ML17286A788

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Proposed Tech Spec 3.4.1.1 Re MCPR Safety Limits
ML17286A788
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 05/20/1991
From:
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17286A787 List:
References
NUDOCS 9105310017
Download: ML17286A788 (2)


Text

3/4.4 REACTOR COOLANT SYSTEM 3/4. 4. 1 RECIRCULATIOH SYSTEM RECIRCULATION LOOPS LIMITING CONOITIOH FOR OPERATION

3. 4. l. 1 Two reactor coolant system recirculation loops shall be in operation.

APPLICABILITY: OPERATIONAL CONDITIONS l~ and 2*.

ACTjON:

a. Mith one reactor coo1ant system recirculation loop not in operation:
1. Verify that the requirements of LCO 3.2.6 and LCO 3.2.8 are met, or comply with the associated ACTION statements
2. Verify that THERMAL POMER/core flow conditions lay outside Region 8 of Figure 3.4.1.1-1.

With THERMAL POWER/core flow conditions which lay in Region 8 of Figure 3. 4. l. 1-1, as soon as practical, but in a11 cases within 15 minutes, initiate action to exit Region 8 by either decreasing THERMAL POWER with control rod insertion or increasing core flow with flow control valve manipulation.

Mithin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> exit Region 8. The starti'ng or shifting of a recirculation pump for the purpose of exiting Region 8 is specifically prohibited.

3. Mithin 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s:

a) Place the recirculation flow control system in the Local Manual (Position Control) mode, and b) Increa q t U RITICAL POWER RATIO (MCPR) Safety Limi y 0.01 to 1.07 per Specification 2.1.2, and, c) Reduce the Maximum Average Planar Linear Heat Generation Rate (tlAPLHGR) for gegegal Electric fuel limit to ~~e-h 1 i 1 p

, and, SPCCISi50 IV 7 HQ COP,k a Pc n~TIQ G S.lMI7 S P &POR 7 d) Reduce the volumetric flow rate of the operating recircula-tion loop to < 41,725"" gpm.

See Special Test Exception 3. 10.4.

~*This value represents the actual volumetric recirculation loop flow which produces 1QOX core flow at 10'HERMAL POMER. This value was determined during the Startup Test Program. 9i05310017 910520 PDR ADOCK 05000397 P PDR MASHIHGTOH NUCLEAR - UNIT 2 3/4 4-1 Amendment Ho. 71

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