ML19326B860
| ML19326B860 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/07/1975 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19326B859 | List: |
| References | |
| NUDOCS 8004180595 | |
| Download: ML19326B860 (38) | |
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.. ;,c TABLE OF CONTEhTS as-fMS SECTION TITLE PAGE
- 1. DEFINITIONS 1 1.1 RATED POWER 1 1.2 REALTOR OPERATING CONDITIONS 1 1.3 OPERABLE 2 4
1.4 PROTECTION INSTRUMENTATION LOGIC 2 1.5 INSTRUMENTATION SURVEILLANCE 3 1.6 QUADRANT POWER TILT 4 1.7 REALTOR BUILDING 4 1.8 ABNORMAL OCCURRENCE 6
- 2. SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS-7 2.1 SAFETY LIMITS, REACIDR CORE 7 2.2 SAFETY LIMITS, REACTOR SYSTD1 PRESSURE 10 2.3 LIMITING SAFETY SYSTEM SE"ITINGS, PROTECTIVE INSTRU-MENTATION 11
- 3. LIMITING CONDITIONS FOR OPERATION 16 3.1 REACTOR C00LAKr SYSTEM 16 3.1.1 Operational Components 16 3.1.2 Pressurization, Heatup and Cooldown Limitations 18 3.1.3 Minimon Conditions for Criticality 21 3.1.4 Reactor Coolant System Activity 22 3.1.5 Chemistry 25 3.1.6 Leakage 27 3.1.7 bbderator Temperature Coefficient of Reactivity 30 3.1.8 Low Power Physics Testing Restrictions 31 3.1.9 Control Rod Operation 32 3.2 MAKEUP AND QiEMICAL ADDITION SYSTEMS 34 3.3 EMERGENCY CORE COOLING, REACTOR BUILDING COOLING, AND REACTOR BUILDING SPRAY SYSTatS 36 3.4 STEAM AND POWER CONVERSION SYSTEM 40 -
3.5 INSTRUMENTATION SYSTDIS 42 3.5.1 Operational Safety Instrumentation 42 3.5.2 Control Rod Group and Power Distribution Limits 46 3.5.3 Safety Features Actuation System Setpoints 49 3.5.4 In-Core Instrumentation 51 3.6 REACTOR BUILDING 54 3.7 AUXILIARY ELECTRICAL SYSTDI 56 3.8 FUEL IDADING AND REFUELING 58 3.9 CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTDI 60 l 3.10 SECONDARY SYSTDI ACTIVITY 66 3.11 EMERGENCY COOLING POND 66a 3.12 MISCELLANE0US RADIOACTIVE MATERIALS SOURCES 66b 3,13 PENETRATION ROOM VEhTILATION SYSTDI 66c 3,14 HYDROGEN PURGE SYSTEM 66e _
3.15 FUEL HANDLING AREA VENTILATION SYSTEM 66g 8 U d I 8 0f RF~
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- 4. SURVEILLANCE REQUIREMENTS 67 4.1 OPERATIONAL SAFETY ITEMS 67 4.2 REACTOR COOLANT SYSTEM SURVEILLANCE 76 4.3 REACTOR COOLANT SYSTEM INTEGRITY FOLLOWING ENTRY 78 4.4 REACTOR BUILDING 79 4.4.1 Reactor Building Leakage Test 79 4.4.2 Structural Integrity 85 4.5 EMERGENCY CORE COOLING SYSTEM AND REACTOR BUILDING COOLING SYSTEM PERIODIC TESTING 92 4.5.1 Emergency Core Cooling System 92 4.5.2 Reactor Building Cooling Systems 95 g 4.6 AUXILIARY ELECTRICAL SYSTEM TESTS 100 4.7 REACTOR CONTROL ROD SYSTEM TESTS 102 4.7.1 Control Rod Drive System Functional Tests 102 -
4.7.2 Control Rod Pro gram Verification 104 4.8 EMERGENCY FEEDWATiR PUMP TESTING 105 4.9 REACTIVITY ANOMALIES 106 4.10 CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM SURVEILLANCE 107 4.11 PENETRATION ROOM VENTILATION SYSTEM SURVEILLANCE 109 4.12 HYDROGEN PURGE SYSTEM SURVEILLANCE 109b d.13 EMERGENCY COOLING POND 110a 4.14 RADI0 ACTIVE MATERIALS SOURCES SURVEILLANCE 110b 4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH ENERGY LINES OUTSIDE OF CONTAINMENT 110c 4.16 SPECIAL SURVEILLANCE 110e 4.17 FUEL HANDLING AREA VENTILATION SYSTEM SURVEILLANCE 110f l
- 5. DESIGN FENIURES 111 5.1 SITE 111 ,
5.2 REACTOR BUILDING 112 5.3 REACTOR 114 5.4 NEW AND SPENT FUEL STORAGE FACILITIES 116
- 6. ADMINISTRATIVE CONTROLS 117 -l 6.1 RESPONSIBILITY 117 6.2 PLANT STAFF ORGANIZATION 117 6.3 QUALIFICATIONS 118
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6.4 REVIEW AND AUDIT 121 6.5 ACTION TO BE TAKEN IN '111E EVENT OF AN ABNORMAL OCCURRENCE 127 6.6 ACTION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED 128 6.7 PLANT OPERATING PROCEDURES 129 6.8 RADIATION AND RESPIRATORY PROTECTION PROGRMI 130 6.9 EMERGENCY PLANNING 136 6.10 INDUSTRIAL SECURITY PROGRMI 137 6.11 RECORDS RETENTION 138 6.12 PLANT REPORTING REQUIREMEN'IS 140 l 1
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/*"N ~M inimum volumes (including a 10% safety factor) of 550 ft3 of 8700 ppm boron as boric acid solution in the boric acid addition tank or 16,000 gallons of 2270 ppm boron as boric acid solution in the borated water storage tank (3) will each satisfy this requirement. The speci-fication assures that the two supplies are available whenever the reacter is critical so that a single failure will not prevent boration to a cold condition. The minimum volumes of boric acid solution given~ include the boron necessary to account for xenon decay.
The principal method of adding boren to the primary system is to pump the concentrated boric acid solution (8700 ppm boron, minimum) into the makeup tank using the 25 gpm boric acid pumps. Using only one of the two boric acid pumps, the required volume of boric acid can be injected in less than three hours. The alternate method of addition is to inject boric acid from the borated va+er stcrage tank using the makeup pumps. ,
the required 16,000 gallons of beric acid can be injected in less than two hours using only one of the makeup pumps.
Concentration of boron in the boric acid addition tank may be higher than the concentration which would crystallize at ambient conditions.
For this reason and to assure a flow of boric acid is available 'when needed this tank and its associated piping will be kept 100F above the crystallization temperature for the concentration present. Once in the makeup system, the concentrate is sufficiently well mixed and di-luted so that normal system temperatures assure boric acid solubility.
D REFEREN'CES 5
(1) FSAR, Section 9 1; 9 2 (2) PSAR, Figure 6-2 (3) PSAR, Section 3.3 9
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3.3 E!!ERGENCY CORE COOLING, REACTOR BUILDING COOLING AND REACTOR BUILDING SPRAY SYSTEMS Applicability Applies to the emergency core cooling, reactor building cooling and reactor building spray systems. l Objectivity To define the conditions necessary to assure immediate availability of the -
emergency core cooling, reactor building cooling and reactor building spray l systems.
Specification 3.3.1 The following equipment shall be operable whenever containment integrity is established as required by Specification 3.6.1:
(A) One reactor building spray pump and its associated spray nozzle header.
(D) TWo reactor building cooling fans and associated cooling units.
(C) Two out of three service water pumps shall be operable, powered from independent essential buses, to provide re-dundant and independent flow paths.
(D) Two engineered safety feature actuated low pressure injection !
pumps shall be operable.
l (ii) Both low pressure injection coolers and their cooling water supplies shall be operable.
(F) Two BWST level instrument channels shall be operable. .
(G) The borated water storage tank shall contain a minimum level -
of 35.9 feet (350,000 gallons) of water having a minimum ;
concentration of 2270 ppm boron at a temperature not less than '
40F. The manual valve on the discharge line from the borated water storage tank shall be locked open.
(11) The four reactor building emergency sump isolation valves to the LPI system shall be either manually or remote-manually operable.
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s (I) The engineered safety features valves associated with each of the above systems shall be operable or locked in the ES position.
3.3.2 In addition to 3.3.1 above, the following ECCS equipment shall be operable when the reactor coolant system is above 350F and irradi-ated fuel is in the core:
(A) Two out of three high pressure injection (makeup) pumps shall be maintained operable, powered from independent essential busses, to provide redundant and independent flow paths.
(B) Engineered safety features valves associated with 3.3.2.a above shall be operable or locked in the ES position.
3.3.3 In addition to 3.3.1 and 3.3.2 above, the following ECCS equipment shall be operabic when the reactor coolant system is above 800 psig:
(A) The two core flooding tanks shall each contain an indicated minimum of 13 + 0.4 feet (1040 + 30 ft3 ) of borated water at 600 + 25 psig.- -
(B) Core flooding tank boron concentration shall not be less than 2270 ppm boron.
(C) The electrically operated discharge valves from the core flood tanks shall be open and breakers locked open and tagged.
(D) One of the two pressure instrument channels and one of the two level instrument channels per core flood tank shall be operable.
3.3.4 The reactor shall not be made critical unless the following equipment ~
in addition to 3.3.1, 3.3.2, and 3.3.3 above is operable.
(A) Two reactor building spray pumps and their associated spray nozzle headers and four reactor building emergency cooling fans and associated cooling units. ,
(B) The sodium thiosulfate tank shall contain an indicated 31 ft of 30 wt% solution sodium thiosulfate (37,500 lb). The sodium hydroxide tank shall contain an indicated 31 ft. of 20 wt%
solution sodium hydroxiJe (20,500 lb.) .
(C) All man';al valves in the main discharge lines of the sodium l thiosulfate and sodium hydroxide tanks shall be locked open. )
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(D) Engineered safety feature valves and interlocks associated '
with 3.3.1, 3.3.2, and 3.3.3 shall be operable or locked in the ES position.
3.3.5 Maintenance shall be allowed during power operation on any component (s) -
in the high pressure injection, low pressure injection, service water, i reactor building spray and reactor building cooling l 37 i
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,. systems which will not remove more than one train of each l
. system from service. . Maintenance shall not be performed on
~ components which would make the affected systen train inoperable for w re than 24 consective hours. Prior to initiating main-tenr.ce on any component _of a train in any system, the redundant coLponent of that_ system shall be demonstrated to be operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the maintenance.
3.3.6 If the conditions of Specifications .3.1 3.3.2, 3.3.3, 3.3 3.3.5 cannot be met except as note - shu down shall be initiated and the reactor s e in hot shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, and, if not corrected, in cold shutdown condition within an additional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
3.3.7 Exceptions to '3.3.6 shall be as follows: -
(A) If the conditions of Specification 3.3.1(F) cannot be met, reactor operation is permissible only during the succeeding l f
seven days unless such components are sooner made operable, provided that during such seven days' the other BWST level instrument channel shall be operable.
(E) If the conditions of Specification 3.3.3(D) cannot be met, reactor operation is permissible only during the succeeding
[ seven days unless such components are sooner made operable, provided that during such seven days the other CFT instrument channel (pressure of level) shall be operable.
Bases The requirements of Specification 3.3.1 assure that below 350F, adequate long term core cooling is provided. TWo low pressure injection pumps are ~
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specified, llowever,' only one is necessary to supply emergency coolant to
} the reactor in the event of a loss-of-coolant accident.
The post-accident reactor building cooling and long-term pressure reduction -
may be accomplished by four cooling units, by two spray units or by a combi-nation of two cooling units and one spray unit. Post-accident iodine removal-may be accomplished by one of the two' spray system strings. The specified' requirenents assure that the required post-accident components are available for both reactor building cooling and iodine removal. Specification 3.3.1 assures that the required equipment is operational.
'Mie borated water storage tank is used for three purposes:
(A) As a supply of borated water for accident conditions.
(B)' As a alternate supply of borated water for reaching cold shutdown. (2)
(C) As a supply-of borated water for. flooding the fuel transfer' ~
, - canal _ during refueling operation. (3)
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'60,000 gallons of borated water are :i.pp]ied for emergoney core cooling and rc actor building spray in the event of a lons-of-coolant accident. This f unnunt fulfills requirements for en. err"ncy core cooling. 16,000 gallonn of borated water are required to reach cold shutdown. The borated water storage tank capacity of 380,000 gallonn is based on refueling volume requirements.
llenters caintain the borated water supply at a tcmperature to prevent crystal-lization and local freezing of the boric acid. The boron concentration is set at a value that vill maintain the core at least 1 percent.ok/k suberitical at 700 F vithout any control rods in the core. The c'oncentration for 1% ok/k suberiticality is 1609 ppm boron in the core, while the minimum value speci-fied in the borated water storage tank is 2270 ppm boron.
Specification 3.3.2 assures that above 350 F two high pressure injection pumps are also available to provide injection water as the ene"gy of the reactor coolant system is increased.
Specification 3.3.3 assures that above 800 psig both core flooding tanks .
are operational. Since their design pressure is 600 + 25 psig, they are not brought into the operational state until 800 psig to prevent spurious in-jection of borated water. Both core flooding tanks are specified as a single core flood tank has insufficient inventory to reflood the core.(A.l Specification 3.3.h assures that prior to Soing critical the redundant reactor building cooling unit and spray are operational.
The spray system utilizen common suction lines with the lov pressure injection system. If a single train of equipment is removed from either system, the
{P5 other train must be assured to be operable in each system.
When the reactor is critical, maintenance is allowed per Specification 3.3.5. !
Operability of the specified components shall be based on the results of testing as required by Technical Specification 4.5. The maintenance period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is acceptable if the operability of equipment redundant to that removed from service is demonstrated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to removal. 2 Exceptions to Specification 3.3.6 permit continued operation for seven days if one of two BWST level instrument channels is operable or if either the pressure or level instrument channel in the CFT instrument channel is operable. l ,
In the event that the need for emergency core cooling should occur, function-ing of one train (one high pressure injection pu=p, one low pressure injec-tion pump, and both core ficodin6 tanks) vill protect the core and in the event c'.' a main coolant loop severence, limit the peak clad temperature to lesa than 23000 F and the metal-water reaction to that representing less than 1 percent of the clad.
The service water ryntom consists of two independent but interconnectcc, full capacity, 100% redundant systemn, to ensure continuous heat removal.( )
1 One service water pump is required for normal operation. ite normal operating )
requirements are greater than the c=ergency requirements following a loss-of-coolant accident.
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l REFERENCES (1) FSAR, Section 14.2.S (2) FSAR, Section 3.2 (3) FSAR, Section 9.5.2 (4) FSAR, Section 9.3.1 e
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, T 3.8.10 he reactor building purge isolation system, including the radiation monitors shall be tested and verified to be operable within 7 days l prior to refueling operations.
3.8.11 Irradiated fuel shall not be removed from the reactor until the unit has been suberitical for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
3.8.12 All fuel handling in the Auxiliary Building shall cease upon notifi-cation of the issuance of a tornada watch for Pope, Yell, Johnson, or Logan counties in Arkansas. Fuel handling operations in progress will be completed to the extent necessary to place the fuel handling bridge and crane in their normal parked and locked position.
3.8.13 No loaded spent fuel shipping cask shall be carried above or into the Auxiliary Building equipment shaft unless atmospheric dispersion conditions are equal to or better than those produced by Pasquill type D stability accompanied by a wind velocity of 2 m/sec. In addi-tion, the railroad spur door of the Turbine Building shall be closed and the fuel handling area ventilation system shall be in operation.
Bases Detailed written procedures will be available for use by refueling personnel.
These procedures, the above specifications, and the design of the fuel handl-ing equipment as described in Section 9.7 of the FSAR incorporating built-in interlocks and safety features, provide assurance that no incident could occur during the refueling operations that would result in a hazard to public health and safety. If no change is being made in core geometry, one flux monitor is sufficient. Eis permits maintenance on the instrumentation. Continuous mon-itoring of radiation levels and neutron flux provides immediate indication of an unsafe condition. ne form boron concentration.(jgcay > heat removal pump is used to maintain a uni-The shutdown margin indicated in Specification 3.8.4 from thewillcore.(2 keep )the core suberitical, even with all control rods withdrawn ne boron concentration will be maintained above 1800 ppm.
Although this concentration is sufficient to maintain the core keff f,0.99 if all the control rods' were removed from the core, only a few control rods will '
be removed at any one time during fuel shuffling and replacement. The keff i with all rods in the core and with refueling boron concentration is approxi-mately 0.9. Specification 3.8.5 allows the control room operator to inform l
i the reactor building personnel of any impending unsafe condition detected .
from the main control board indicators during fuel movement.
The specification requiring testing reactor building purge termination is to verify that these components will function as required should a fuel handling accident occur which resulted in the release of significant fission products.
Because of physical dimensions of the fuel bridges, it is physically impossible for fuel assemblies to be within 10 feet of each other while being handled.
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'N Speciricat, ion '3.10 I is required au t.he ' safety analysic for the fuel handling F
accident yas based on the assumption that the reactor had been shutdown for
'72. hours t3)
' REFERENCES (1)-'FCAR,Section.9.5 '
(2) FSAR,.Section 1h.2.2.3 (3) FSAR, Section 1h.2.2.3.3 -
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S 3.9 CONTit0L ROOM liHliRGliNCY Allt CONDITIONING SYSTEM Applic.tbility Applies to the operability of the control room emergancy air conditioning system.
Objective To ensure that the control room emergency air conditioning system will perform within acceptable levcis of efficiency and reliability.
Specification 3.9.1 TWo independent circuits of the control room emergency air condi- -
tioning system shall be operable whenever reactor building integrity is required with the following performance capabilities:
- a. The results of the in-place cold DOP and halogenated hydrocarbon tests at design flow (t 10%) on HEPA filters and charcoal adsor-ber banks shall show > 99% DOP removal and > 99% halogenated hydrocarbon removal.
- b. We results of laboratory carbon sample analysis from the char-coal adsorber banks shall show > 90% radioactive methyl iodide removal at a velocity within + 20% of system design, 0.05 to 0.15 mg/m3 inlet iodide concentration, > 95% R. H. and > 125F.
- c. Fans shall be shown to operate within + 10% of design flow.
- d. The pressure drop across the combined HEPA filters and charcoal adsorber banks shall be less than 6 inches of water at system design flow rate (t 10%).
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One circuit of the system shall be capable of automatic initiation.
3.9.2 If one circuit of the control room emergency air conditioning system is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding seven days provided that during such seven days all active components of the other circuit shall be operable.
3.9.3 If the requirements of Specifications 3.9.1 and 3.9.2 cannot be met the reactor shall be placed in the cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Bases The control room emergency air conditioning system is designed to filter the control room atmosphere during control room isolation conditions.
One circuit is designed to automatically start upon control room isolation and the other circuit to be manually started on failure of the first circuit.
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', 3 99% DOP removal and >
99% halogenated hydrocarbon removal? -
- b. The results of laboratory carbon sample analysis from the charcoal adsorber banks shall show > 90% radioactive methyl
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iodide removal at a velocity within + 20% of system design, 0.15 to 0.5 mg/m3 inlet methyl iodide concentration, > 95%
R.ll, and > 190F. ,
- c. Fans shall be shown to operate within + 10% of design flow.
- d. The pressure drop across the combined HEPA filters and char-coal adsorber banks shall be less than 6 inches of water at system design flow rate (+ 10%) .
- c. Air distribution shall be uniform within + 20% across HEPA filters and charcoal adsorbers. -
3.13.2 If one circuit of the penetration room ventilation system is made or found to be inoperable for any reason, reactor opera-tion is permissible only during the succeeding seven days pro-vided that during such seven days all active components sf the other daily.
circuit shall be operable and shall be demonstrated operable 3.13.3 If the requirements of Specifications 3.13.1 and 3.13.2 cannot be met, the reactor shall be placed in the cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. ,
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Bases The penetration roon ventilation system is designed to collect and process potential reactor building penetration leakage to mininize environmental activity levels resulting from post accident reactor building leaks. The system consists of sealed penetration rooms, two redundant filter trains and two redundant fans discharging to the unit vent. The entire system is activated by a reactor building engi-neered safety features signal and initially requires no operator action.
Each filter train is constructed with a prefilter, a HEPA filter and a charcoal adsorber in series. The design flow rate through each of these filters is 2000 scfm, which is significantly higher than the 1.25 scfm maximum leakage rate from the reactor building at a leak rate of 0.1%
per day. -
High efficiency particulate air (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential release of radio-iodine to the environment. The in-place test results should indicate a system leak tightness of less than 1 percent bypass leakage for the char-coal adsorbers and a HEPA efficiency of at least 99 percent removal of DOP particulates. The laboratory carbon sample test results should indicate a radioactive uethyl iodide removal efficiency of at least 90 percent for expected accident conditions. If the efficiencies of the HEPA filters and charcoal adsorbers are as specified, the resulting doses will be less than the 10CFR100 guidelines for the accidents analyzed. Operation of the fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.
If one circuit of the penetration room ventilation system is found to be inoperable, there is not an immediate threat to the containment system perfonaance and reactor operation may continue for a limited period of time while repairs are being made.
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b 3.14 HYDROGEN PURGE SYSTEM Applicability Applies to the operating status of the hydrogen purge system.
Objective To ensure that the hydrogen purge system will perform within acceptable levels of efficiency and reliability.
Specification 3.14.1 Two independent circuits of the hydrogen purge system shall be operable whenever reactor building integrity is required with the following performance capabilities: -
- b. The results of laboratory carbon sample analysis shall show
> 90% radioactive methyl iodide removal at a velocity within
[ 20% of system design, 0.05 to 0.15 mg/m 3 inlet methyl iodide concentration, > 95% R.11. and > 190F.
- c. Fans shall be shown to operate within 110% design flow.
- d. The pressure drop across the combined HEPA filters and charcoal adsorber banks shall be less than 6 inches of water at system design flow rate (+ 10%) .
- e. Air distribution shall be uniform within + 20% across HEPA filters and charcoal adsorbers.
- f. Each system inlet heater shall be shown to operate at rated '
power.
3.14.2 If one circuit of the hydrogen purge system is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding thirty days provided that during such thirty days all active components of the other circuit shall be operable and shall be demonstrated operable every seven days.
3.14.3 If the requirements of Specifications 3.14.1 and 3.14.2 cannot be met, the reactor shall be placed in the cold shutdown con-dition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Bases The hydrogen purge system is designed to operate as necessary to limit the hydrogen cm.contration in the reactor building following an accident.
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n The system is composed of two redundant, 100% capacity, supply circuits and two redundant, 100% capacity, exhaust circuits. Each supply circuit consists of a blower, prefilter and associated piping and valves. Each exhaust circuit consists of a blower, HEPA filter and charcoal filter, dehumidifier, flowmeter, sample connection and associated piping and valves.
The blower is a rotary positive type. The dehumidifier consists of two redundant heating elements inserted in a sectioq of ventilation duct.
The function of the dehumidifier is to sufficiently increase the temper-ature of the entering air to assure 70 porcent relative humidity entering the filter train with 100 percent saturated air entering the dehumidifier.
The purpose of the dehumidifier is to assure optimum charcoal filter effici-ency. lleating element control is provided by a thermoswitch. Humidity indication is provided downstream of the heating elements by a humidity -
readout gage. The filter train provides prefiltration, high efficiency particulate filtration and iodine filtration. Face velocity to the char-coal adsorber is low. The charcoal adsorber is composed of a module con-sisting of two inch deep double tray carbon cells. Both the purge flow to the unit vent and the purge sample flow are metered using rotometers.
Both of these rotometers have an accuracy of + two percent of full scale, and each has remote readout capability. The purge sample activities can be collected, counted and analyzed in the radio-chemistry laboratory.
The in-place test results should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99 percent removal of DOP particulates. The labor-atory carbon sample test results should indicate a radioactive methyl iodide removal efficiency of at least 90 percent for expected accident conditions.
If the efficiencies of the HEPA filters and charcoal adsorbers are as specified, the resulting doses will be less than the 10CFR100 guide-1enes for the accidents analyzed. Operation of the fans significantly dif-ferent from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.
If one circuit of the penetration room ventilation system is found to be inoperable, therr s not an immediate threat to the containment system -
performance and reactor operation may continue for a limited period of time while repairs are being made.
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o 3.15 IUEL liANDLING AREA VENTILATION SYSTEM Applicability Applies to the operability of the fuel handling area ventilation system.
Objective To ensure that the fuel handling area ventilation system will perform within acceptable levels of efficiency and reliability.
Specification 3.15.1 The fuel handling area ventilation system shall be operable whenever irradiated fuel handling operations are in progress -
in the fuel handling area of the auxiliary building and shall have the following performance capabilities:
- b. The results of laboratory carbon sample analysis shall show
> 90% radioactive methyl iodide removal at a velocity within J_20% of system design, 0.05 to 0.15 mg/m3 inlet methyl iodide cenration, > 95% R.11. and > 125F.
- c. Fans shall be shown to operate within + 10% design flow.
- d. The pressure drop across the combined HEPA filters and char-coal adsorber banks shall be less than 6 inches of water at system design flow rate (+ 10%).
- e. Air distribution shall be uniform within + 20% across HEPA
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filters and charcoal adsorbers. -
3.15.2 If the requirements of Specification 3.15.1 cannot be met irradiated fuel movement shall not be started (any irradiated fuel assembly movement in progress may be completed).
Bases The fuel handling area ventilation system is designed to filter the auxiliary building atmosphere during fuel handling operations to limit the release of activity should a fuel handling accident occur.
The system consists of one circuit containing two exhaust fans and a filter train. The fans are redundant and only one is required to be operable. The filter train consists of a prefilter, a HEPA filter and a charcoal adsorber in series.
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liinh officiency particulate ai r (IIEPA) filters are installed before the charcoal adsorbers to preve ', clogging oi' the iodine adsorbers.
The charcoal adsorbers are i ,,alled to reduce the potential release of radioiodine to the environment. The in-place test results should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99 percent removal of DOP particulates. The laboratory carbon sample test results should indicate a radioactive methyl iodide removal efficiency of at least 90 percent for expected accident conditions. If the efficiencies of the llEPA filters and charcoal adsorbers are as specified, the resulting doses will be less than the 10CFR100 guidelines for the accidents analyzed.
Operation of the fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal ad-sorbers.
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Tcbic 4.1-2 Minimum Equipmcat Test Frequency p'
V Item Test Frequency
- 1. Control Rods kod Drop Times of All Each Refueling Shutdown Full Length Rods 1/
- 2. Control Rod Movement Movement of Each Rod Every Two riceks Above Cold Shutdown Conditions
- 3. Pressuri:cr Code Setpoint Safety Valves One Within 2 Necks Prior to or Follouing Each aefueling Shutdown '
4 Main Steam Safety Sotpoint Four tlithin 2 Necks Prior Valves to or Following Each Refueling Shutdown
- 5. Refueling System Functioning ~
Interlocks Start of Each Refueling Shutdown
- 6. Reactor Coolant Evaluate System Leakage Daily
- 7. Deleted O
- 8. Reactor Building Functioning Isolation Trip Each Refueling Shutdown --
- 9. Service Water Functioning Systems Each Refueling Shutdown
- 10. Spent Fuel Cooling Functioning System Each Refueling Shutdown Prior to Use
- 11. Decay llcat Removal Functioning System Isolation Each Refueling Shutdoun Valve Automatic Prior to Repressurization at a pressure greater than Closure and Isolation 30n psig but less than 420 2 System psig.
1/ Sanc as tests listed in section 4.7 : i
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.Py The liner plate surveillance is based on the requirement to monitor the liner plate performance as a membrane to preserve the required leak A
tightness of the reactor building.
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4.5 !!HliRGE!1CY CORil C001,ING SYSTl!M AND itEAC'IOR BUILDING COOLING SYSTEM PF.RIODIC Tl! STING 4.5.1 Emergency Core Cooling Systems Applicability Applies to periodic testing requirement for emergency core cooling systems.
Objective To verify that the energency core cooling systems are operable.
Specification 4.5.1.1 System Tests 4.5.1.1.1 liigh Pressure Injection System -
(a) During each refu111ng period, a system test shall be conducted to demonstrate that the system is operable. A test signal will be applied to demonstrate actuation of the high pressure inject-ion system for emergency core cooling operation.
(b) The test will be considered satisfactory if control board indie4 tion 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) During each refueling period, a system test shall be conducted to demonstrate that the system is operable. The test shall be performed in accordance with the procedure sunmarized below:
(1) A test signal will be applied to demonstrate actuation of the '
low pressure injection system for emergency core cooling operation.
(2) Verification of the 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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Two service water pumps are normally operating. At least once per month operation of one pump is shifted to the third pump, so testing vill be unnecessary.
The reactor building fans are normally operating, so testing is unnecessary.
Reference FSAR, Secticn 6 D
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4.6 AUXILIARY ELECTRICAL SYSTEM TESTS ~~'
Applicability !
I Applies to the periodic testing and surveillance requirements of the auxiliary when electrical system to ensure it will respond promptly and properly 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 during each refueling outage to demonstrate 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 pcwer.
The diesel generator chall be fully loaded and run for one hour ~
after operating temperatures have stabilized.
3.
Each diesel generator shall be given an inspection at least every refueling outage following the manufacture's recommendations for this class of standby service. The above tests will be considered satisfactory if all applicable equipment operates as designed.
4.
During the monthly diesel generator test specified in Paragraph 1 above, the diesel starting air compressors shall air checked be receivers.for operation and their ability to recharge the Also monthly, the diesel oil transfer pumps shall be checked for operation and their ability to transfer oil to the day tank. '
5.
During each refueling outage, the capability of each starting air compressor to charge the 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 at each refueling outage, the capacity of each diesel oil transfer pump shall be verified to be at least 10 gpm. N 100
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m 4.10 CONTROL R00tl EMERGENCY AIR CONDITIONING SYSTB1 SURVEILLANCE Applicability Applies to the surveillance of the control room energency air condition-ing system.
Objective To verify an acceptable level of efficiency and operability of the control room emergency air conditioning system. (
Specification 4.10.1 At least once per refueling period (not to exceed 18 months), -
the pressure drop across the combined HEPA filters and charcoal adsorber banks shall be demonstrated to be less than 6 inches of water at system design flow (+ 10%) .
4.10.2 At least once per refueling period (not to exceed 18 months) automatic initiation of the control room emergency air condi-tioning system shall be denonstrated.
4.10.3.a The tests and sample analysis of Specification 3.9.1 shall be performed initially and at least once per refueling period (not to exceed 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 ventilation zone communicating with the system.
- c. Italogenated hydrocarbon testing shall also be performed after 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 and gaseous fission products to which the control area would be subj ected 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 profilter, 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, 107
4.10 CONTROL R00f! EMERGENCY AIR CONDITIONING SYSTEtt SURVEILLANCE Applicability Applies to the surveillance of the control room energency air condition-ing system.
Objective To verify an acceptable level of efficiency and operability of the control room emergency air conditioning system.
Specification 4.10.1 At least once per refucting period (not to exceed 18 months),
the pressure drop across the combined HEPA filters and charcoal adsorber banks shall be demonstrated to be less than 6 inches of water at system design flow (+ 10%) .
4.10.2 At least once per refueling period (not to exceed 18 months) automatic initiation of the control room emergency air condi-tioning system shall be demonstrated.
4.10.3.a The tests and sample analysis of Specification 3.9.1 shall be per nitially and at least once per refueling period (r , exceed 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 ventilation zone communicating with the system,
- c. Italogenated hydrocarbon testing shall also be performed after 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 l
The purpose of the control room filtering system is to limit the particulate
! 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, 107
adesive deterioration in the ifEPA units; and unusual or excessive noise or vibration when the fan motor is running. Pressure drop across the com-bined !! EPA 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 should be determined at least once per operating cycle to show system perfomance capability.
He frequency of tests and sample analysis are necessary to show that the
!! EPA filters and charcoal adsorbers can perform as evaluated. The charcoal adsorber efficiency test procedures should allow for obtaining at least two sampics. 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 DOP aerosol shall be perfomed in accordance with ANSI N510 (1975) " Stan-dard for Testing of Nuclear Air Cleaning Systems." Any HEPA filters found defective shall be replaced with filters qualified acconting 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 adsorbent qualified according to nogulatory Guide 1.52.
Operation of the system for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> every month will demonstrate operability of the filters and adsorber system. All dampers and other fichmdal and isolation systens will be shown to be operable.
If significant painting, fire or chemical release occurs uch that the HEPA filter or charcoal adsorber could becew contaminated from the fumes, chemi-cals or foreign material, ti.e saac tests and sample analysis shall bcs per-fomed as required for operational use. He determination of significant shall be made by the operator on duty at the time of the acident. Know-ledgeable staff members should be e:casulted prior to maki.p. this determina-tion.
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4.11 PENETRATION ROOH 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 At least once per refueling period (not to exceed 18 months) the following conditions shall be denonstrated:
- a. The 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 uniform within + 20% across HEPA filters and
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charcoal adsorbers.
4.11.2a. The tests and sample analysis of Specification 3.13.la. G b. shall be performed initially and at least once per refueling period (not to exceed 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 ventilation zone communicating with the system.
- c. Italogenated hydrocarbon testing shall also be performed after each complete or partial replacement of the charcoal adsorber bank or after any structural maintenance on the system housing.
4.11.3 Each circuit shall be operated at least I hour every month.
This test shall be considered satisfactory if control board indication verifies that all components have responded properly to the actu-ation signal.
Bases The penetration room ventilation systen is designed to collect and process potential reactor building penetration room leakage to minimize environ-mental activity levels resulting from post accident reactor building leakt.
The system consists of a scaled penetration room, two redundant filter trains and two redundant fans discharging to the unit vent. The entire system is activated by a reactor building pressure engineered safety features signal and initially requires no operator action.
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Since the system is not normally operated, a periodic test is required to show that the system is available for its engineered safety features func-tion. During this test the system will be inspected for such things as water, oil, or other foreign material, gasket deterioration in the HEPA units, and unusual or excessive noise or vibration when the fan motor is nmning.
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 at 1 cast once per operating cycle to show system performance capability.
He frequency of tests and sample analysis are necessary to shes that the IIEPA filters and charcoal adsorbers can perform as evaluated. We 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 halo-genated hydrocarbon refrigerant and of the HEPA filter bank with DOP aemsol shall be perfomed 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 perfomed 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.
Operation of the system each month for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> will demonstrate operability of the active system components and the filter and adsorber system. If significant painting, fire or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemicals or foreign aaterial, .the same tests and sample analysis shall be perfomed as required for operational use. We determination of significant shall be made by the operator on duty at the time of the incident. Knowledge-able staff members Gould be consulted prior to making this determination, i
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4.12 IlYDORGl!N PilRGE SYS'iliH SURVE1LLANCE 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 At least once per refueling period (not to exceed 18 months) the following conditions shall be demonstrated:
- a. We 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 uniform within + 20% across HEPA filters and charcoal adsorbers.
- c. Each system inlet heater unit operates at rated power.
4.12.2.a. We tests and sample analysis of Specification 3.14.1.a 6 b,
- shall be perfomed initially and at least once per refueling period (not to exceed 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 ventilation zone communicating with the system. !
- 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 circuit 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 Ilydrogen concentration instruments shall be calibrated at least once per refueling period (not to exceed 18 months) with proper consideration to moisture effect.
B^s cs, Since the hydrogen purge system is not normally operated, a periodic test is required to show that the system is available for hydrogen control following an accident. During this test the system will be inspected for such things as water, oil, or other foreign material, gasket deterioration !
in the HEPA units, and unusual or excessive noise or vibration when the fan motor is running.
109b l i
. . . , ^3 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 at least once per operating cycle 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 1 cast 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.
Operation of the hydrogen purge system each month for at least ten (10) hours will demonstrate operability of the filters and adsorber system including the heater and remove excessive moisture built up on the adsorber.
If significant painting, fire or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemi-cals or foreign material, the same tests and sample analysis shall be performed as required for operational use. The determination of significant shall be made by the operator on duty at the time of the incident. Knowledgeable staff members should be consulted prior to making this determination.
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y ,m 4.17 ITEL llANDLING AR!iA Vi!Nf1LATION SYSTEff SURVEILLANCE Applicability Applies to the surveillance of the fuel handling area ventilation system.
Objective To verify an acceptable level of efficiency and operability of the fuel handling area ventilation system.
Specification 4.17.1 At least once per refueling period the following conditions shall be demonstrated:
- a. Pressure drop across the combined HEPA filters and charcoal adsorber flow rate, banks is less than 6 inches of water at system design b.
- Air distribution is uniform within + 20% across HEPA filters and
-~
charcoal adsorbers.
4.17.2 The tests and sample analysis of Specification 3.15.1.a G b. shall be performed within 720 sy, tem operating hours prior to irradiated fuel handling operations in the auxiliary building.
4.17.3 The systeo shall 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.
Bases Since the fuel handling area ventilation system may be in operation when fuel is stored before in the pool handling but not being of irradiated fuel. handled its operability must be verified.
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 jerations and performance of Specification 4.17.2 will demonstrate operability of the active system components and the filter and adsorber systens.
Pressure drop across the combined llEPA 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 at least once per :
refueling period to show systcu performance capability.
{
The frequency of tests and sample analysis are necessary to show that the i HEPA filters and charcoal adsorbers can perform as evaluated. The charcoal l 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 110f l
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. a equal to the thickness of the bed. Tests of the charcoal adsorbers with halogenated hydrocarbon refrigerant and of the HEPA filter bank with DOP acrosol 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 efficency tests shall be perfonned in accordance with RDT Standard M16-IT. If laboratory test results are unaccept,able, all charcoal adsorbents in the system shall be replaced with charcoal adsorbents qualified according to f!egulatory Guide 1.52.
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