ML15086A189

Technical Requirements Manual/Trm Revision 128/Trm344

ML15086A189
Person / Time
Site:	Waterford
Issue date:	03/10/2015
From:	Entergy Operations
To:	Office of Nuclear Reactor Regulation
Shared Package
ML15086A176	List: ML15086A157 ML15086A181 ML15086A182 ML15086A183 ML15086A186 ML15086A187 ML15086A188 ML15086A189 ML15086A203 ML15086A204 ML15086A205 ML15086A206 ML15086A208 ML15086A209 ML15086A210 ML15086A211 W3F1-2015-0023, Technical Requirements Manual/Trm Revision 128/Trm3412
References
W3F1-2015-0023
Download: ML15086A189 (7)

Text

3/4 4-1 AMENDMENT NO. 99, 109, 126(DRN 04-1244, Am. 99)3/4.4 REACTOR COOLANT SYSTEM 3/4.4.3 PRESSURIZER HEATERS LIMITING CONDITION FOR OPERATION (DRN 06-1065, Am. 109)3.4.3.1 The pressurizer heaters shall be OPERABLE with at least 300 kW of nominal heater capacity available in addition to the heater capacity specified in Technical Specification 3.4.3.1b. (DRN 06-1065, Am. 109)APPLICABILITY: MODE 1 ACTION: With less than the above heater capacity available, restore the required capacity within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or initiate a Condition Report which requires the performance of an evaluation justifying

continued plant operation. The evaluation should be completed within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and should be approved by the General Manager Plant Operations (GMPO) or his designee (e.g.,

the duty plant manager). SURVEILLANCE REQUIREMENTS (LBDCR 13-011, Am. 126) 4.4.3.1 The specified heater capacity shall be verified at least once each refueling interval.(DRN 04-1244, Am. 99; LBDCR 13-011, Am. 126

)

(DRN 07-201, Am. 112) 3/4 4-2 AMENDMENT NO. 112 (DRN 07-201, Am. 112)

(DRN 07-201, Am. 112)

REACTOR COOLANT SYSTEM 3/4.4.5 LEAKAGE DETECTION INSTRUMENTATION

LIMITING CONDITION FOR OPERATION_____________________________

3.4.5.1 The following Reactor Coolant System leakage detection system shall be OPERABLE.

a. Either the condensate flow switches on the required operable Containment Fan Coolers or a containment atmosphere gaseous radioactivity monitoring system.

APPLICABILITY: MODES 1, 2, 3, AND 4.

ACTION: a. With the above required leakage detection system not OPERABLE for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, initiate a Condition Report within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. This Condition Report requires within the following 30 days, evaluation of the condition and generation of a plan for restoring the equipment to operable status.

b. The provisions or TRM LCO 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS___________________________________

4.4.5.1 The leakage detections system shall be demonstrated OPERABLE by:

a. Containment atmosphere gaseous monitoring system-performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Containment atmosphere gaseous monitoring system-performance of CHANNEL FUNCTIONAL TEST at least once per quarter. Containment atmosphere gaseous monitoring system-performance CHANNEL CALIBRATION TEST at least once per 18 months.

b. Containment Fan Cooler condensate flow switches - performance of a CHANNEL FUNCTIONAL TEST at least once per 18 months. (DRN 07-201, Am. 112)

(LBDCR 13-003, Am. 124) 3/4 4-2(a) AMENDMENT NO. 124(LBDCR 13-003, Am. 124)(LBDCR 13-003, Am. 124)REACTOR COOLANT SYSTEM 3/4.4.6 CHEMISTRY LIMITING CONDITION FOR OPERATION 3.4.6 The Reactor Coolant System chemistry shall be maintained within the limits specified in Table 3.4-2. APPLICABILITY: At all times. ACTION: MODES 1, 2, 3, and 4: a. With any one or more chemistry parameter in excess of its Steady State Limit but within its Transient Limit, restore the parameter to within its Steady State Limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 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 /> 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 />. b. With any one or more chemistry parameter in excess of its Transient Limit, be in at least HOT STANDBY within 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 />.

At All Other Times: With the concentration of either chloride or fluoride in the Reactor Coolant System in excess of its Steady State Limit for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or in excess of its Transient Limit, reduce the pressurizer pressure to less than or equal to 500 psia, if applicable, and perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operation prior to increasing the pressurizer pressure above 500 psia or prior to proceeding to MODE 4. SURVEILLANCE REQUIREMENTS 4.4.6 The Reactor Coolant System chemistry shall be determined to be within the limits by analysis of those parameters at the frequencies specified in Table 4.4-3. (LBDCR 13-003, Am. 124)

(LBDCR 13-003, Am. 124) 3/4 4-2(b) AMENDMENT NO. 124(LBDCR 13-003, Am. 124)(LBDCR 13-003, Am. 124)

TABLE 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY STEADY STATE TRANSIENT PARAMETER LIMIT LIMIT DISSOLVED OXYGEN* < 0.10 ppm < 1.00 ppm CHLORIDE < 0.15 ppm < 1.50 ppm FLUORIDE < 0.10 ppm < 1.00 ppm

____________________________*Limit not applicable with Tavg less than or equal to 250°F. (LBDCR 13-003, Am. 124)

(LBDCR 13-003, Am. 124) 3/4 4-2(c) AMENDMENT NO. 124(LBDCR 13-003, Am. 124)(LBDCR 13-003, Am. 124)

TABLE 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS SAMPLE AND PARAMETER ANALYSIS FREQUENCY DISSOLVED OXYGEN* At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> CHLORIDE At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> FLUORIDE At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

_____________________________________

• Not required with Tavg less than or equal to 250°F (LBDCR 13-003, Am. 124)

(DRN 04-1236, Am. 92,07-201, Am. 112

) 3/4 4-3 AMENDMENT NO. 92

, 99, 110, 112 (DRN 04-1236, Am. 92,07-201, Am. 112

) (DRN 04-1236, Am. 92)

REACTOR COOLANT SYSTEM PRESSURIZER HEATUP/COOLDOWN

LIMITING CONDITION FOR OPERATION

3.4.8.2 The pressurizer shall be limited to:

(DRN 06-1000, Am. 110)

a. A maximum heatup rate of 200°F per hour, b. A maximum cooldown rate of 200°F per hour, (DRN 06-1000, Am. 110)

APPLICABILITY: At all times.

ACTION: With any of the pressurizer limits in excess of any of the above limits, restore the affected parameter to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-

limit condition on the structural integrity of the pressurizer; and enter TRM

LCO 3.0.3.

SURVEILLANCE REQUIREMENTS 4.4.8.2.1 The pressurizer temperatures shall be determined to be within the limits at least once per 30 minutes during system heatup or cooldown.

(DRN 04-1236, Am. 92)

(DRN 04-1244, Am. 99,07-201, Am. 112 )

3/4 4-4 AMENDMENT NO. 99

, 112(DRN 04-1244, Am. 99,07-201, Am. 112)

(DRN 03-1808, Am. 80)

REACTOR COOLANT SYSTEM

3/4.4.9 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION

3.4.9 The structural integrity of ASME Code Class 1, 2, and 3 components shall be maintained.

APPLICABILITY

All MODES.

ACTION: a. With the structural integrity of any ASME Code Class 1 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) prior to increasing the Reactor Coolant System temperature more than 70F above the minimum temperature required by NDT considerations. b. With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200F, except during hydrostatic testing of components that are nonisolable from the Reactor Coolant System, then restore the structural integrity prior to increasing the Reactor Coolant System temperature more than 30F above the minimum temperature required by NDT considerations. c. With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component from

service. (DRN 04-1191, Am. 91)

d. The provisions of TRM LCO 3.0.4 are not applicable. (DRN 03-1808, Am. 80; 04-1191, Am. 91)