ML20246H685

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Proposed Tech Specs 3.4.2,3.4.3 & Table 3.7-5,changing Allowable Min Setpoint Value to -3% for RCS Safety Valves & Plant Sys Turbine Cycle Safety Valves & Allowing More Flexibility During Plant Operation
ML20246H685
Person / Time
Site: Arkansas Nuclear 
Issue date: 08/22/1989
From:
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20246H667 List:
References
NUDOCS 8909010336
Download: ML20246H685 (5)


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REACTOR COOLANT SYSTEM SAFETY VALVES - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.2. A mintmum of one pressurizer code safety valve shall be OPERABLE with a lift setting of 2500 PSIA +1,-3%*.

l APPLICABILITY:

MODES 4 AND 5.

ACTION:

With no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE shutdown cooling loop into operation.

SURVEILLANCE RE0VIREMENTS 4.4.2 No additional Surveillance Requirements other than those required by Specification 4.0.5.

^The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

If found outside of a 11% tolerance band, the setting shall be adjusted to within 11% of the lift setting shown.

ARKANSAS - UNIT 2 3/4 4-3 Amendment No.

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. SAFETY VALVES --0PERATING LIMITING CONDITION FOR OPERATION 13.4~ 3 H All pressurizer code safety-valves shall be' 0PERABLE with,a lift setting 2500 psia +1,-3%*.

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APPLICABILITY:. MODES l', 2 and 3.

ACTION:

a.

.With one pressurizer code safety valve inoperable, either' restore the inoperable valve to OPERABLE status within 15 minutes or be-Tin HOT-SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

The provisio'ns of. Specification 3.0.4 may be suspended for one valve at a time for up to 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> for entry into and during operation in MODE 3 for the purpose of setting.the pressurizer code safety' valves ~under ambient (hot) conditions provided a

' preliminary cold setting was made prior to heatup.

SURVEILLANCE REQUIREMENTS 4.4.3 No~ additional-Surveillance Requirements other than those required by Specification 4.0.5.

"The lift setting pressure shall correspond to ambient' conditions of the valve'at nominal operatingLtemperature and pressure..If found outside of.a-11% tolerance band, the setting shall be adjusted to within 11% of the lift'

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L ARKANSAS - UNIT 2 3/4 4-4 Amendment No. 36 a_____-___--__-__-__

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M4. 7 PLANT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAF6TY CYCLES The OPERABILITY of the main steam line code safety valves ensures that the secondary system pressure will be limited to within 110% of its design pressure of 1000 psig during the most severe anticipated system operational transient. The maximum relieving capacity is associated with a turbine trip from 100% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser).

The specified valve lift settings and relieving capacities are in accordance with the requirements of Section III of the ASME Boiler and Pressure Code, 1971 Edition.

The "as-found" requirements are conservative with respect to Section XI of the ASME Boiler and Pressure Vessel Code, 1986 Editicn, and Addenda through 1987. The total relieving capacity for all valves on all of the steam lines in 14,799,360 lbs/hr which is 118.7 percent of the total secondary steam flow of 12, 463,439 lbs/hr at 100%

4 RATED THERMAL POWER. A minimum of 2 OPERABLE safety valves per steam r

generator ensures that sufficient relieving capacity is available for removing decay heat.

STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERMAL POWER required by the reduced reactor trip settings of the Power Level-High channels.

The reactor' trip setpoint reductions are derived on the following bases:

l For two loop operation 3p = {X) - (Y)(V) x (125)

X For single loop operation (two reactor coolant pumps operating l

in the same loop)

SP = f ) ' (Y)(U) x (**)

X where:

reduced reactor trip setpoint in percent of RATED SP

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THERMAL POWER maximum number of inoperable safety valves per steam V

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l ARKANSAS - UNIT 2 B 3/4 7-1 Amendment No.

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