ML19326C033
| ML19326C033 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/01/1977 |
| From: | Desiree Davis Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19326C029 | List: |
| References | |
| NUDOCS 8004180715 | |
| Download: ML19326C033 (28) | |
Text
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE - UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 25 License No. DPR-51 1.
The Nu,isar Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Arkansas Power & Light Company (the licensee) dated Septerrser 30, 1976, complies with the standards and requirements of the f.;0mic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
j 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.c(2) of Facility Operating License No. DPR-51 is hereby amended to read as follows:
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. (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 25, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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, cDon K. Davis, Acting Chief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: ~ June 1, 1977 a
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ATTACHMENT TO LICENSE AMEN 0 MENT N0. 25 FACILITY OPERATING LICENSE NO. OpR-51 DOCKET NO. 50-313 Change the Appendix A portion of the Technical Specifications to add the following reyised pages.
The chasi ed.. areas an,the' J
revised pages are identified by marginal lines.
Pages 1*
2 67 68 72a 73 73a 83 92 93 94*
95 96*
100 100a 101 105 106*
107
.109 109a 109b 110 110h 1101
- There were no changes on these pages. They are included as a matter of convenience in updating the Technical Specifications.
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l DEFINITIONS The following terms are defined for unifom interpretation of these specifi-cations.
1.1 RATED POWER Rated power is a steady state reactor core output of 2568 wt.
1.2 REACTOR OPERATING CONDITIONS 1.2.1 Cold Shutdown The reactor is in the cold shutdown condition when it is suberitical by at least 1 percent Ak/k and Tavg is no = ore than 200 F.
Pressure is defined by Specification 3.1.2.
1.2.2 Hot Shutdown The reactor is in the hot shutdevn condition when it is suberitical by at least 1 percent Ak/k and Tavg is at or greater than 525 F.
1.2 3 Reactor Critical The reactor is critical when the neutren chain reaction is self-sustaining and Kerr = 1.0.
1. 2. 14 Hot Standby-The reactor is in the hot standby condition when all of the following condi-tions exist:
A.
Tavg is greater than 525 F.
B.
The reactor is critical.
C.
Indicated neutron power on the power range channels is loss than 2 percent of rated power.
1.2 5 Power Operation The reactor is in a power operating condition when the indicated neutron power is above 2 percent of rated power as indicated on the pcVer range channels.
1.2.6 Refueling Shutdown The reactor is in the refueling shutdown condition when, even with all rods removed, the reactor vould be suberitical by at least 1 percent ak/k and the coolant tenperature at the decay heat removal pu=p suction is at the Amendment No. 25 1
3
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 Refueling Operation An operation involving a change in core geometry by manipulation of fuel or control rods when the reactor vessel head is removed.
1.2.8
- Startug, 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 cperable when it.is capable of performing its intended function within the required range. The component or system shall be consid-ered 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 in instrument channel is the combination of sensor, wires, amplifiers and output devices which are connected for the purpose of measuring the value of a process variable for the purpose of observation, 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 p
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.
Amendment No. 25
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4 SURVEILLANCE STANDARDS Specified surveillance intervals may be adjusted plus or minus 25 percent to accommodate normal test and surveillance schedules. The maximum combined interval for any 3 consecutive tests shall not exceed 3.25 times the specified surveillance interval. Surveillance retuirements are not applicable when the plant operating conditions are below those requiring operability of the designated component. However, the required surveillance must be performed prior to reaching the operating conditions requiring operability. For example, instrumentation requiring twice per week surveillance when the reactor is critical need not have the required surveillance when the reactor is shutdown.
h.1 OPERATIONAL SAFEIT ITEMS Applicability Applies to items directly related to safety limits and limiting conditions for operation.
Objective To specify the =inimum frequency and type of surveillance to be applied to unit equip =ent and conditiens.
Specification a.
The minimum frequency and type of surveillance required for reactor protective system and engineered safeguards system instrumentation when the reactor is critical shall be as stated in Table 4.1-1.
b.
Equipment and sa=pling test shall be perfor=ed as detailed in Tables h.1-2 and 4.1-3 c.
D'iscrepancies noted during surveillance testing vill be corrected and recorded.
d.
A power distribution =ap shall be made to verify the expected power distribution at pericdic intervals at least every 10 effective i
full power days using the incore instrumentation detector system.
Bases Check Failures such as blevn instrument fuses, defective indicators, faulted ampli-fiers which result in " upscale" or "downscale" indication can be easily ree-ognized by simple observation of the functioning of an instru=ent or system.
Futhermore, such failures are, in =any cases, revealed by alarm or annun-cistor action. Comparison of output and/or state of independent channels measuring the same variable supplements this type of built-in surveillance.
Based on experience in operation of both conventional and nuclear plant sys-tems, when the plant is in operation, the minimu= checking frequency stated is deemed adequate for reactor system instrumentation.
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Amendment No. 25 67
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) i 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 undetr ced failure existing within the system and to minimize the likelihoc. 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 Channel C Three Weeks After Startup Channel D Four Weeks After Startup Re reactor protective system instrumentation test cycle is continued with one enannel'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. De trip test checks all logic combinations and is to be performed on a rotational basis. We 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 the equipment and systems to assure safe operation.
REFERENCE FSAR Section 7.1.2.3.4 68 Amendment No. 25
4 Table h.1-1 (cont'd) n Channel Description Check Test Calibrate Rec.a rks s
rt
.e 37 Boric Acid Addition Tank o
to a.
Level Channel NA NA R
un b.
Temperature Channel M
NA R
- 38. Sodium Thiosulfate Tank NA
- A R
Level Indicator 39 Sodiuc Hydroxid. Tank
!!A
- lA R
Level Indicucr 40.
Incor,: Neutror. Detectcrs
( 1 )
- A
- iA (1) Oneck Functienir.6
-4 1.1.
Dr.ergency Plant P.adiation Ej Instruments M(1)
NA E
(1) Battery Check
-12. Deleted h3.
Strong Motion Acceleographs Q(1)
NA Q
(1) attery Check hh.
ESAS Manual Trip Punctions a.
Switches & Logic NA R
NA f
b.
Logic NA NA l
3+5 Reactor Manual Trip NA P
HA 16.
Reactor Lullding 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
!*ot Done Previo.:s '.ieck
Tabic 4.1-2 Minimum Equipment Test Frequency Item Test Frequency 1.
Control Rods Rod Drop Times of All Each Refueling Shutdown Full Length Rods 1/
8 2.
Control Rod Movement Movement of Each Rod Every Two Weeks Above Cold Shutdown Conditions 3.
Pressuri:er Code Setpoint One Valve Every 18 Months Safety Valves 4
Main Steam Safety Setpoint Four Valves Every 18 Months Valves 5.
Refueling System
. x;.ioning 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 Heat Removal Functioning Every 18 Months System Isolation Valve Automatic Closure and Isola-tion System 1/ Same as ' tests listed in Section 4.7 i
l Amendment No. JD, 25 73'
Table 4.1c2 (Continued)
Minimum Ecuipment Test Frequency Item Test Frecuency 12.
Flow Limiting Annulus Verify, at normal One year, two years, on Main Feedwater operating conditions, three years, and every Line 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. Excercise Through
- a. Quarterly Valves Approximately 10%
Travel
- b. Every 18 Months.
- b. Cycle 15.
Main Feedwater
- a. Exercise Through
- a. Quarterly Isolation Valves Approximately 5%
Travel
- b. Cycle
- b. Every 18 Months.
16.
Reactor Internals Demonstrate Operability Each refueling shutdown.
Vent Valves By:
- a. Conducting a remote visual inspection of visually accessible sur-faces of the valve body and disc sealing faces and evaluating any observed surf ace irregu-larities.
- b. Verifying that the valve is not stuck in an open position, and
- c. Verifying through manual actuation that the valve is fully open with a force of 5 400 lbs (applied vertically upward).
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Amendment No. J, W, 25 73a
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4.4.1.2.5 Test Frequency Local leak detection tests shall be performed during each I
reactor shutdown for refueling or other convenient 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 emergency hatch door is opened when reactor building integrity is required, the affected door seal shall be tested.
In addition, a pr:ssure 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 rs:e 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 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 Amendment No.13, 25 83 6
_. - _.. _. _. -. ~ _ _ _ _ _ _. _ _. _ _ _
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4.5 EMERGENCY CORE COOLING SYSTEM AND REACTOR BUILDING COOLING SYSTEM PERIODIC TESTING 4.5.1 Emergency Core Cooling 3ystems 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 operable. A test signal will be applied to demon-strate actuation of the high pressure injection system for energency 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 Inj ection 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 pressure injection system for energency 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.
Amendment No. Ig, 25 92
4.5.1.1.3 Core Flooding System (a) Once every 18 months, a system test shall be condacted 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 4.5.1.2.1 Pumps Approximately quarterly, the high pressure and low pressure in-jection pumps shall be 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 a:cident. The removal of heat from the core pro-vided by these systems is. designed to limit core damage.
The high pressure injection system under normal operating conditions has one
.I 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 l
tank recire line.
This allows water to be pumped from the borated water storage tank through each of the injection lines and back to the tank.
{
Amendment No. 25 93
With the reactor shutdown, the check valves in each core flooding line are checked for operability by reducing the reactor coolant system pressure until the indicated level in the core fJ aod tanks verify that the check valves have opened.
REFU SCI FSAR Section 6 4
Amendment No. '25 N
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s 4.5.2 Reactor Building Cooling Systems Applicability Applies to testing of the reactor building cooling systems.
Objective To verify that the reactor building cooling systems are operable.
Specification 4.5.2.1 System Tests 4.5.2.1.1 Reactor Building Spray System (a) Once every 13 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 no::les).
(b)
Station compressed air or smoke will be introduced into the spray headers to verify the availability of the headers and spray no :les at least every five years.
(c) The test will be considered satisfactory 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 summari:ed below:
(1) A test signal will be applied to actuate the reactor building cooling operation.'
(2) Verification of the engineered safety features function of
~
I the service water system which supplies the reactor building coolers shall be made to demonstrate operability of the coolers.
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Arendment No. 25 95 E
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r (b) The test will be considered satisfactory if control board indication verifies that all components have responded to the actuation signal properly.
k.5.2.2 component Tests k.5.2.2.1 Pumps At intervals not to exceed 3 months the reac+4r buildina; spray pumps shall be started and operated to verify proper operation. Acceptable performance vill be indicated if the ptarp starts, operates for fifteen minutes, and the discharge pressure and flow are within 110% of a point on the pump head curve.
k.5.2.2.2 Valves At intervals not to exceed three months each engineered safety features valve in the reactor building spray and reactor building cooling system and each engineered safety features valve associated with reactor building cooling in the service water syste= shall be tested to verify that it is operable.
Bas es The reactor building cooling system and reactor building spray system are designed to remove the heat in'the reactor building atsosphere to prevent the building pressure from exceeding the design pressure.
The delivery capability of one reactor building spray pump at a time can be tested'by opening the valve in the line from the borated water storage tank, opening the corresponding valve in the test line, and starting the corresponding pu=p.
Pump discharge pressure e.nd flow indication demonstrate performance.
With the pumps shut down and the borated water storage tank outlet closed, the reactor building spray injection valves can each be opened and closed by operator action. With the reactor building spray inlet valves closed, low pressure air or smcke can be blevn through the test connections of the. reactor building spray nossles to demonstrate that the flow paths are open.
The equipment, piping, valves, and instrumentation of the reactor building cooling system are arranged so that they can be visually inspected. The cooling units and associated piping are located outside the secondary concrete shield. Personnel can enter the reactor building during power operations to inspect and maintain this equipment. The service water piping and valves outside the reactor building are inspectable at all times. Operational tests and inspections vill be performed prior to initial startup.
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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 synchroni:ed from the control room and loaded to full rated load and allowed to run until diesel generator operating temperatures have stabili:ed.
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 fully loaded and run for one hour after operating temperatures have stabili:ed.
3.
Each diesel generator shall be given an inspection once every 18 months following the manufacturer's recommendations for this class of standby service.
4.
During the monthly diesel generator test specified in Paragraph 1 above, the following shall be perfo:med:
a.
The diesel generator starting air compressors shall be checked for operation and their ability to recharge the air receivers.
b.
The diesel oil transfer pumps shall be checked for operability and their ability to transfer oil to the day tank.
c.
The day tank fuel level shall be verified.
d.
The emergency storage tank fuel level shall be verified.
Amendment No. J3, 25 100
s Diesel fuel from the emergency storage tank shall be e.
sampled and found to be within acceptable limits speci-fied in Table 1 of ASTM DS75-68 when checked for viscosity, water, and sediment.
5.
Once every 18 months, the capability of each starting air l
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.
4.6.2 Station Batteries and Switchyard Batteries The. voltage, temperature and specific gravity of a pilot cell in 1.
each bank and the overall battery voltage of each bank shall be measured and recorded daily.
2.
Measurements shall be made quarterly of voltage of each cell to the nearest 0.01 volt of the specific gravity of each cell, and 3
of the temperature of every fifth cell in each bank. The level of the electrolyte shall me checked and adjusted as required.
All data, including the amount of water added to any cell, shall be recorded.
3.
Once every 18 months, a performance discharge test shall be conducted in accordance with the manufacturer's instructions, for the purpose of determining battery capacity.
4.
Any battery charger which has not been loaded while connected to its 125V d-c distribution system for at least 30 minutes during every quarter shall be tested and loaded while connected to its bus for 30 minutes. The third battery charger, which is capable of being connected to either of the two 12SV d-c distribution systems, shall be loaded while connected to each bus for at least 30 minutes every quarter.
4.6.3 Emergency Lighting The correct functioning of the emergency lighting system shall be verified once every 18 months.
i Amendment No. k, 25 100s
3ases 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 intervals. 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 be verified by simulated loss-of-power tests once every 18 months.
Considering system redundancy, the specified testing intervals for the station batteries should be adequats to detect and correct any sal-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 equali:ing 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 every 18 months and is subject to review and modification if experience demonstrates a more effective test schedule.
References FSAR, Section 8 Amendment No. JI, 25 101 e
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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 operible.
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 foed-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 all components have operated 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 control 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 si stem. The test is done during shutdown to avoid thermal cycle to the em egency feedwater no::les on the steam generator due to the lower temperature of the emergency feedwater.
Amendment No. 25 los
k.9 REACTIVITY ANOMALIES Applicability Applies to potential reactivity anomalies.
Cbjective To require the evaluation of nactivity anomalies of a specified magnitude occurring during the operation of the unit.
Speci fication Following a normalization of the computed boren concentrs. tion as a function of burnup, the actual boren eencentration of the coolant shall be periodically compared with the predicted value. If the difference between the observed and predicted steady-state concentrations reaches the equivalent of one per-cent in reactivity, an evaluatien of this abnor-nal occurrance vill be made to deter =ine the cause of the discrepancy.
Bases To. eliminate possible errors in the calculations of the initial reactivity of the core and the reactivity depletion rate, the predicted relation between fuel burnup and the boron concentration, necessa:y to maintain adequate con-trol characteristics, must be adjusted (normalized) to accurately reflect actual core conditions. When full pcVer is reached initially, and with the ccatrol rod groups in the desired positiens, the boren concentration is mea-sured and the predicted curve is adjusted to this point. As power operation proceeds, the seasured bcron concentration is compared with.the predicted concentration and the slep of the curve relating' burnup and reactivity is compared with that predicted. This process of normalization should be com-pleted after about 10 percent of the total core burnup. Thereafter, actual boron concentra.. ion can be ecmpared with prediction, and the reactivity status of the core can be continuously evaluated. Any reactivity anomaly greater than 1 percent ak/k would be unexpected, and its occurrence would be thor-oughly investigated and evaluated.
The value of 1 percent ak/k is considered a safe limit since a shutdevn mar-gin of at least 1 percent ak/k with the mest reactive rod in the fully with-drawn position is always saintained.
Amendment No. 25 106
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4.10 CMTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM SURVEILLANCE Applicability Applies - to the surveillance of the control room emergency air conditioning system.
Objective To verify an acceptable level of efficiency and operability of the control room emergency air conditioning system.
Specification l
At intervals not to exceed 18 months, the pressure drop across the combined HEPA filters and charcoal adsorber banks shall be 4.10.1 to be less than 6 inches of water at system design flow (;; 10%).
4.10.2 At intervals not to exceed 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 at intervals 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 folicwing significant painting, fire or chemical release in any ventila-tion :one communicating with the system,
- 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.
- c. Halogenated 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 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 normstly operated, a periodic test is required to
' insure operability when r%yded. During this test the system will be inspected for such things as wate t, 'il, or other foreign material; gasket deterioration, Amendment No. 19, 25 107
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4.'11 PENETRATION ROOM VENTILATION SYSTEM SURVEILLANCE Applicability
- Applies to the surveillance of the penetration room ventilation system.
Objective To verif'y an acceptable level of efficiency and qperability of the pene-tration room ventilation system.
Specification 4.11.1 At intervals 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 rate (+ 10%).
4.11.2 Initially and after any maintenance or testing that cou 4 affect the air distribution within the penetration room ventilation system, air distribution shall be demonstrated to be uniform within +20%
across HEPA filters and charcoal adsorbers.
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4.11.3 At intervals not to exceed 18 months, automatic initiation of the penetration room ventilation system shall be demonstrated.
4.11.4a The tests and sample analysis of Specification 3.13.la, b, 6 c. shall be performed at httervals 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
- one communicating with the system.
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.
c.
Halogenated hydrocarbon testing shall siso be performed after each complete or partial replacement of the charcoal adsorber bank or after any structural maintenance on the system housing.
4.11.5 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.
Amendment No. If, IA, 25 109
e-L Bases ne penetration room ventilation system is de' signed to collect and process potential reactor building ponctration room leslage to minimize environ-mental scrivity levcis resulting from post accident reactor building leaks.
%e 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. -
Sin.:e 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, gaskec deterioration in the HEPA units, and unusual or excessive noise or vibration when the fan motor is zunning.
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 excess.ive amounts of foreign matter. Pressure drop should be determined at least once per 18 months to show system performance capability.
We frequency of tests and sample analysis are necessary to show that the HEPA filters and charcos1 adsorbers can perform as evaluated.
Le 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 aerosol shall be performed in accordance with ANSI N510 (1975) ' Standard for Testing of Nuclear Air C1 caning Systems." Any HEPA. filters found defective shall be replaced with filters qualified according to Regulatory Position C.3.d. of Regulatory Guido 1.52 Radi'oactive methyl iodide removal efficiency tests shall be perfo:=cd in accordance with RDT Standard M16-I.T.
If laboratory test results are unacceptable, all charcoal adsorbents in the system shall be replaced with cliarcoal adsorbents qualified according to Regulatory Guide 1.S2.
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 che=ical release occurs such that the HEPA filter or charcos1 adsorber could become contaminated from the fumes, chemicals or foreign unterial, the same tests and sample analysis shall be performed as required for operational use. n e determination of significant shall be made by the operator en duty at the time of the incident.
Knowledge-able staff members should be consulted prior to making this determination.
109a Amendment No. ) ( g, 25
4.12 IlYDROGEN PURGE SYSTEM SURVEII. LANCE 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 intervals not to exceed 18 months, the following 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, S c. shall be performed at intervals 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 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.
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.
. i 4.12.4 Hydrogen concentration histruments shall be calibrated once every 18 months 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 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.
1 109b Amendment No, y;, 25 i
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 t. tat the filters and adsorbers are not clogged by excessive amounts of foreign matter.
Prt.ssure drop should be determined at least once per 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 perfom as evaluated. De charcoal adsorber efficiency test procedures should allow for obtaining at least two s ahiples. Each sampic 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 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 io'dide 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 etntaminated from the fu=es, chemi-
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cals or foreign material, the same tests and sample analysis shall be peric=ed as required for operational use, ne determination of significant shall be made by the operator en duty at the time of the incident.
Knowledgeable staff members should be consulted prior to making this dete=ination.
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Amendment No. Jg, 25 gio
4.17 FUEL IIANDLING AREA VENTILATION SYSTEM 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 ventialtion system.
Specification 4.17.1 At intervals not to exceed 18 months, 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 rate (+ 10%).
4.17.2 Initially and after any maintenance or testing that could affect the air distribution within the fuel handling area ventilation system, air distribution shall be demonstrated to be uniform within +20% across HEPA filters and charcoal adsorbers.
j 4.17. 3. a.
The tests and sample analysis of Specification 3.15.1.a,b, S c.
shall be performed within 720 system operating hours prior to irradiated fuel handling operations in the auxiliary building, and prior to irradiated 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 auxiliar'y building after each complete or partial replacement of a HEPA filter bank or after any structural maintenance on the system housing.
c.
Halogenated hydrocarbon testing shall also be performed prior to irradiated fuel handling in the auxiliary building after
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each complete or partial replacement of a charcoal adsorber bank or after any structural maintenance on the system housing.
4.17.4 The system 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 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, i
Bases i
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 4.17.3 will demonstrate operability of the active system components and the filter and adsorber systems.
- Amendment No. I6, 13, 25 110h i
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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 una.:ceptable, all charcoal adsorbents in the system shall be replaced with charcoal adsorben,ts qualified according to Regulatory Gu4de 1.52.
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Amendment No. 25 1101 me
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