ML19326C291
| ML19326C291 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/30/1976 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19326C282 | List: |
| References | |
| NUDOCS 8004220848 | |
| Download: ML19326C291 (18) | |
Text
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refueling temperature (normally 140F). Pressure is defined by Specifi-cation 3.1.2.
A refueling shutdown refers to a shutdown to replace or rearrange all or a portion of the fuel assemblies and/or control rods.
1.2.7 Reftteling Operation An operation involving a change in core geometry by manipulation of fuel or control ieds when the reactor vessel head is removed.
1.2.8 Refueling Period (deleted) 1.2.9 Startup The reactor shall be considered in the startup mode when the shutdown margin is reduced with the intent of going critical.
1.3 OPERABLE A component or system is operable when it is capable of performing its intended function within the required range. The component or system shall be consid-cred to have this capability when:
(1) it satisfies the limiting conditions for operation defined in Specification 3, and (2) it has been tested period-ically in accordance with Specification 4, and has met its performance require-ments.
1.4 PROTECTION INSTRUMENTATION LOGIC 1.4.1 Instrument Channel An instrument channel is the combination of sensor, wires, amplifiers and output devices which are connected for the purpose of measurf.ag the value of
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a process variable for the purpose of obse.vation, control and/or protection.
An instrument channel may be either analog or digital.
1.4.2 Reactor Protection System The reactor protection system is shown in Figures 7-1 and 7-9 of the FSAR.
It is that combination of protective channels and associated circuitry which forms the automatic system that protects the reactor by control rod trip.
It includes the four protection channels, their associated instrument channel inputs, manual trip switch, all rod drive control protective trip breakers and
' activating relays or coils.
A protection channel, as shown in Figure 7-1 of the FSAR (one of three or one of four independent channels, complete with sensors, sensor power supply 2
8004220 l
+
Other channels are subject only to " drift" errors induced within the instrumentation itself and, consequently, can tolerate longer intervals between calibrations.
Process system instrumentation errors induced by drift can be expected to remain within acceptable tolerances if re-calibration is performed once every 18 months.
Substantial calibration shifts within a channel (essentially a channel failure) will be revealed during routine checking and testing procedures.
Thus, minimum calibration frequencies for the nuclear flux (power range) channels, and once every 18 months for the process system channels is considered acceptable.
Testing On-line testing of reactor protective channels is required once every 4 weeks on a rotational or staggered basis. The rotation scheme is designed to reduce the probability of an undetected failure existing within the system and to minimize the likelihood of the same systematic test errors being introduced into each redundant channel.
The rotation schedule for the reactor protective channels is as follows:
Channels A, B, C, D Before Startup if shutdown greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Channel A One Week After Startup Channel B Two Weeks After Startup
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Channel C Three Weeks After Startup Channel D Four Weeks After Startup The reactor protective system instrumentation test cycle is continued with one channel's instrumentation tested each week. Upon detection of a failure that prevents trip action, all instrumentation associated with the protective channels will be tested after which the rotational test cycle is started again.
If actuation of a safety channel occurs, assurance will be required that actuation was within the limiting safety system setting.
The protective channels coincidence logic and control rod drive trip.
breakers are trip tested every four weeks. The trip test checks all logic combinations and is to be performed on a rotational basis. The logic and breakers of the four protective channels shall be trip tested prior to startup and their individual channels trip tested on a cyclic basis.
Discovery of a failure requires the testing of all channel logic and breakers, after which the trip test cycle is started again.
The equipment testing and system sampling frequencies specified in Table 4.1-2 and Table 4.1-3 are considered adequate to maintain the status of 2
the equipment and systcms to assure safe operation.
REFERENCE f
FSAR Section 7.1.2.3.4 i
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Table k.1-1 (cont'd)
Channel Description Check Test Calibrate Remarks 37 Boric Acid Addition Tank a.
Level Channel NA NA R
b.
Temperature Channel M
NA R
- 38. ' Sodium Thiosulfate Tank NA NA R
Level Indicator 39 Sodium Rydroxide Tank' NA NA R
Level Indicatcr LO.
Incore Neutron Detectcrs
':(1)
NA NA (1) Check Functionir.g
-a Ll.
Emergency Plant Radiaticn Y
Instruments M(1)
NA R
(1) Battery Check 42.
1)eleted h3.
Strong Motion Acceleographs Q(1)
NA Q
(1) Eattery Check hk.
ESAS Manual Trip Functions a.
Switches & Logic NA R
NA b.
Logic NA M
NA 45 Reactor Manual Trip NA P
NA
- h6.
Reactor Building Sump Level NA NA R
Note: S - Each Shift T/W - Twice per Week R - Once every 18 months D - Daily B/M - Every 2 Mcnths NA - Net Applicable W - Weekly Q - Quarterly M - Monthly P - Prior to Each Startup if Not Done Previous "a'eek
f Tabic 4.1-2 Minimtsn Equipment Test Frequency Item Test Frequency 1.
Control Rods Rod Drop Times of All Each Refueling Shutdown Full Length Rods 1/
2.
Control Rod Movement Movement of Each Rod Every Two Weeks Above Cold Shutdown Conditions 3.
Pressurizer Code Setpoint One Valve Every 18 Months Safety Valves 4.
Main Steam Safety Setpoint Four Valve Every 18 Months Valves S.
Refueling System Functioning Start of Each Refueling Interlocks Shutdown 6.
Reactor Coolant Evaluate Daily System Leakage 7.
Deleted 8.
Reactor Building Functioning Every 18 Months Isolation Trip 9.
Service Water Functioning Every 18 Months Systems
- 10. Spent Fuel Cooling Functioning Every 18 Months when System irradiated fuel is in the pool.
- 11. Decay fleat Removal Functioning Every 18 Months System Isolation Valve Automatic Closure and Isola-tion System 1/ Same as tests listed in Section 4.7 73
t Table 4.1-2 (Continued)
Minimum Equipment Test Frequency Item Test Frequency 12.
Flow Limiting Annulus Verify, at normal One year, two years, on Main Feedwater operating conditions, three years, and every Lines at Reactor that a gap of at least five years thereafter Building Penetration 0.025 inches exists measured from date of between the pipe and initial test.
the annulus.
13.
SLBIC Pressure Calibrate Every 18 Months Sensors 14 Main Steam Isolation
- a. Exercise Through
- a. Quarterly Valves Approximately 10%
Travel
- b. Cycle
- b. Every 18 Months 4
- 15. Main Feedwater
- a. Exercise Through a Quarterly Isolation Valves Approximately 5%
Travel
- b. Cycle
- b. Every 18 Months 4
73a
4.4.1.2.5 Test Frequency Local leak detection tests shall be performed during each reactor shutdown for refueling or other convenien* intervals, but in no case at intervals >2 years except that:
(a) The equipment hatch and fuel transfer tube seals shall be additionally tested after each opening.
(b)
If a personnel hatch or energency hatch door is opened when reactor building integrity is required, the affected door seal shall be tested.
In addition, a pressure test shall be performed on the personnel and emergency hatches every six months.
4.4.1.3 Reactor Building Modifications Any major modification or replacement of components affecting the reactor building integrity shall be followed by either an integrated leak rate test or a local leak test, as appropriate, and shall meet the acceptance criteria specified in 4.4.1.1 and 4.4.1.2 respectively.
4.4.1.4 Isolation Valve Functional Tests Every three months, remotely operated reactor building isolation valves shall be stroked to the position required to fulfill their safety function unless such operation is not practical during plant operation. The latter valves shall be tested once every 18 months.
4.4.1.5 Visual Inspection
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A visual examination of the accessible interior and exterior surfaces of the reactor building structure and its components shall be performed during each refueling shutdown and prior to any integrated leak test, to uncover any evidence of deterioration which may affect either the reactor building's structural integrity or leak-tightness. The discovery of any significant deterioration shall be accompanied by corrective actions in accord with acceptable procedures, nondestructive tests, and inspections, and local testing where practical prior to the conduct of any integrated leak test.
Such repairs shall be reported as part of the test results.
Bases (1)
The reactor building is designed for an internal pressure of 59 psig and a steam-air mixture temperature of 285F. Prior to initial operation, the reactor building will be strength tested at 115% of design pressure and leak rate tested at the design pressure. The reactor building will also be leak tested prior to initial operation at not less than 50% of 83
4.5 EMERGENCY CORE COOLING SYSTEM AND REACTOR BUILDING COOLING SYSTEM PERIODIC TESTING 4.5.1 Emergency Core Cooling Systems Applicability Applies to periodic testing requirement for emergency core cooling systems.
Objective To verify that the emergency core cooling systems are operable.
Specification 4.5.1.1 System Tests 4.5.1.1.1 High Pressure Injection System (a) Once every 18 months, a system test shall be conducted to demonstrate that the system is operaale. A test signal will be applied to demon-strate actuation of the high pressure injection system for emergency core cooling operation.
(b) The test will be considered satisfactory if control board indication verifies that all components have responded to the actuation signal properly; all appropriate pump breakers shall have opened or closed and all valves shall have completed their travel.
4.5.1.1.2 Low Pressure Injection System (a) Once every 18 months, a system test shall be conducted to demonstrate that the system is operable. The test shall be performed in accordance with the procedure summarized below:
(1) A test signal will be applied to demonstrate actuation of the low nressure injection system for emergency core cooling operation.
(2) Verification of tho engineered safeguard function of the service water system which supplies cooling water to the decay heat removal coolers shall.be made to demonstrate operability of the coolers.
(b) The test will be considered satisfactory if control board indication verifies that all components have responded to the actuation signal properly; all appropriate pump breakers shall have opened or closed, and all valves shall have completed their travel.
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-~r 4.5.1.1.3 Core Flooding System (a) Once every 18 months, a system test shall be conducted to demon-strate proper operation of the system. During this test, verifi-cation shall be made that the check valves in the core flooding tank discharge lines operate properly.
(b) The test will be considered satisfactory if control board indica-tion of core flood tank level verifies that all check valves have opened.
4.5.1.2 Component Tests 4J.1.2.1 Pumps Approximately quarterly, the high pressure and low pressure in-jection pumps shall te started and operated to verify proper operation. Acceptable performance will be indicated if the pump starts, operates for fifteen minutes, and the discharge pressure and flow are within +10% of the initial level of per-formance as determined using test flow paths.
4.5.1.2.2 Valves - Power Operated (a) At intervals not to exceed three months each, engineered safety feature valve in the emergency core cooling systems and each engineered safety feature valve associated with emergency core cooling in the service water system which are designed to open in the event of a LOCA shall be tested to verify operability.
(b) The acceptable performance of each power operated valve will be that motion is indicated upon actuation by appropriate signals.
Bases The emergency core cooling systems are the principle reactor safety features in the event of a loss of coolant accident.
vided by these systems is designed to limit core damage.The removal of heat from the The high pressure injection system under normal operating conditions has one pump operating. At least once per month, operation will be rotated to another high pressure injection pump. This will help verify that the high pressure injection pumps are operable.
The requirements of the service water system for cooling water are more severe
-during normal operation than under accident conditions.
Rotation of the pump in operation on a monthly basis will verify that two pumps are operable.
The low pressure injection pumps are tested singularly for operability by open-ing the borated water storage tank outlet valves and the borated water storage tank recire line.
Thi; allows water to be pumped from the borated water storage tank through each of the injection lines and back to the tank.
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4.5.2 Reactor Building Cooling Systems Applicability Applies to testing of the reactor building cooling systems.
Obj ective To verify that the reactor building cooling systems are operable.
Specificatio,n 4.5.2.1 System Tests 4.5.2.1.1 Reactor Building Spray System (a) Once every 18 months, a system test shall be conducted to demon-strate proper operation of the system. A test signal will be applied to demonstrate actuation of the reactor building spray system (except for reactor building inlet valves to prevent water entering nozzles).
(b)
Station compressed air or smoke will be introduced into the spray headers to verify the availability of the headers and spray nozzles at least every five years.
(c) The test will be considered ratisfactory if visual observation and control board indication verifies that all components have responded to the actuation signal properly.
4.5.2.1.2 Reactor Building Cooling System (a) Once every 18 months, a system test shall be conducted to demon-strate proper operation of the system. The test shall be per-formed in accordance with the procedure summarized below:
(1) A test signal will be applied to actuate the reactor building cooling operation.
(2) Verification of the engineered safety features function of the service water system which supplies the reactor building coolers shall be made to demonstrate operability of the coolers.
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'4.6 AUXILIARY ELECTRICAL SYSTEM TESTS Applicability Applies to the periodic. testing and surveillance requirements of the auxiliary electrical system to ensure it will respond promptly and properly when required.
Specification 4.6.1 Diesel Generators 1.
Each diesel generator shall be manually started each month and demonstrated to be ready for loading within 15 seconds.
The signal initiating the start of the diesel shall be varied from one test to another (start with handswitch at control room panel and at diesel local control panel) to verify all starting circuits are operable. The generator shall be synchronized from the control room and loaded to full rated load and allowed to run until diesel generator operating temperatures have stabilized.
2.
A test shall be conducted once every 18 months to demon-strate that the emergency power system is available to carry load within 15 seconds of a simulated ES signal of the safety features system coincident with the loss of offsite power. The diesel generator shall be full loaded and run for one hour after operating temperatures have stabilized.
3.
Each diesel generator shall be given an inspection once every 18 months following the manufacture's recommendations for this class of standby service. -
4.
During the monthly diesel _ generator test specified in Paragraph 1 above, the diesel starting air compressors shall be checked for operation and their ability to recharge _ the air receivers.
Also monthly, the diesel oil transfer pumps shall be checked for operation and their ability to transfer oil to the day tank.
5.
Once every 18 months, the capability of each starting air
. compressor to charge the. air receivers from 0 to 225 psig within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> shall be verified.
Also once every 18 months, the capacity of each diesel oil transfer pump shall be verified to be at least 10 gpm.
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1 100 1
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Pressure drop across the combined HEPA filters and charcoal adsorbers of less than 6 ~ inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.
Pressure drop and air distribution should be determined once every 18 months to show system performance capability.
The frequency of tests and sample analysis are necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated. The charcoal adsorber efficiency test procedures should allow for obtaining at least two samples. Each sample should be at least two inches in diameter and a length equal to the thickness of the bed. Tests of the charcoal adsorbers with halogenated hydrocarbon refrigerant and of the HEPA filter bank with DOP aerosol shall be performed in accordance with ANSI N510 (1975) " Standard for Testing of Nuclear Air Cleaning Systems." Any HEPA filters found defective shall be replaced with filters qualified according to Regulatory Position C.3.d. of Regulatory Guide 1.52.
Radioactive methyl iodide removal efficiency tests shall be performed in accordance with RDT Standard M16-IT.
If laboratory test results are unacceptable, all charcoal adsorbents in the system shall be replaced with charcoal adsorbents qualified according to Regulatory Guide 1.52.
9 110g
Bases The emergency power system provides power requirements for the engineered safety features in the event of a DBA.
Each of the two diesel generators is capable of supplying minimum required engineered safety features from independent buses. This redundancy is a factor in establishing testing int ervals. The monthly tests specified above will demonstrate operability and load capacity of the diesel generator.
The fuel supply and diesel starter motor air pressure are continuously monitored and alarmed for abnormal conditions. Starting on complete loss of off-site power will t e verified by simulated loss-of-power tests once every 18 months.
Considering system redundancy, the specified testing intervals for the station batteries should be adequate to detect and coirect any mal-function before it can result in system malfunction.
Batteries will deteriorate with time, but precipitous failure is extremely unlikely.
The surveillance specified is that which has been demonstrated over the years to provide an indication of a cell becoming unserviceable long before it fails.
Routine battery maintenance specified by the manufacturer includes regularly scheduled equalizing charges in order to retain the capacity of the battery. A test discharge should be conducted to ascertain the capability of the battery to perform its design function under postulated accident condition.
An excessive drop of voltage with respect to time is indicative of required battery maintenance or replacement.
Testing of the emergency lighting is scheduled annually and is subject to review and modification if experience demonstrates a more effective test schedule.
References FSAR, Section 8 101 v
4.8 EMERGENCY FEEDWATER PUMP Applicability Applies to the periodic testing of the turbine and electric motor driven emergency feedwater pumps.
Objective To verify that the emergency feedwater pump and associated valves are operable.
Specification 4.8.1 Test 1.
The turbine and electric motor driven emergency feedwater pumps shall be operated every three months for a minimum of one hour.
2.
The emergency feedwater valves shall be cycled every three months.
3.
Once every 18 months, a functional test of the emergency feed-water system shall be made using the electric motor driven emergency feedwater pump.
4.8.2 Acceptance Criteria This test shall be considered satisfactory if control board indication and visual observation of the equipment demonstrates that s11 components have oper.ted properly.
Bases The three (3) month testing frequency will be sufficient to verify that both emergency feedwater pumps are operable. Verification of correct operation will be made both from the ccrtrol room instrumentation and direct visual observation of the pumps. The cycling of the emergency valves will be done coincident with the pump testing, but not concur-rently so that cold emergency feedwater is not pumped to the steam generator.
The functional test, performed once every 18 months, will verify that the flow path to the steam generators is open and that water reaches the steam generators from the emergency feedwater system. The test is done during shutdown to avoid thermal cy-le to the emergency feedwater no::les on the steam generator due to the lower temperature of the emergency feedwater.
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4.10 CON' TROL ROOM EME ENCY AIR CONDITIONING SYSTEM SU vEILLANCE Applicability Applies to the surveillance of the control room emergency air condition-system.
Objective To verify an acceptable level of efficiency and operability of the control room emergency air conditioning system.
Specification 4.10.1 Once every. 8 months, the pressure drop across the combined HEPA 1
filters and charcoal adsorber banks shall be demonstrated to be less than 6 inches of water at system design flow (+ 10%).
4.10.2 Once every 18 months, automatic initiation of the control room emergency air conditioning system shall be demonstrated.
4.10.3.a The tests and sample analysis of Specification 3.9.1.a,b, 6 c. shall be performed initially
- and once every 18 months or after every 720 he' irs of system operation and following significant painting, fire or chemical release in any ventila-tion zone communicating with the system.
- b. Cold D0P testing shall also be performed after each complete or partial replacement of the HEPA filter bank or after any struc-tural maintenance on the system housing.
- c. !!alogenated hydrocaroon testing shall also be performed after
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each complete.or partial replacement of the charcoal adsorber
' bank ~ or after any structural maintenance on the system housing.
4.10.4 Each circuit shall be operated at least I hour every month.
Bases The purpose of the control room filtering system is to limit the particulate I
and gaseous fission products to which the control area would be subjected during an accidental radioactive release in or near the Auxiliary Building.
The system is designed with 100 percent capacity filter trains which consist of a prefilter, high efficiency particulate filters, charcoal adsorbers and a fan.
Since the system is not normally operated, a periodic test is required to insure operability when needed. During this test the system will be inspected for such things as water, oil, or other foreign material; gasket deterioration,
- Initial tests shall be performed within 90 days of the date of issuance of Amendment 10 to License No. DPR-51.
107
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3 4.11 PENETRATION ROOM VENTILATION SYSTEM SURVEILLANCE Applicability Applies to the surveillance of the penetration room ventilation system.
Objective To verify an acceptable level of efficiency and operability of the pene-tration room ventilation system.
Specification 4.11.1 Once every 18 months, the following conditions shall be demonstrated:
T:ie pressure drop across the combined HEPA filters and charcoal a.
adsorber banks is less than 6 inches of water at system design flow rate (+ 10%).
b.
Air distribution is uniform within + 20% across HEPA filters and charcoal adsorbers, 4.11.2 Once every 18 months, autocatic initiation of the penetration room ventialtion system shall be demonstrate.
4.11.3a The tests and sample analysis of Specification 3.13.la,b, 6 c. shall be performed initially-and every 18 months or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of sy sm epe cation and following signifi-cant painting, fire or che 8 release in any ventilation zone communicating with the systc..
b.
Cold DOP testing shall also be performed after each complete or partial replacement of the HEPA filter bank or after any struc-tural maintenance on the system housing.
Halogenated hydrocarbon testing shall also be performed after L
c.
each complete or partial replacement of the charcoal adsorber bank or after any structural maintenance on the system housing.
4.11.4 Each circuit shall be operated at least I hour every month. This test shall be considered satisfactory if control board indication verifles that all components have responded properly to the actu-ation signal.
- Initial tests shall be performed within 90 days of the date of issuance of Amendment 10 to License No. DPR-51.
109
.m 4.12. HYDROGEN PURGE SYSTEM SURVEILLANCE
. Applicability Applies to the surveillance of the hydrogen purge system.
Objective To verify an acceptable level of efficiency and operability of the hydrogen purge system.
Specification 4.12.1 Once every 18 months, the followlag conditions shall be demonstrated:
a.
The pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 16 inches of water at system design flow rate (+ 10%).
b.
Each system inlet heater unit operates at rated power.
4.12.2.a.
The tests and sample analysis of Specification 3.14.1.a,b, 6 c. shall be performed initially
- and once every 18 months or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation and following significant painting, fire or chemical release in any ventil-ation zone communicating with the system.
b.
Cold DOP testing shall also be performed after each complete or partial replacement of a HEPA filter bank or after any structural maintenance on the system housing.
4 c.
Halogenated hydrocarbon testing shall also be performed after each complete or partial replacement of a charcoal adsorber bank or after any structural maintenance on the system housing.
4.12.3 Each cir".ait shall be operated at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> each month.
4.12.4 Hydrog a concentration instruments shall be calibrated once every 18 month with proper consideration to moisture effect.
Bases Since the hydrogen purge -system is not normally operated, a periodic test is required to show that the system is available for hydrogen contret fdllowing an accident.
During this test, the system will be inspe.. 1 for j
such things.as water, oil, or other foreign material, gasket deterioration i
in the HEPA units,. and unusual or excessive noise or vibration when the fan motor is running.
- Initial tests = shc11 be performed within 9 months of the date of issuance of Amb.cdment 'O to License ~No. DPR-51 issued 2/18/76.
109b
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4.17 FUEL 11ANDLING AREA VENTILATION SYSTEM SURVEILLANCE Applicability Applies to the surveillance of the fuel handling area ventilation system.
Objective To verify in acceptable level of efficiency and operability of the fuel handling area ventialtion system.
Specification 4.17.1 Once every 18 months, the following conditions shall be demonstrated:
a.
Pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches of water at system design flow rate (+ 10%).
b.
Air distribution is uriform within + 20% across HEPA filters and charcoal adsorbers.
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4.17.2.a.
The tests and sample analysis of Specification 3.15.1.a,b, 6 c.
shall be performti within 720 system operating hours prior to irradiated fuel hai.iling operations in the auxiliary building, and prior to irradiais4 fuel handling in the auxiliary build-ing following significant painting, fire or chemical release in any ventilation zone communicating with the system.
b.
Cold DOP testing shall also be performed prior to irradiated fuel handling in the auxiliary building after each complete or partial replacement of a HEPA filter bank or after any structural maintenance on the system housing, Halogenated hydrocarbon testing shall also be performed prior c.
to irradiated fuel handling in the auxiliary building after each complete or partial replacement of a charcoal adsorber bank or after any structural maintenance on the system housing.
4.17.3 The systes : ball _ be operated for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> prior to initia-tion of irradiated fuel handling operations in the auxiliary building if it has not been operated for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> within the previous 30 days.
Bases Since the fuel handling area ventilation system may be in operation when fuel is stored in the pool but not being handled, its operability must be verified before handling of irradiated fuel. Operation of the system for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> before irradiated fuel handling operations and performance of Specification 4.17.2 will demonstrate operability of the active system components and the filter and adsorber systems.
110f
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Pressure drip across the combined HEPA filters and charcoal adsorbers of less than 6 inches of water at the system design flow rate will indicate that the filt. rs and adsorbers are not clogged by excessive amounts of foreign matter.
Pressure drop and air distribution should be determined once every 18 months to show system performance capability.
The frequency of tests and sample analysis are necessary to show that the hEPA filters and charcoal adsorbers can perform as evaluated. The charcoal adsarber efficiency test procedures should allow for obtaining at least two samples.
Each sample should be at least two inches in diameter and a length equal to the thickness of the bed. Tests of the charcoal adsorbers with halogenated hydrocarbon refrigerant and of the HEPA filter bank with DOP aerosol shall be performed in accordance with ANSI N510 (1975) " Standard for Testing of Nuclear Air Cleaning Systems." Any HEPA filters found defective shall be replaced with filters qualified according to Regulatory Position C.3.d. of Regulatory Guide 1.52.
Radioactive methyl iodide removal efficiency tests shall be performed in accordance with RDT Standard M16-IT.
I# 1aboratory test results are unacceptable, all charcoal adsorbents in the system shall be replaced with charcoal adsorbents qualified according to Regulatory Guide 1.52.
110g