ML18102A738

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Proposed Tech Specs,Revising Eighteen Month Surveillance Performed to Measure RCS Total Flow Rate to Account for Necessary Plant Conditions for Performing Test in Mode 1 & Current Extended Plant Outages
ML18102A738
Person / Time
Site: Salem  PSEG icon.png
Issue date: 01/07/1997
From:
Public Service Enterprise Group
To:
Shared Package
ML18102A737 List:
References
NUDOCS 9701100263
Download: ML18102A738 (3)


Text

. .. . .. *. *.*= POWER DISTRIBUTION LIMITS DNB PARAMETERS " LIMIT I NG CONDI TI ON 3.2.5 The following Drm related parameters shall be maintained within the limits shown on Table 3.2-1: a. b. c. Reactor Coolant System Tavg* Pressurizer Pressure Coolant System Total Flow Rate APPLICABILITY:

MODE l ACTION: With any of the above parameters exceeding its limit, restore the eter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than S' of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. SURVEILLANCE REQUIREMENTS 4.2.5. l Each of the parameters of Table 3.2-1 shall be verified to within their limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. 4.2.5.2 The Reactor System total flow rate shall be detennintd to be within . *_.*the limits of Table 3.2-1 by performing-a precision heat balance within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after achieving steady state conditions RATED THERMAL POWER at least once per 18 months. The provisions of Specification 4.0.4 are not applicable.

SAlEJ1 -UNIT 1 3/4 2-13 9701100263 970107 PDR ADOCK 05000272 p PDR PARAMETER Reactor Coolant System Tavg Pressurizer Pressure Reactor Coolant System -. -. -. -.

  • 4 Loops In Operation ss2°F 2220 psia* 357,200 gpm/I *Limit not applicable during either THERMAL POWER ramp increase in excess of 5% RATED THERMAL POWER per minute or a THERMAL POWER increase in excess of 10% RATED THERMAL POWER. #Includes a 2.2% flow measurement uncertainty plus a 0.1% measurement uncertainty due to feedwater venturi fouling. SALEM -UNIT l 3/4 2-14 Amendment No.96 i \ ..
        • . .

LIMITS LIMITING FOR OPERATION 3.2.5 The following DNB related parameters shall be maintained within the limits shown 3.2-1: a. Reactor System T

  • avg b. Pressurizer.Pressure.
c. Reactor Coolant System Total Flow Rate. -APPLICABILI'I"i:

MODE 1 ACTION: With any of the above parameters exceeding its limit, restore the parameter to within its "limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

REQUIREMENTS 4.2.5.l Each of the parameters of Table 3.2-1 shall be verified to be within their limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. 4.2.5.2 The Reactor Coolant System Total Flow Rate shall be determined to be within its limit b' at least onee per 18 months. the limits of Table 3.2-1 by performing a

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after achieving steady state RATED THERMAL POWER at least once p7r 18 months. T e provisi of specification 4.0.4 are not applicable.

Amendment No. 72 SAL.EM -UNIT 2 3/4 2-16