ML17289A475

Proposed Tech Spec 3/4.4.6 Re Pressure/Temp Limits

ML17289A475
Person / Time
Site:	Columbia
Issue date:	04/10/1992
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17289A472	List: ML17289A471 ML17289A475
References
NUDOCS 9204200102
Download: ML17289A475 (7)

Text

The following pages will be affected by this Technical Specification amendment.

REMOVE INSERT XX1V Xx) V 3/4 4-19 3/4 4-19 3/4 4-22 02 920410 PDR ADOCK 0 5000S97 P

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INDEX LIST OF TABLES (Continued)

TABLE PAGE 4.4. 6. l. 3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM-"

WITHDRAWAL SCHEDULE ..............................

3. 6. 3-1 PRIMARY CONTAINMENT ISOLATION VALVES.............. 3/4 6-21

3. 6. 5. 2-1 SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION VALVES. 3/4 6-39 3.7.8-1 AREA TEMPERATURE MONITORING ..... 3/4 7-31

'.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE ................... 3/4 8-9

4. 8. 2. 1-1 BATTERY SURVEILLANCE RE(UIREMENTS .. 3/4 8-14

3. 8.4. 2-1 PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES ................... 3/4 8-23 3.8.4.3-1 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION ............;.......................... 3/4 8-26 B3/4.4.6-1 REACTOR VESSEL TOUGHNESS ................ B 3/4 4-6

5. 7. 1-1 COMPONENT CYCLIC OR TRANSIENT LIMITS ............. 5-7

6. 2. 2-1 MINIMUM SHIFT CREW COMPOSITION "

SINGLE UNIT FACILITY ...... ~... 6-6 WASHINGTON NUCLEAR - UNIT 2 XX1 V Amendment No. 87. 98

REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS (Continued) 4.4.6. 1.2 The reactor coolant system temperature and pressure shall be deter-mined to be to the right of the criticality limit line of Figure 3.4.6. 1 curve C within 15 minutes prior to the withdrawal of control rods to bring the reactor to criticality and at least once per 30 minutes during system heatup.

4 .4.6. 1.3 The reactor vessel material surveillance specimens shall be removed and examined, to determine changes in reactor pressure vessel material properties as required by 10 CFR Part 50, Appendix H in accordance with the schedule.+a=Pat~

Th i f h i t.i h 11 b d Pd th curves of Figure 3. 4. 6. 1.

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4.4. 6.1.4 The reactor vessel flange and head flange temperature shall be verified to be greater than or equal to 80'F:

a. In OPERATIONAL CONDITION 4 when reactor coolant system temperature is:

1. < 100'F, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

2. < 90'F, at least once per 30 minutes.

b. Within 30 minutes prior to and at least once per 30 minutes during tensioning of the reactor vessel head bolting studs.

WASHINGTON NUCLEAR - UNIT 2 3/4 4"19 Amendment No. 87

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