ML19211A159
| ML19211A159 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/30/1979 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19211A157 | List: |
| References | |
| NUDOCS 7912170108 | |
| Download: ML19211A159 (10) | |
Text
INSTRUMENTATION POST-ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.5 The post accident monitoring instrumentation channels shown in Table 3.3.7.5-1 shall be OPERABLE.
APPLICABILITY:
OPERATIONAL CONDITIONS 1 and 2.
ACTION:
a.
With one or more post-accident monitoring instrumentation channels inoperable, restore the inoperable channel (s) to OPERABLE status within 30 days or be in at least HOT SHUTCOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.3.7.5 Each of the above required post-accident monitoring instrumentation I
channels shall be demonstrated OPERABLE by performance of the CHANT.il CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.5-1.l 1595 044 3E-STS 3/4 3-59 7912170IC)E
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1ABLE 3.3.7.5-1 p
[i POSI-ACCIDENT HONITORING INSTRUMENTATION HINIHUM INSTRUMENTS l OPERABLE INSIRUMLNI I.
Reactor Vessel Pressure 2
2.
Heactor Vessel Water Level 2
2 3.
Suppression Chamber Water Level 2
4.
Suppression Chamber Water Temperature 2
S.
Suppression Chamber Air Temperature s
2
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6.
Drywell Pressure 2
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7.
Drywell Temperature O
2 8.
Drywell Oxygen Concentration +
2 9.
Drywell flydrogen Concentration 10.
II.
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TABLE 4.3.7.5-l' "I
POSI-ACCIDElli HONITORING lilSTRUMENIATION SURVEILLANCE REQUIREMENTS CliANNEL CHANNEL INSTRUMENT CilECK CAllBRATION 1.
Reactor Vessel Pressure H
R l
2.
R l
3.
Suppression Chamber Water Level H
R 4.
Suppression Chamber Water Temperature H
R S.
Suppression Chamber Air Temperature H
R
{
6.
Primary Containment Pressure H
R l
H R
'f 7.
Drywell,Iemperature ll 8.
Drywell Oxygen Concentration NA R
9.
Drywell flyttrogen Concentration HA R
10.
11.
12.
C LJ1 CD A
Ch 8
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- (QK ALTERNATE Sysr*:ms As APM0!RIATk PRIMARY CONTAINMENT ATMOSPHERE DILUTION SYSTEM (If less than two hydrogen recombiners available)
D LIMITING CONDITION FOR OPERATION 3.6.'6.2 The primary containment atmosphere dilution (CAD) system shall be l
OPERABLE with:
An OPERABLE flow path capable of supplying nitrogen to the drywell,
~
a.
and b.
A minimum supply of (4350) gallons of liquid nitrogen.
APDLICABILITY:
OPERATIONAL CONDITIONS 1 and 2.
ACTION:
With the CAD system inoperable, restore the CAD system to OPERABLE status within 30 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 />.
SURVEILLANCE REOUIREMENTS 4.6.6.2 The primary containment atmosphere dilution system shall be demon-(
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strated to be OPERABLE:
a.
At least once per 31 days by verifying that:
1.
The system contains a minimum of (4350) gallons of liquid nitrogen, and 2.
Each valve (manual, power operated or automatic) in the flow path not locked, sealed, of otherwise secured in position, is in its correct position.
b.
At least once per 18 months by:
1.
Cycling each power operated (excluding automatic) valve in the flow path not testable during plant operation through at least one complete cycle of full travel, and 2.
Verifying that each automatic valve in the flew path actuates to its correct position on a i solation test signal.
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CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYORQGEN MIXING SYSTEM LIM! TING CONDITION FOR OPERATION l
APPLICABILITY:
CPERATIONAL CONDITIONS 1 and 2.
ACTION:
With one hydrogen mixing system inoperable, restor, the inoperable system to l
OPERABLE status within 30 days or be in at least b -T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i 1
SURVEILLANCE RE0VIREMENTS 4.6.6.3 Each hydrogen mixing system shall be demonstrated OPERABLE:
l I
a.
At least once per 92 days by:
i 1.
Starting the system from the control room, 2.
Verifying that the system operates for at least 15 minutes, and I
3.
Verifying that the system is aligned to receive electrical power !
frem separate OPERABLE emergency buses.
b.
At least once per 18 months by qerifying a system flow rate of et least cfm.
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PRIMARY CONTAINMENT OXYGEN CONCENTRATION LIMITING CONDITION FOR OPERATION 3.6.6.4 The primary containment atmosphere oxygen concentrat*on shall be less than 4% by (volume).
APPLICABILITY:
OPERATIONAL CONDITION 1", during the time period:
i a.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is gre er than 15% of RATED THERMAL,
POWER, following startup, to l
b.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducing THERMAL POWER to less than 15% of RATED THERMAL POWER preliminary to a scheduled reactor shutdown.
ACTION:
With the oxygen concentration in the primary containment exceeding the limit, be in at least STARTUP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
O SURVEILLANCE REOUIREMENTS 4.6.6.4 The oxygen concentration in the primary containmen hall be verified to be within the limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> afthr THERMAL POWET# greater than 15% of RATED THERMAL POWER and at least once per 7 days thereafter..
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SPECIAL TEST EXCEPTIONS 3/4.10.5 OXYGEN CONCENTRATION LIMITING CONDITION FOR OPERATION 3.10.5 The provisions of Specification 3.6.6 ay be suspended during the performance of the Startup Test Program until ther the required 100% of RATED l
THERMAL POWER trip tests nave been completed or the reactor has operated for 120 Effective Full Power Days.
APPLICABILITY:
OPERATIONAL CONDITION 1.
ACTION With the requirements of the above specification not satisfied, be in at least STARTUP within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.10.5 The Effective Full Power Days of operation shall be verified to be less than 120, by calculation, at least once per 7 days during the Startup Test Program.
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INSTRUMENTATION r"-""".
F BASES 3/4.3.7.5 POST-ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures.that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident.
(This capability is consistent with the reconmendations of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant conditions During and Following an Accident," December 1975.)
3/4.3.7.6 SOURCE RANGE MONITORS l
The source rara;e monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown.
At these power levels, reactivity additions should not be made without this flux level information available to the operator.
When the inter-mediate range monitors are on scale adequate information is available without the SRMs and they can be retracted.
3/4.3.7.7 TRAVERSING IN-CORE PROSE SYSTEM The OPERABILITY of the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipmerit accurately represent the spatial neutron flux distribution of the reactor core.
The OPERABILITY of this system is demonstrated by irra-diating each cetector to be used and determining the acceptability of its voltage curve.
For the purpose of measuring a full incore flux map is used.
Quarter-core 'fldx maps, as defined in
, may be used and full incore flux maps or symmetric incere thimoles may ce usec for measuring
- 4. 3. 7. 8 CHLORINE DETECTION SYSTEM 7-
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The OPERABILITY of the chlorine detect.icn system ensures that an accidental chlorine release will be detected promptly aJid tne necessary protective actions will be automatically initiated to provided protection for control room personnel.
Upon detection of a high concentration of chlorine, the control room emergency ventilation system will autcmatically be placed in the (isolation) mode of opera-tion to provide the required protection.
(The detection systems required by this specification are consistent with the recommendations of Regulatory Guide 1.95 " Protection of Nuclear Power Pian Control Room Operators against an Accicental Chlorine Release", Fecruary 1975.)
3/4.3.7.9 CHLOR DE INTRUSION MONITCES T.s :r.ierice intrusi n me. nit:rs Or0.ics adecuate warning of any leakage in.re concenser or rotwell so that actions can be taken to mitigate the :en-4 secuences of seen intrusion in the reactor coolant system.
With only a minimum
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m:er Of instruments availac'e increasec sampling frequency provides acequate
':-.3-ion for :ne same pur:csa.
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3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL The OPERABILITY of the systems required for the detection and control of hydrogen gas ensures that these systems will be available to maintain the
. hydrogen concentration within the primary containment below its flammable limit durina post-LOCA conditions.
Either hydrogen recombiner (or the primary con-tainment atmosphere dilution system) system is capable of controlling the expected hydrogen generation associated with (1) zirconium-water reactions, (2) radiolytic decomposition of water and (3) corrosion of metals within con-tainment.
(The hydrogen mixing systems are provided to ensure adequate mixing of the containment atmosphere following a LOCA.
This mixing action will prevent.
localized accumulations of hydrogen from exceeding the flammable limit.)
(The hydrogen control system is consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations in Containment Following a LOCA", March 1971. )
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