ML061010560

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Issuance of Amendment Deletion of Requirement for Standby Liquid Control System During Refueling - Technical Specification Reactivity Control Systems
ML061010560
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 04/07/2006
From: Stewart Bailey
Plant Licensing Branch III-2
To: Levis W
Public Service Enterprise Group
References
TAC MC8608
Download: ML061010560 (6)
v • d • e


Text

REACTIVITY CONTROL SYSTEMS 3/4.1 5 STANDBY LIOUID CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.1.5 The standby liquid control system consists of two redundant subsystems and shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2 I

ACTION:

a. In OPERATIONAL CONDITION 1 or 2:
1. With one system subsystem inoperable, restore'the subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2. With both system subsystems inoperable, restore at least one subsystem to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.1.5 The standby liquid control system shall be demonstrated OPERABLE:

a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that:
1. The temperature of the sodium pentaborate solution in the storage tank is greater than or equal to 700F.
2. The available volume of sodium pentaborate solution is within the limits of Figure 3.1.5-1.
3. The heat tracing circuit is OPERABLE by determining the temperature of the pump suction piping to be greater than or equal to 70 0 F.

HOPE CREEK 3 /4 1-19 Amendment No. 166

TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION VALVE ACTUA-TION GROUPS MINIMUM APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION SIGNAL Cd) PER TRIP SYSTEM(a) CONDITION ACTION

3. MAIN STEAM LINE ISOLATION
a. Reactor Vessel Water Level - 1 2 1, 2, 3 21 Low Low Low, Level 1
b. Main Steam Line Radiation - 2 (b) 2 1, 2, 3## 28 High, High
c. Main Steam Line Pressure - 1 2 1 22 Low
d. Main Steam Line Flow - High 1 2/line 1, 2, 3 20
e. Condenser Vacuum - Low 1 2 1, 2**, 3** 21
f. Main Steam Line Tunnel 1 2/line 1, 2, 3 21 Temperature - High
g. Manual Initiation 1, 2, 17 .2 1, 2, 3 25
4. REACTOR WATER CLEANUP SYSTEM ISOLATION
a. RWCU A Flow - High 7 1/Valve Ce) 1, 2, 3 23
b. RWCU A Flow - High, Timer 7 1/Valve (e) 1, 2, 3 23
c. RWCU Area Temperature - High 7 6/Valve (e) 1, 2, 3 23
d. RWCU Area Ventilation A Ce) 7 6/Valve 1, 2, 3 23 Temperature-High
e. SLCS Initiation 7 C(f) 1/Valve (e) 1, 2 23 I
f. Reactor Vessel Water 7 2/Valve (e) 1, 2, 3 23 Level - Low Low, Level 2
g. Manual Initiation 7 1/Valve (e) 1, 2, 3 25 HOPE CREEK 3 /4 3 -12 Amendment No. 166

TABLE 3.3.2-1 (Continued)

NOTES

    • When any turbine stop valve is greater than 90% open and/or when the key-locked bypass switch is in the Norm position.

The hydrogen water chemistry (HWC) system shall not be placed in service until reactor power reaches 20% of RATED THERMAL POWER.

After reaching 20% of RATED THERMAL POWER, and prior to operating the HWC system, the normal full power background radiation level and associated trip setpoints may be increased to levels previously measured during full power operation with hydrogen injection. Prior to decreasing below 20% of RATED THERMAL POWER and after the HWC system has been shutoff, the background level and associated setpoint shall be returned to the normal full power values. If a power reduction event occurs so that the reactor power is below 20% of RATED THERMAL POWER without the required setpoint change, control rod motion shall be suspended (except for scram or other emergency actions) until the necessary setpoint adjustment is made.

(a) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Eor required surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

(b) Also trips and isolates the mechanical vacuum pumps.

(c) Also starts the Filtration, Recirculation and Ventilation System (FRVS).

(d) Refer to Table 3.3.2-1 table notation for the listing of which valves in an actuation group are closed by a particular isolation signal.

Refer to Tables 3.6.3-1 and 3.6.5.2-1 for the listings of all valves within an actuation group.

(e) Sensors arranged per valve group, not per trip system.

(f) Closes only RWCU system isolation valve(s) HV-FO01 and HV-F004.

(g) Requires system steam supply pressure-low coincident with drywell pressure-high to close turbine exhaust vacuum breaker valves.

(h) Manual isolation closes HV-F008 only, and only following manual or automatic initiation of the RCIC system.

(i) Manual isolation closes HV-F003 and HV-F042 only, and only following manual or automatic initiation of the HPCI system.

Cj) Trip functions common to RPS instrumentation.

HOPE CREEK 3/4 3-16a Amendment No. 166

TABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED MAIN STEAM LINE ISOLATION (Continued)

e. Condenser Vacuum - Low S Q R 1, 2**, 3**
f. Main Steam Line Tunnel Temperature - High NA Q R 1, 2, 3
g. Manual Initiation NA Q (a) NA 1, 2, 3
4. REACTOR WATER CLEANUP SYSTEM ISOLATION
a. RWCU A Flow - High S Q R 1, 2, 3
b. RWCU A Flow - High, Timer NA Q R 1, 2, 3
c. RWCU Area Temperature - High NA Q R 1, 2, 3
d. RWCU Area Ventilation A Temperature - High NA Q R 1, 2, 3
e. SLCS Initiation NA Q(b) NA 1, 2 I
f. Reactor Vessel Water Level - Low Low, Level 2 S Q R 1, 2, 3
g. Manual Initiation NA Q(a) NA 1, 2, 3
5. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION
a. RCIC Steam Line A Pressure (Flow) - High NA Q R 1, 2, 3
b. RCIC Steam Line A Pressure (Flow) - High, Timer NA Q R 1, 2, 3
c. RCIC Steam Supply Pressure -

Low NA Q R 1, 2, 3

d. RCIC Turbine Exhaust Diaphragm Pressure - High NA Q R 1, 2, 3 HOPE CREEK 3 /4 3-29 Amendment No. 166

TABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION (Continued)

h. HPCI Torus Compartment Temperature - High NA Q R 1, 2, 3
i. Drywell Pressure - High NA Q R 1, 2, 3
j. Manual Initiation NA R NA 1, 2, 3
7. RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION
a. Reactor Vessel Water Level -

Low, Level 3

  • S Q R 1, 2, 3
b. Reactor Vessel (RHR Cut-in Permissive) Pressure - High NA Q R 1, 2, 3 C. Manual Initiation NA Q(a) NA 1, 2, 3
    • When any turbine stop valve is greater than 90% open and/or when the key-locked bypass switch is in the Norm position.

(a) Manual initiation switches shall be tested at least once per 18 months. All other circuitry associated with manual initiation shall receive a CHANNEL FUNCTIONAL TEST at least once per 92 days as part of circuitry required to be tested for automatic system isolation.

(b) Each train or logic channel shall be tested at least every other 92 days.

HOP ,CREEK_.

3 /4 3-31 Amendment No. 166

INSTRUMENTATION BASES 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY (continued)

OPERABLE to ensure that no single instrument failure can preclude the isolation function.

The valve groups actuated by this Function are listed in Table 3.3.2-1.

4.c, 4.d. RWCU Area Temperature and Area Ventilation Differential Temperature

- High RWCU area temperatures and area ventilation differential temperatures are provided to detect a leak from the RWCU System. The isolation occurs even when very small leaks have occurred and is diverse to the high differential flow instrumentation for the hot portions of the RWCU System.

If the small leak continues without isolation, offsite dose limits may be reached. Credit for these instruments is not taken in any transient or accident analysis in the UFSAR, since bounding analyses are performed for large breaks such as recirculation or MSL breaks.

Area temperature and area ventilation differential temperature signals are initiated from temperature elements that are located in the room that is being monitored. Twelve ambient temperature sensor/monitors provide input to the RWCU Area Temperature - High Function. Twelve channels are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function.

Twelve differential temperature sensor/monitors provide input to the RWCU Area Ventilation Differential Temperature - High Function. Twelve channels are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function.

The valve groups actuated by this Function are listed in Table 3.3.2--l.

4.e. SLC System Initiation The isolation of the RWCU System is required when the SLC System has been initiated to prevent dilution and removal of the boron solution by the!

RWCU System. SLC System initiation signals are initiated from the two SLC pump start signals.

"wo channels (one from each pump) of the SLC System Initiation Function are available and are required to be OPERABLE only in OPERATIONAL CONDITIONS 1 and 2 (when the SLC system is required to be OPERABLE), since these OPERATIONAL CONDITIONS are consistent with the Applicability for the SLC System (TS 3.1.5).

4.f. Reactor Vessel Water Level - Low Low, Level 2 Low RPV water level indicates that the capability to cool the fuel may be threatened. Should RPV water level decrease too far, fuel damage could result. Therefore, isolation of some interfaces with the reactor vessel occurs to isolate the potential sources of a break. The isolation of the RWCU System on Level 2 supports actions to ensure that the fuel peak cladding temperature remains below the limits of 10 CFR 50.46. The Reactor Vessel Water Level - Low Low, Level 2 Function associated with RWCU isolation is nDt Hope Creek B 3/4 3-2k Amendment No. 166

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