ML020880520

Bases Revision Technical Specifications 2.2, Safety Limit - Reactor Coolant System Pressure.

ML020880520
Person / Time
Site:	Kewaunee
Issue date:	03/19/2002
From:	Webb T Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-02-025
Download: ML020880520 (2)

Text

Kewaunee Nuclear Power Plant Point Beach Nuclear Plant N490 Highway 42 6610 Nuclear Road Kewaunee, WI 54216-9511 Two Rivers, WI 54241 920.388.2560 920.755.2321 Committed to Nuclear ence Kewaunee / Point Beach Nuclear Operated by Nuclear Management Company, LLC NRC-02-025 March 19, 2002 10 CFR 50.36 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Ladies/Gentlemen:

Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant Bases Revision(s) to the Kewaunee Nuclear Power Plant Technical Specifications Nuclear Management Company (NMC), licensee for the Kewaunee Nuclear Power Plant (KNPP),

hereby submits a revision to the Bases for the Technical Specifications (TS) 2.2, "Safety Limit Reactor Coolant System Pressure." The change to the TS 2.2 bases removed nominal values from the bases, which were for information only and have led to confusion about the actual setpoint.

Additional changes were also made for uniformity throughout the TS.

These changes have been screened for evaluation pursuant to the requirements of 10 CFR 50.59 in accordance with approved KNPP procedures and were determined to be acceptable.

Attached is a copy of the revised TS Bases page(s) for your controlled TS.

Sincerely, Tom Webb Regulatory Affairs Manager GOR/sc Attachments - TS 2.2 Basis cc - NRC Regional Administrator NRC Resident Inspector NRC Project Manager PSCW

BASIS - Safety Limit - Reactor Coolant System Pressure (TS 2.2)

The Reactor Coolant System(') serves as a barrier preventing radionuclides contained in the reactor coolant from reaching the atmosphere. In the event of a fuel cladding failure, the Reactor Coolant System is the primary barrier against the release of fission products. By establishing a system pressure limit, the continued integrity of the Reactor Coolant System is ensured. The maximum transient pressure allowable in the reactor pressure vessel under the ASME Code,Section III, is 110% of design pressure. The maximum transient pressure allowable in the Reactor Coolant System piping, valves and fittings under USASI B.31.1.0 is 120% of design pressure. Thus, the SAFETY LIMIT of 2735 psig (110% of design pressure, 2485 psig) has been established.(2 )

The settings of the power-operated relief valves, the reactor high pressure trip and the safety valves have been established to prevent exceeding the SAFETY LIMIT of 2735 psig. The initial hydrostatic test was conducted at 3107 psig to ensure the integrity of the Reactor Coolant System.

(°'USAR Section 4 (2)USAR Section 4.3 TS B2.2-1