ML20149C814
| ML20149C814 | |
| Person / Time | |
|---|---|
| Site: | Catawba |
| Issue date: | 01/25/1988 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20149C818 | List: |
| References | |
| NUDOCS 8802090303 | |
| Download: ML20149C814 (2) | |
Text
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- N :l e. INT SYITEMI B'3E5 3/4.6.1.8 ANNULUS VENTILATION SYSTEM The OPERABILITY of the Annulus Ventilation System ensures that during LOCA conditions, containment vessel leakage into the annulus will be filtered through tne HEPA filters and activated carbon adsorber trains prior to discharge to-the l-atmosonere.
Operation of the system with the heaters operating to maintain low humidity using autonatic_ control for at least 10 continuous hours in a 31-day period.is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
This requirement is necessary to meet the assumptions used in the safety f
analyses and limit the SITE BOUNDARY radiation doses to within the dose guide-line values of 10 CFR Part 100 during LOCA conditions.
ANSI N510-1980 will be
{
used as a procedural guide for r,urveillance testing.
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3/4.6.1.9 CONTAINMENT PURGE SYSTEMS t
The containment purge. supply and exhaust isolation valves for the lower f
compartment and the upper compartment (24-inch), and instrument room (12-inch),
l and the Hydrogen Purge System (4-inch) are required-to be sealed closed during plant operation since:these valves have not been demonstrated capable of closing during a LOCA. -Maintaining these valves sealed closed during plant operations I
ensures that excessive quar.tities of radioactive materials.will not be released I
via the Containment Purge System. To provide assurance that these containment valves cannot be inadvertently opened, the valves are sealed closed in accord-ance with Standard Review Plan 6.2.4 which includes mechanical devices to seal or lock the valve closed, or prevents power froa being supplied to the valve operator.
l The use of the containment purge lines is restricted to the 4-inch Con-tainment Air Release and Addition System valves since, unlih the lower compart-l l
ment and the upper compartment, instrument room, and the Hydrogen Purge Sys;em I
valves, these 4-inch valves are capable of closing during a LOCA.
Therefore.
the SITE BOUNDARY dose guideline values of 10 CFR Part~100,would not be exceeded in the event of an accident during containment purging operation.
Operation with the line open will be limited to 3000 hours0.0347 days <br />0.833 hours <br />0.00496 weeks <br />0.00114 months <br /> during a calendar year fo' the l
4-inch valves. The total time the containment purge (vent) system isolatian valves may be open during MODES 1, 2, 3,.and 4 in a calendar year is a fur.ction of anticipated need and operating experiencre.
Only safety related reasons;
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e.g., containment pressure control or the redur. tion of airborne radiosctivity to f acilitate personnel access for s'arveilit6ce and maintenance activities, may be used to justify the opening of these isciation valves.
l Leakage integrity tests with a maximum allowable leakage rate for contain-ment purge supply and exnaust valves will provide early indication of resilient material seal degradation and will allow opportunity f or repair before gross leakage failures could develop.
The 0.60 L, leakage limit of Specification 2.5.1.20. snall not oe exceecec when tne leakage rates ceternined by tne leakage i.te;-ity tests of tnese valvss are acaec to tne creviously ceterminec tote; i:
aP vaives an: eenetrations s=je:t te Type E a7c C tests.
- G-I
UCT! '. s ;
i 3/' t-3 m en m.t h:. r (unit 1)
Amencment h:. 5 '. Unit 2) 8802090303 800125 PDR ADOCK 05000413:
p PDR
r:
-TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NUMBER FUNCTION N!59 Accumulator Discharge NI60 Accumulator Discharge NI70 Accumulator Discharge NI71 Accumulator Discharge N181 Accumualtor Discharge N!82 Accumulator Discharge NI93 Accumulator Discharge NI94 Accumulator Discharge NI124 9afety Injection (Hot Leg)
NI125
!tesidual Heat Removal (Hot Leg)
NI126 Safety Injection (Hot Leg)
NI128 Safety Injection (Hot Leg)
NI129 Residual Heat Removal (Hot Leg)
N1134 Safety: Injection (Hot Leg)
NI156 Safety: Injection (Hot Leg)
NI157 Safety Injection (Hot Leg)
NI159 Safety' Injection (Hot Leg)
NI160 Safety Injection (Hot Leg)
HI165 Safety Injection / Residual Heat Removal (Cold Leg)
NI167 Safety Injection / Residual Heat Removal (Cold Leg)
NI169 Safety Injection / Residual Heat Removal (Cold Leg)
NI171 Safety Injection / Residual Heat Removal (Cold Leg)
NI175 Safety Injection / Residual Heat Removal (Cold Leg)
NI176 Safety ~ Injection / Residual Heat Removal (Cold Leg)
NI180 Safety Injection / Residual Heat Removal (Cold Leg)
NI181 Safety Injection / Residual Heat Removal (Cold Leg)
I NI248 Upper Head Injection q NI249 Upper Head Injection NI250 Upper Head Injection i
NI251 Upper Head Injection
- Note 1 NI252 Upper Head Injection u NI253 Upper Head Injection g
l Note 1:
Upon the disconnection of the UHI System from the Reactor Coolant System, this specification is no longer applicable.
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CATKGA - UNITS 1 & 2 3/4 4-22 Amencment No.32 (Unit 1) l Amendment No.23 (Unit 2)
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