ML20045H730
| ML20045H730 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 07/07/1993 |
| From: | Chan T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20045H731 | List: |
| References | |
| NUDOCS 9307210191 | |
| Download: ML20045H730 (15) | |
Text
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UNITED STATES 1
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205S0001 NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 164 License No. DPR-46 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated February 25, 1992, as supplemented by letters dated June 9, 1992, and June 14, 1993, complies with the standards and t
requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facili ty will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission-C.
There is e asonable assurance:
(i) that the activities authorized by this ac ndment can be conducted without endangering the health and safety ->f the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9307210191 930707 l
PDR ADDCK 05000298 i
P PDR b.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.164, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective 30 days after its date of issuance.
FOR T NUCLEAR RE LATORY COMMISSION
))s
~.
Te ence L. Chan, Acting Director Project Directorate IV-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 7, 1993
'i 1
I
~*.
ATTACHMENT TO LICENSE AMENDMENT NO. 164
' FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 Replace the following pa9es of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOC.PAGES INSERT PAGES ii ii 187 through 192 187 through 190 191 -
192 193 193 194 194 195 195 196 196 197 197 198 198 199 199 200 200 t
b v
4 9v-w
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TABLE OF CONTENTS (cone'd) a Pare No SURVEILLANCE LIMITING CONDITIONS FOR OPERATION RECUIREMENTS 3.5 CODI AND CONTAINMENT C00 LING SYSTEMS 4.5 114 - 131 A.
Core Spray and LPC: Subsystems A
'114 B.
Containment Cooling Subsystem (RER Service Water)
B 116 C
117-C.
HPCI Subsys:em D.
RCIC Subsys:em D
118 E.
Automa:ic Depressurization System E
119 F.
Minimum Low Pressure Coolin8 System Diesel Generator Availability F
120 C.
Maintenance of Filled Discharge Pipe G
122 3.6 PRIMARY SYSTEM BOUNDARY 4.6 132 - 158 A.
Thermal and Pressurization Limitations A
132 3.
Coolan: Chemis:ry B
133a C
135 C.
Coolan: Leakage D.
Safety and Relief Valves D
136 E
137 E.
Je: Pumps F
Recirculation Pump Flow Mismatch F
137 3.
nservice *nspection C
137 H.
Shock Suppressors (Snubbers)
H 137a 3.7 CONTA*NMENT SYSTEMS 4.7 159 - 184 A
159 A.
Primary Con:ainmen:
3.
5:andby Gas Treatment Sys:em 3
165 C
165a C.
?rimary Con:ainmen: solation 7a'.ves D
166 3.S MISCELLANEDUS RADICACT;7E MATER *AL SOURCES a.8 135 - 190
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.b L.
L A.
Auxi'iary Electrical Equipmen:
A 191 3
192 3.
Opera:icn with *noperable Equipmen:
3.10 CCRE ALTE?.AT1055 4.10 203 209 A
203 A.
Refue'ing *nterlocks 3
205 B.
Core Moni:oring C.
Spen: Fuel Pool 'a'a er Level C
205 D.
Time Limi:a: ion D
206 E.
Spent Fuel Cask Handling E
206 4.11 2'O - 21.e 3.11 FUEL RODS A.
A*.*erage Planar Linear Hea: 3eneration Rate (APLHGR)
A 210 3.
Linear Hea: Genera: ion Ra:e (LHGR)
S 210
inimum :ri:ical Power ?.a:io (MCPR) 0 212 C.
i Amendment No. 94,97,196,152, I63,164
-it-
" INTENTIONALLY LEFT BIANK" 1
- Amendment No. 40' 164 187. 188, 189. 190 I.
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTDi ADolicability:
Acolicability:
Applies to the auxiliary electrical Applies to the periodic testing power system.
requirements of the auxiliary electrical systems.
Obiective:
Obiective:
To assure an adequate supply of Verify the operability of the electrical power for operation of auxiliary electrical system.
those systems required for safety.
Specification:
Soecification:
A.
Auxiliary Electrical Eauipment A.
Auxiliary Electrical Eculoment 1.
The reactor shall not be made 1.
Emercency Buses Undervoltage Relays l critical from a
Cold Shutdown Condition unless
.all of the a.
Loss of voltage relays following conditions are satisfied:
Once every 18 months, loss of a.
Both off-site sources (345 KV and voltage on emergency buses is 69 KV) and the startup transformer simulated to demonstrate the and emergency transformer are load shedding from emergency available and capable of buses and the automatic start automatically supplying power to the of diesel generators.
4160 Volt emergency buses IF and 1G.
b.
Undervoltage relays b.
Both diesel generators shall be operable and there shall be a
once every 18
- months, low minimum of 45,000 gal, of diesel voltage on emergency buses is fuel in the fuel oil storage tanks.
simulated to demonstrate disconnection of the emergency c.
The 4160V critical buses IF and 1G buses from the offsite power and the 480V critical buses IF and source.
The undervoltage 1G are energized.
relays shall be calibrated once every 18 months.
1.
The loss of voltage relays and their auxiliary relays are operable.
2.
The undervoltage relays and their auxiliary relays are operable.
d.
The four unit 125V/250V batteries and their chargers shall be
- operable, e.
The power monitoring system for the inservice RPS MG set or alternate source shall be operable.
Amendment No.
S^, S2, SS, 95,164
-191-l
l o,
LIMITING CONDITIONS FOR OPERATION SURVEILIANCE REOUIREMENTS 3.9.B 4.9.A.
(cont'd)
B.
Operation with Inonerable Eculement khenever the reactor is in Run Mode or Startup Mode with the reactor not in a Cold Condition, the availabil-ity of electric power shall be as specified in 3.9.A.1, except as specified in 3.9.B.l.
1.
Incomine Power a.
From and after the date incoming power is not available from a startup or emergency transformer, continued reactor operation is permissible under this condition for seven days.
At the end of this period, provided the second source of incoming power has not been made immediately available, the NRC must be notified of the event and the plan to restore this second source.
During this period, the two diesel generators and associated critical buses must be demonstrated to be
- operable, b.
From and after the date that incoming power is not available frorn both start-up and emergency trans-formers (i.e.,
both failed), con-tinued operation is permissible, provided the two diesel generators ant. associated critical buses are demonstrated to be operable, all core and containment cooling systems are operable, reactor power level is reduced to 25% of the rated and NRC is notified within 24 heat s of the situation, the precautw.a to be taken during this period and the plans for prompt restoration of incoming power.
l_
Amendment No. 80, 82, SS, 106, 122, 164 192-
LIMITING CONDITIONS FOR OPERATION SURVEILIANCE REOUIREMENTS 3.9.B (cont'd.)
4.9.A (cont'd.)
2.
Diesel Generators 2.
Diesel Generators Each diesel generator shall be a.
From and after the date that one of a.
the diesel generators or an asso-started manually and loaded to ciated critical bus is made or found not less than 50% of rated to be inoperable for any reason, load for no less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> continued reactor operation is per-once each month to demonstrate missible in accordance with Specifi-operational readiness.
cation 3.5.F.1 if Specification 3.9.A.1 is satisfied.
During the monthly generator test the diesel generator b.
From and after the date that both starting air compressor shall diesel generators are made or found be checked for operation and to be inoperable for any reason, its ability to recharge air continued reactor operation is receivers.
The operation of permissible only during the the diesel fuel oil transfer succeeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in accordance pumps and fuel oil day tank with Specification 3.5.F.2 if level switches shall be demon-Specification 3.9. A.1 is satisfied, strated, and the diesel start-ing time to reach rated volt-c.
From and after the date that_one of age and frequency shall be the diesel generators or associated logged.
critical buses and either the emer-gency or startup transformer power b.
Once every 18 months the source are made or found to be condition under which the inoperable for any reason, continued diesel generator is required reactor operation is permissible in will be simulated and a test accordance with Specification conducted to demonstrate that
- 3. 5. F.1, provided the other of f-site it will start and accept the source, startup transformer or emer-emergency load within the gency transformer is available and specified time sequence.
The capable of automatically supplying results shall be logged.
power to the 4160V critical buses C'
8pec cation 4.9.A.2.c and the NRC is notified within 24 de hours of the occurrence and the plans for restoration of the d.
Once a month the quantity of inoperable components.
die..! fuel available shall be logged.
e.
Every three months and upon sample of diesel delivery a fuel shall be checked for quality. The quality shall be within the acceptable limits specified in Table 1 of ASTM D975-68 for Nos. 1D or 20 and logged.
f.
At least once per 18 months, during shutdown, each diesel generator shall be given an inspection in accordance with instructions based on the manu fa c t u re r s
recommendations.
)
. Amendment No. SO SO, 99,05,10t,111,100,164
-193-
LIMITING CONDITIONS FOR OPERATION SURVEILIANCE REOUIREMENTS 3.9.B (cont'd.)
4.9.A (cont'd.)
3.
DC Power 3.
DC Power a.
From and after the date that one of a.
Every week, the following parameters the four unit 125 volt or 250 volt shall be verified:
batteries is made or found to be inoperable for any reason, restore 1.
The parameters of each desig-the inoperable battery to OPERABLE nated pilot cell meet the Cat-status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at egory A limits in Table 3.9.1.
least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within 2.
The total terminal voltage for the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, each 125 volt. battery is greater than or equal to 125 volts on float charge, and for each 250-volt battery the-terminal voltage is greater than or equal to 250 volts on float charge.
b.
Every quarter, and within 7 days after a battery discharge causing battery terminal voltage below 105 volts for a 125-volt battery or 210 volts for a 250-volt battery, or battery overcharge with battery ter-minal voltage above 140 volts for a 125-volt battery or 280 volts for a-250-volt
- battery, it shall be verified that:
1, The parameters for cell-to-cell meet the Category B
limits in Table 3.9.1.
2.
There is no abnormal corrosion at either terminal or connec-tors which could affect con-nection resistance, or the bar connection resistance of these items is less than or equal to 150 x 10-' ohm, and the inter-1 rack cable connection resis-tance shall be less than or equal to 280 x 10-' ohn.
1 3.
The electrolyte temperatures in a representative sample of
- cells, has an average temperature of at least i
70*F.
i c.
Once each operating cycle:
1.
The cells, cell plates, and i
battery racks shall be visually inspected.
Amendment No. 32, S2, SS, 10';, 122,164
-194-
'e LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.9.B.3-(conttd.)
4.9.A.3--(cont'd).
b.
From and after the date that.a unit 2.
The cell-to-cell and terminal battery charger is mad & or found to connections shall be verified be inoperable, restore the inoper-to be clean,. tight, free of.
able battery charger to OPERABLE-corrosion. and coated with status or replace with the spare anti-corrosion material.
battery charger within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be
.l in at least HOT SHUTDOW within the 3.
The resistance of each cell-next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOW to. cell and terminal bar' within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
connection shall. be verified to be less than.or equal to 150 x 10 ohn, and the inter,
l rack cable-connection resistance shall be verified to be less. than or ' equal to 280 x 10-' ohn.
4.
Each 125 volt battery charger will supply 200 amperes at-.125 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and each 250 volt' battery charger will-supply.
200 amperes at 250 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
d.
Once _ each operating cycle, during shutdown, one of the following tests will'b~e performed:
b 1.
A battery. service. test. to verify that battery capacity is adequate to supply the emergency load profile.
f 2.
A performance : discharge test, in lieu of the above - service test, once every five years to verify that battery capacity is at least 90%
of the
.l, manufacturer's rating.
3.
A performance discharge' test, in lieu of the above service test, ' when the battery. shows signs.- of, degradation or - has been in service seventeen -
years or longer.-
' Amendment No. SO, 22, ??, 10':, 122,164 195-
LIMITING CONDITIONS FOR OPERATION SURVEILIANCE REOUIREMENTS 3.9.B (cont'd.)
4.9.A (cont'd),
4.
Power Monitorine System for RPS 4.
Power Monitorine System for RPS System System a.
With one RPS electric power The above specified RPS power monitoring channel for an inservice monitoring system instrumentation RPS MG set or alternate power supply shall be determined operable:
inoperable, restore the inoperable channel to operable status within a.
At least once per operating-72 hours or remove the associated cycle by demonstrating the RPS MG set or alternate power supply operability of over-voltage, from service.
under-voltage and under-frequency protective instru-b.
With both RPS electric power mentation by performance of a monitoring channel for an inservice channel calibration including RPS MG set or alternate power supply simulated automatic actuation inoperable, restore at least one to of the protective
- relays, operable status within 30 minutes or tripping logic and output remove the associated RPS MG set or circuit breakers and verifying alternate power supply from service.
the following set-points.
1.
Over-voltage s 132 VAC, with time delay 5 2 sec.
2.
Under voltage a 108 VAC, with time delay s 2 sec.
3.
Under-frequency a 57 Hz. with time delay 5 2 sec.
1 4
1 l
Amendment No. 32, S2, SS, 10';, 130,164 196
(
TABLE 3.9.1 BATTERY SURVEILLANCE REOUIREMENTS CATEGORY Aus CATEGORY Bc2)
Parameter (WEEKLY)
(QUARTERLY)
Limits for each Limits for each Allowable") value for designated pilot cell connected cell each connected cell Electrolyte 2 Minimum level 2 Minimum level Above top of plates, Level indication mark, and indication mark, and not overflowing s 1/4" above maximum and s 1/4" above level indication mark maximum level indication mark Float Voltage 22.13 volts 22.13 volts")
22.10 volts Not more than 0.020 below the average of all connected cells Specific 21.195")
21.190 Gravity")
Average of all con-Average of all nected cells 21.190")
connected cells 21.200
")
For any Category A parameter (s) outside the limit (s) shown, the battery may be considered OPERABLE provided that within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> all the Category B measurements are taken and found to be within their allowable values, and provided all Category A and B parameter (s) are restored to within limits within the next 6 days.
l (2)
For any Category B parameter (s) outside the limit (s) shown, the battery may be considered OPERABLE provided that the Category B parameters are within their allow-able values and provided that Category B parameter (s) are restored to within limits within 7 days.
U)
Any Category B parameter not within its allowable value indicates an inoperable battery.
")
May be corrected for average electrolyte temperature.
U)
Corrected for electrolyte temperature and level.
")
Or battery charger current is less than 2 amperes when on float charge.
l Amendment No. 164 197
s 3.9 PASES The general objective of this Specification is _ to assure an adequate source of electrical power to operate the auxiliaries during plant operation, to operate facilities to cool and lubricate the plant during shutdown and to operate the engineered safeguards following the accident.
There are three sources of ac electrical energy available; namely, the startup transformer, the emergency i
transformer and two diesel generators. The de supply is required for switch gest and engineered safety feature systems.
This supply consists of two 125V DC and two 250V DC batteries and their related chargers.
Specification 3.9.A states the required availability of ac and de power; i.e.,
active off-site ac sources and the required amount of on site ac and dc sources.
Auxiliary power for CNS is supplied from the startup transformer and the normal transformer.
Both of these transformers are sized to carry 100% of the station auxiliary load.
The emergency transformer is about one third the size of these two transformers and is equal in size to both emergency diesel generators.
The startup transformer and the emergency. transformers are the offsite power sources.
Their voltage is monitored by undervoltage relays which provide low voltage protection for the emergency buses.
Whenever the voltage setpoint and time delay limit for the undervoltage relays have been exceeded, the emergency buses are automatically disconnected from the offsite power source.
If the startup or emergency transformer is lost, the unit can continue to operate since the unit auxiliary transformer is in service, and the emergency or startup transformer and the diesels are available.
If both the startup and emergency transformers become inoperable, the power level must be reduced to a value where by the unit can safely reject the load and continue to supply auxiliary electric power to the station.
In the normal mode of operation, the startup and emergency transformers are energized and two diesel generators are operable. One diesel generator may be allowed out of service based on the availability of power from the startup transformer and the fact that one diesel generator carries sufficient engineered safeguards equipment to cover all breakers. With the startup transformer and one diesel generator out of service, the off site transmission line corresponding to the emergency transformer must be available. Upon the loss of one on-site and one off site power source, power would be available from the other immediate off-site power source and the two operable on-site diesels to carry sufficient engineered safeguards equipment to cover all breaks.
4 In addition to these two power sources, removal of the Isolated Phase Bus " quick" disconnect links would allow backfeed of power through the main transformer to the unit auxiliary transformer and provide power to carry the full station auxiliary load.
The time required to perform this operation is comparable to the time the reactor could remain on RCIC operation before controlled depressurization need be initiated.
The D.C. Power Systems allowable out-of service time is based on NRC Regulatory Guide 1.93, " Availability of Electrical Power Sources."
The two-hour limit to restore battery operability minimizes reactor operation while in a degraded condition.
Amendment No. '; 3, 10^. 122, 130, 164
- 19 '. -
l l
+
l 4.9 BASES The monthly test of the diesel generator is conducted to check for equipment failures and deterioration.
Testing is conducted up to equilibrium operating conditions to demonstrate proper operation at these conditions.
The diesel generator will be manually started, synchronized and connected to the bus and load picked up.
The diesel generator should be loaded to at least 50% of rated load to prevent fouling of the engine. It is expected that the diesel generator will be run for at least two hours. Diesel generator experience at other generating stations indicates that the testing frequency is adequate and provides a high reliability of operation should the system be required.
Each diesel generator has two air compressors and two air receivers for starting.
It is expected that the air compressors will run only infrequently. During the monthly check of the diesel generator, each receiver in each set of receivers will be drawn down below the point at which the corresponding compressor automatically starts ta check operation and the ability of the compressors to recharge the receivers.
The diesel generator fuel consumption rate at full load is approximately 275 gallons per hour.
Thus, the monthly load test of the diesel generators will test the operation and the ability of the fuel oil transfer pumps to refill the day tank and will check the operation of these pumps from the emergency source.
The test of the diesel generator during the refueling outa5e will be more comprehensive in that it will functionally test the system; i.e, it will check diesel generator sta' ng and closure of diesel generator breaker and sequencing of load on the diesel g.,erator.
The diesel generator will be started by simulation of a loss-of-coolar,c accident. In addition, an undervoltage condition will be imposed to simulate a loss of off-site power.
Periodic tests between refueling outages verify the ability of the diesel generator to run at full load and the core and containment cooling pumps to deliver full flow.
Periodic testing of the various components, plus a functional test once-a-cycle, is sufficient to maintain adequate reliability.
I The diesel fuel oil quality must be checked to ensure proper operation of the diesel generators.
Water content should be minimized because water in the fuel could contribute to excessive damage to the diesel engine.
When it is determined that some auxiliary electrical equipment is out of service, the increased surveillance required in Section 4.5.F is deemed adequate to provide assurance that the remaining equipment will be operable.
The surveillance requirements for demonstrating the OPERABILITY of the unit batteries are in accordance with the recommendations of NRC Regulatory Guide 1.129, "Mainte-nance Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants," dated February 1978 and IEEE Std 450-1987, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations."
i 1
8 Amendment No. 65 16'4, 90, 22, 95, 10':,
'5
-199-l
l 1
4.9 BASES (cont'd)
Once each operating cycle, during shutdown, either a service test or performance discharge is performed on the 125 V and the 250 V batteries. The performance dis-charge test is performed in lieu of the service test when a battery shows signs of degradation. Degradation is indicated when battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below 90% of the manufacturer's rating.
Replacement criteria for 125V and 250V station batteries is s801 capacity factor and the maximum time for replacement should be one (1) year. This will assure that the remaining battery capacity is adequate to meet load requirements.
1 Verifying average electrolyte temperature above the minimum for which the battery was sized, total battery terminal voltage on float charge, connection resistance values and the performance of battery service and discharge tests ensures the effectiveness of the charging system, the ability of the battery to handle high discharge rates and compares the battery capacity at that time with the rated capacity.
Due to the physical configuration of the CNS batteries, two different inter-cell connection resistance values are surveilled.
Each division of the 125V and 250V batteries are configured into two racks, coupled with inter-rack connectors. There-fore, separate resistance values are provided for both the inter-cell (copper-bar type) and inter-rack (cable-type) connectors to demonstrate acceptability of battery connection resistance.
Table 3.9.1 specifies the normal limits for each designated pilot cell and each connected cell for electrolyte level, float voltage and specific gravity. The limits i
for the designated pilot cells ensure that their float voltage and specific gravity are characteristic of a charged cell with adequate capacity, and ensures the OPERABILITY and capability of the battery.
Operation with a battery cell's parameter outside the normal limit but within the allowable value specified in Table 3.9.1 is permitted for up to 7 days. During this 7-day period:
(1) the allowable values for electrolyte level ensures no physical damage to the plates with an adequate electron transfer capability; (2) the allowable value for the average specific gravity of all the cells, not more than 0.020 below j
the manufacturer's recommended full charge specific gravity, ensures that the decrease in rating will be less than the safety margin provided in sizing; (3) the allowable value for an individual cell's specific gravity ensures that an individual cell's specific gravity will not be more than 0.020 below the average specific gravity of all connected cells and that the overall capability of the battery will be maintained within an acceptable limit; and (4) the allowable value for an indivi-dual cell's float voltage, greater than 2.10 volts, ensures the battery's capability to perform its design function.
seismically qualified, The Reactor Protection System (RPS) is equipped with a Class 1E power monitoring system.
This system consists of eight Electrical Pro-tection Assemblies (EPA) which isolate the power sources from the RPS if the input voltage and frequency are not within limits specified for safe system operation.
Isolation of RPS power causes that RPS division to fail safe.
Amendment No. 00,105, 164
-200-
.