LIC-02-0087, Information Re Fort Calhoun Station Unit No. 1 (FCS) Technical Specifications (TS) with Respect to Maximum Safety Injection Tank (SIT) Nitrogen Cover Gas Pressure

Information Re Fort Calhoun Station Unit No. 1 (FCS) Technical Specifications (TS) with Respect to Maximum Safety Injection Tank (SIT) Nitrogen Cover Gas Pressure

ML022540582
Person / Time
Site:	Fort Calhoun
Issue date:	08/23/2002
From:	Ridenoure R Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-02-0087
Download: ML022540582 (2)

Text

uIII w m Omaha Pubfic Power Oistnct 444 South 16th Street Mall Omaha NE 68102-2247 August 23, 2002 LIC-02-0087 U. S. Nuclear Regulatory Commission ATTN.: Document Control Desk Washington, DC 20555

References:

1. Docket No. 50-285

SUBJECT:

Fort Calhoun Station Unit No. 1 Technical Specifications with respect to Maximum Safety Injection Tank Cover Gas Pressure In response to telecons with the NRC staff dated July 24, 2002 and August 13, 2002, Omaha Public Power District (OPPD) is providing information concerning the Fort Calhoun Station Unit No. 1 (FCS) Technical Specifications (TS) with respect to maximum Safety Injection Tank (SIT) nitrogen cover gas pressure.

Conversations with OPPD's fuel vendor (Framatome ANP) indicated that a maximum value for SIT nitrogen cover gas pressure is an input to the Large Break Loss-of-Coolant Accident (LBLOCA) analysis for FCS. The NRC approved RELAP4 LBLOCA methodology uses either an average value from measured SIT nitrogen cover gas pressure data or the average between the minimum and maximum TS SIT nitrogen cover gas pressure values. The LBLOCA analysis for FCS uses the average value from measured SIT nitrogen cover gas pressure data. Therefore, maximum SIT nitrogen cover gas pressure meets Criterion 2 of 10 CFR 50.36(c)(2)(ii) for incorporation into the FCS TS. OPPD will submit a License Amendment Request incorporating an upper limit for SIT nitrogen cover gas pressure into the FCS TS by January 31, 2003.

The design pressure of the SITs is 275 psig at 200'F. SIT pressure is administratively controlled by plant operating procedures to Ž_240 psig and _*270 psig. SIT pressure is verified by plant surveillance procedures to be within this band each shift per procedure OP-ST-SHIFT-001, "Operations Technical Specification Required Shift Surveillance." Additionally, a high-pressure alarm for the SITs is provided at 265 psig.

The SIT relief valves are J. E. Lonergan Company Model LCT-20/S4 valves. They are spring loaded, enclosed-bonnet relief valves with an 0-ring seat and a nominal one-inch inlet. The base, bonnet, disc, guide and most other component parts are made of stainless steel.

The SIT relief valves are nominally set at 275 psig. The SIT relief valves are subject to surveillance testing per Technical Specification 3.3(1)a. The acceptance range for as-found PoDI Employment with Equal Opportunity 4171

U. S. Nuclear Regulatory Commission LIC-2-0087 Page 2 testing of the SIT relief valves is 267 to 283 psig or +3%/-3%. This corresponds to the generic ASME Section XI/OM-1 acceptance criteria for safety/relief valve testing.

This letter contains the following commitment:

• Submit License Amendment Request adding an upper limit for SIT nitrogen gas cover pressure by January 31, 2003.

If you have additional questions, or require further information, please contact Dr. R. L. Jaworski at (402) 533-6833.

-Sincerely, -- . ... .

Division anag - Nuclear Operations RTRT F*/trb c: E. W. Merschoff, NRC Regional Administrator, Region IV A. B. Wang, NRC Project Manager John G. Kramer, NRC Senior Resident Inspector Winston & Strawn