ML20058L208
| ML20058L208 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/01/1990 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20058L205 | List: |
| References | |
| ET-90-0121, ET-90-121, NUDOCS 9008070060 | |
| Download: ML20058L208 (2) | |
Text
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Attachment:
to ET 90-0121-Page 1 ofL2
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LIMITI O CONDITIONS FOR OPkRATION AND SURVEILLANCE REQUIREMENTS
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SECTION g
TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION.
3/4 ' 21 VALVES...............................................
4 3/4.4.7.
CHEMISTRY................................................
3/4 4-22 TABLE 3.4-2 REACTOR COOLANT S'.' STEM CHEMISTRY LIMITS...............
3/4 4 23 TABLE 4.4-3 REACTOR C0OLANT SYMEM CHEMISTRY SURVEILLANCE REQUIREMENTS........................................
3/4 4-24 3/4.4.8 SPECIFIC ACTIVITY..........................
3/4 4-25 FIGURE 3.4-1 DOSE EQUIVALENT I-131 REACTOR COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL
-POWER WITH THE REACTOR COOLANT SPECIFIC ACTIVITY >
1 pCi/ GRAM 00$E EQUIVALENT I-131.................
3/4 4-27 TA8LE 4.4-4 REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE ANO ANALYSIS PR0 GRAM....................................
3/4 4 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant Systes...................................
3/4 4-29
-FIGURE 3.4-2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS APPLICA8LE UP TO 46 EFPY...........................
3/4 4-30 FIGURE 3.4-3 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS APPLICABLE UP TO Y...........................
3/4 4-31 TABLE 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - WITH0RAWAL SCHEDULE.......................
3/4 4-32 Pressurizer..............................................
3/4 4-33 overpressure Protection Systees..........................
3/4 4 FIGURE 3.4-4 MAXIMUM A'.LOWE0 PORY SETPOINT FOR THE COLD OVERPRESSURE MITIGATION SYSTEM.....................
3/4 4 3/4.4.10 STRUCTtM A INTEGRITY.....................................
3/4 4-37 3/4.4.11 REACTOR COOLANT SYSTEM VENTS.............................
3/4 4-38 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS.............................................
3/4 5-1 WOLF CREEK - UNIT 1 VIII 9008070060 900801 ADOCK0500g2 DR
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BASES
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PAGE=
REACTOR COOLANT,pYSTEM (Continued) 3/4.4.5 STEAM GENERATORS................................
B 3/4 4-2' 3/4.4.6 REACTOR COO LANT SYSTEM LEAKAGE......................'......
8 3/4 4-4 3/4.4.7 CHEMISTRY.................................................
8 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY.......................................
8 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS................................
B 3/4 4-6 TABLE B 3/4.4-1 REACTOR VESSEL T0VGHNESS..........................
B 3/4'4-10 l
FIGURE B 3/4.4-1. FAST NEUTRON. FLUENCE (E>1MeV) AS A FUNCTION OF dEFFECTIVE FULL 7 F0WER YEARSD_ TUL L E0' ';E 1 SERVICE LIFE. ya........
B 3/4 4-11
= _ = _ - -
FIGURE G
/4.4-2 EFFECT GF FLUENCE AND COPPtk On 5nifi Of niNOT FOR RCACTOR VCSSCL STCCLS CXPOSCC TO IDoa0!^TIOP At 550*c S 3/' '-13 3/4.4.10 STRUCTURAL INTEGRITY.....................................
B.3/4 4-16 j'
3/4.4.11 REACTOR COOLANT SYSTEM VENTS............................
B 3/4 4-16
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3/4.5 EMERGENCY CORE C00LIN'G SYSTEMS l
3/4.5.1 ACCUMULATORS................
B 3/4 b-1 t
3/4.5.2, 3/4,5.3, and 3/4.5.4 ECCS SUBSYSTEMS.....................
B 3/4~5-1 3/4.5.5 REFUELING WATER STORAGE TANK..............................
B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS l
3/4.6.1 PRIMARY CONTAINMENT.......................................
B 3/4 6-1 3/4.6.2-DEPRESSURIZATION AND COOLING SYSTEMS....................
B-3/4 6-3
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3/4.6.3 CONTAINMENT ISOLATION VALVES..............................
B 3/4 6-4 l
l 3/4.6.4 COMBUSTIBLE GAS CONTROL.........
B 3/4 6-4
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