargers unless offsite power is restored to the safeguards buses. This is done to minimize the loading on the standby emergency power supply during the period immediately following a safety injection signal during a design basis accident. In this case, restoration of the chargers is completed by operators when adequate power is confirmed to be available.
The TS Bases are being revised to clarify this description. The revised Bases will read, The battery chargers are interlocked such that a loss of offsite power will disconnect the battery chargers from their 480 VAC source. A coincident safety injection signal would prevent restoration of the battery chargers unless offsite power is restored to the safeguard buses.
As stated in the Point Beach Final Safety Analysis Report (FSAR), safety-related batteries D-05, D-06, D-105, and D-106 have been sized to carry their expected shutdown loads following a plant trip/loss-of-coolant accident (LOCA) and loss of offsite power or following a station blackout period for one-hour without battery terminal voltage falling below 105 volts (for battery considerations) and while maintaining voltage at the fed components sufficient for them to operate. Describe when and how the battery chargers would be connected to the emergency diesel generators during/following a plant trip/LOCA given a loss of offsite power event.
- 3)
When was the phrase normal loads added to the Point Beach FSAR? In comparison with the existing wording in Technical Specification SR 3.8.4.6, how is the proposed change conservative?
ENCLOSURE