ML17353A283

Proposed Tech Specs 4.1.3.1.2,4.6.5.1,4.4.6.2.2,4.10.1.2 & Table 4.3-3 to Reduce Frequency of Testing,Per GL 93-05

ML17353A283
Person / Time
Site:	Turkey Point
Issue date:	07/26/1995
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17353A282	List: ML17353A281 ML17353A283
References
GL-93-05, GL-93-5, NUDOCS 9507310250
Download: ML17353A283 (7)

Text

REACTIVI,TY CONTROL SYSTEMS LIMITI'Nd CONDITION FOR OPERATION (Continued) a) The THERMAL POWER level is reduced to less than or equal to 75K of RATED THERMAL POWER within one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the power range neutron flux high trip setpoint is reduced to less than or equal to 85:o of RATED THERMAL POWER. THERMAL POWER shall be maintained less than or equal to 75ro of RATED THERMAL POWER until compliance with ACTIONS 3. l. 3. 1. c. 3. c and 3. 1. 3. 1. c. 3. d below are demonstrated, and b) The SHUTDOWN MARGIN requirement of Specification 3. 1. 1. 1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and c) A power distribution map is obtained from the movable.incore N

detectors and F~(Z) and F>H are verified to be within their limits within 72 hours. and d) A reevaluation of each accident analysis of Table 3. 1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions.

SURVIELLANCE RE UIREMENTS

4. 1. 3. l. 1 The position of each full length rod shall be determined to be within + 12 steps (Analog Rod Position Indication) of the group step counter demand position at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (allowing for one hour thermal soak after rod motion) except during time invervals when the Rod Position Deviation Monitor i- inoperaoie, then verify the group positions at least once per 4 hours.

4. l. 3. 1. 2 Each full length rod not fully inserted in the core shall be deter-mined to be OPERA8LE by movement of at least 10 steps in any one direction at least once per g days.

95073l0250 950726 PDR ADQCK 05000250 P PDR TURKEY PCINT - UNITS 3 E; 4 3/4 1-18 AMENDMENT NOS. AND

TABLE 4.3-3 RADIATION MONITORING INSTRUHENTATION FOR PLANT ANALOG CHANNEL HODES FOR MICH CHANNEL CHANNEL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION -'EST IS RE UIRED Containment

a. Containment Atmosphere Al 1 Nigh p hOiahav Iyi 1 Leakage Detection y'CS

1) Particulate Radio- 1, 2, 3, 4 activity

2) Gaseous Radioactivity 1, 2, 3, 4

2. Spent Fuel Pool Areas

a. Unit 3 Radioactivity High Gaseous

b. Unit 4 (Plant Vent)

Radioactivity--High Gaseous'SPING and PRHS)

TABLE NOTATIONS

" Mith irradiated fuel in the fuel storage pool ar eas.

O'nit 4 Spent Fuel Pool Area is monitored by Plant Vent radioactivity instrumentation.

REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION Continued

2. The leakage" from the remaining isolation valves in each high pressure line having a valve not meeting the criteria of Table 3.4-1, as listed in Table 3.4-1, shall be determined and recorded daily. The positions of the other valves located in the high pressure line having the leaking valve shall be recorded daily unless they are manual valves located inside containment.

Otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

d. With any Reactor Coolant System Pressure Isolation Valve leakage greater than 5 gpm, reduce leakage to below 5 gpm within I hour, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUT-DOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

.SURVEILLANCE RE UIREMENTS

4. 4. 6. 2. 1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:

a. Monitoring the containment atmosphere gaseous'r particulate radio-activity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. Monitoring the containment sump level at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c. Performance of a Reactor Coolant System water inventory balance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving steady-state operation"" and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during steady-state operation, except that not more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> shall elapse between any two successive inventory balances; and

d. Monitoring the Reactor Head Flange Leakoff System at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4. 4. 6. 2. 2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage" to be within its limit:

a. At least once per 18 months.

b. Prior to entering .MODE 2 whenever the plant has been in COLD SHUTDOWN for 74-hours or more and if leakage testing has not been performed 7 e~ys sn he previous 9 months, and

c. Prior to returning the valve to service following maintenance, repair or replacement work on the valve.

o satisfy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with the leakage criteria.

""RCS average coolant temperature being changed by less than 5'F/hour.

TURKEY POINT - UNITS 3 & 4 3/4 4-20 AMENDMENT NOS. ~7AND 2

CONTAINMENT SYSTEMS 3/4,6,5 COMBUSTIBLE GAS CONTROL HYDROGEN MONITORS LIMITING CONDITION FOR OPERATION 3.6.5 Two independent containment hydrogen monitors shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

a. With one hydrogen monitor inoperable, restore the inoperable monitor to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. With both hydrogen monitors inoperable, restore at least one monitor to OPERABLE status within,72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />'URVEILLANCE RE UIREMENTS

4. 6. 5. 1 Each hydrogen monitor shall be demonstrated OPERABLE by the performance of a CH CK at least once per 12 hours, an ANALOG,'CHANNEL OPERATIONAL EST at least once pe & days, and at least once 668%0 f rming a CHANNEL CALIBRATION using sample gas containing:

$ fu jL]hl(y $ Aif.(jLv+L ne vo me percent hydrogen, balance nitrogen, and

b. Four volume percent hydrogen, balance nitrogen.

4. 6. 5. 2 The flow path to each hydrogen monitor shall be demonstrated OPERABLE at least once per 31 days by a system walkdown to verify that each accessible manual, power operated, or automatic valve is in its correct position and that power is available to those components related to the operability of the flowpath.

TURKEY POINT - UNITS 3 8 4 3/4 6-19 AMENDMENT NOS.~AND &2

3/4.10 SPECIAL TEST E CEPTIONS 3/4. 10: 1 -SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod worth and SHUTDOWN MARGIN provided reactivity equivalent to at least the highest estimated control rod worth is available for trip insertion from OPERABLE control rod(s).

APPLICABILITY: MODE 2.

ACTION:

a. With any full-length control rod not fully inserted and with less than the above reactivity equivalent available for trip insertion, immediately initiate and continue boration at greater than or equal

. to 16 gpm of a solution containing greater than or equal to 3.0 wtX (5245 ppm) boron or its equivalent until the SHUTDOWN MARGIN

. required by Specification 3. 1. 1.1 is restored.

b. With all full-length control rods fully inserted and the reactor sub-critical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 16 gpm of a solution containing greater than or equal to 3.0 wtX (5245 ppm), boron or its equivalent until the SHUTDOWN MARGIN required by. Specifica-tion 3,1.1.1 is restored.

SURVEILLANCE RE UIREMENTS 4.10.1.1 The position of each full-length control rod either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

4. 10. 1.2 Each full-length control rod not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50K withdrawn position within e~ prior to reducing the SHUTDOWN MARGIN to less than the limits of Speci f) cation 3.1.1.1.

7 oh($

TURKEY POINT - UNITS 3 8 4 3/4 10-1 AMENDMENT NOS. +44 AND Hg-