ML17262A667
| ML17262A667 | |
| Person / Time | |
|---|---|
| Site: | Ginna  (DPR-18-A-047, DPR-18-A-47) |
| Issue date: | 11/19/1991 |
| From: | Andrea Johnson Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17262A668 | List: |
| References | |
| NUDOCS 9112040289 | |
| Download: ML17262A667 (27) | |
Text
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WA)HINGTON,D. C. 20555 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.
E.
GINNA NUCLEAR POMER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
47 License No. DPR-18 The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Rochester Gas and Electric Corporation (the licensee) dated June 29, 1990, as supplemented on June 20, 1991, complies with the standards and 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 2.
C.
There's 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 set forth in 10 CFR Chapter I; D.
The issuance of this 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.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-18 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 47, are hereby incorporated in the license.
The licensee shall operate the facility in. accordance with the Technical Specifications.
9il2040289 9iiii9 PDR
- DOCK 05000244 'f p
3.
This license amendment is effective immediately and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to -the Technical Specifications Date of Issuance:
Noyember 19, 1991
ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO.
DPR-18 DOCKET NO. 50-244 Replace the following pages of the Appendix A Technical Specifications with
. the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 1
3.0-1 3.0-2 3.0-3 3.0-4 3.1-3 3.7-1 3.7-2 3.7-3 3.7-4 3.8-2 4.6-1 4.6.2 4
4.6-5 4.6-5A 1
3.0-1 3.0-2 3.0-3 3.0-4 3.1-3 3 e7-1 3.7-2 3 e7~3 3.7-4 3.7-5 3.7-6 3.7-7
'.8-2 4.6-1 4.6.2 4.6.2a 4.6-4 4.6-5 4.6-5A
0 TABLE OF CONTENTS 1.0 2.0 DEFINITIONS
- SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS Pacce 2.1-1 2.1 2.2 2.3 Safety Limit, Reactor Core Safety Limit, Reactor Coolant System Pressure Limiting Safety System Settings, Protective Instrumentation 2
~ 1 1
2
~ 2 1
- 2. 3-1 3.0 LIMITING CONDZTIONS FOR OPERATION 3.0 3.1 3.2 3.3 3 '3.5 3.6 3.7 3.8 3.9 3.10 3.11 3.12 3.13 3.14 3.15 3.16 Applicability Reactor Coolant System 3.1.1 Operational Components 3.1.2 Heatup and Cooldown 3.1.3 Minimum Conditions for Criticality
- 3. 1. 4 Maximum Coolant Activity 3.1.5 Leakage
- 3. 1. 6 Maximum Reactor Coolant Oxygen,
- Fluoride, and Chloride Concentrati Chemical and Volume Control System Emergency Core Cooling System, Auxiliary Cooling Systems, Air Recirculation Fan Co Containment Spray and Charcoal Filters Turbine Cycle Instrumentation System Containment System Auxiliary Electrical Systems Refueling Plant Effluents Control Rod and Power Distribution Limits Fuel Handling in the Auxiliary-Building Movable In-Core Instrumentation Shock. Suppressors (Snubbers)
Fire Suppression System Overpressure Protection System Radiological Environmental Monitoring on
- olers, 3.0-1 3 ~ 1 1
3 ~ 1 1
3;1-5 3.1-18 301-21 3.1-25 3 ~ 1 3 1 3 ~ 2 1
3 ~ 3 1
3.4-1 3.5-1 3.6-1 307 1
3.8-1 3.9-1 3.10-1 3
Q 1 1 1
3 ~ 1 2 1
3 ~ 1 3 1
3.14-1 3.15-1 3.16-1 4.0 SURVEILLANCE RE{}UZREMENTS 4.1 4.2 4.3 4.4 4.5 4.6 4.7 Operational Safety Review Inservice Inspection Reactor Coolant System Containment Tests Safety Injection, Containment Spray and Iodine Removal Systems Tests Preferred and Emergency Power Systems Periodic Tests Main Steam Stop Valves
- 4. 1-1 4.2-1 4.3-1 4.4-1
- 4. 5-1 4.6-1 4.7-1 Amendme~
No.
2A 47
I
6 3.0 t
t LIMITING CONDITION FOR OPERATION 3.0.1 APPLICABILITY In the event a Limiting Condition for Operation and/or associated action requirements cannot be satisfied because of circumstances in excess of those addressed in the specification, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action shall be initiated to place the unit in at least hot shutdown within the next 6
hours (i.e.,
a total of seven hours),
and in at least cold
, shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> (i.e.,
a total of 37 h'ours) unless corrective measures are completed that permit operation under the permissible action statements for the specified time interval as measured from initial discovery or until the reactor is placed in a
mode in which the specification is not applicable.
If the action statement corresponding to the Limiting Condition for Operation that was exceeded contains time limits to hot and cold shutdown 3.0.2 that are less than those specified
- above, these more limiting time limits shall be applied.
Exceptions to these requirements shall be stated in the individual specifications.
When a system, subsystem,
- train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its preferred power source is inoperable, it may be considere'd operable for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided:
Amendme~
No.
i 3.0-1
~\\
I
~
I (i) its corresponding preferred or emergency power source is operable; and (2) all of its redundant system(s),
subsystems (s), train (s),
component (s) and device (s) are
- operable, or likewise satisfy the requirements of this specification.
Unless both conditions (1) and (2) are satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the unit shall be placed in at least hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in at least Basis cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
This specification is not applicable in cold'hutdown or refueling modes.
Specification 3.0.1 delineates the ACTION to be taken for circumstances not directly provided for in the ACTION statements and whose occurrence would violate the intent of the specification.
For
- example, Specification 3.3.2 requires two Containment Spray Pumps to be operable and provides explicit action requirements if one spray pump is inoperable.
Under the terms of Specification 3.0.1, if both of the required Containment Spray Pumps are inoperable, the unit is required to be in at least hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least cold shutdown in the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
These time limits apply because the time limits for one spray pump inoperable (6
hours to hot shutdown, wait 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> then 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> to cold shutdown) are less limiting.
As a
further
- example, Specification 3.3.1 requires each Reactor Coolant System accumulator to be operable and provides explicit action requirements if one accumulator is s
Under the terms of Specification 3.0.1, if more than:one accumulator is inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action shall be initiated to place the unit in at least hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within an additional 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The time limit of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Amendgsrit No.
gp, 47 3.0-2
h
)l 1i I
, tI
to hot shutdown and 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> to cold shutdown do not apply because the time limits for 1 accumulatbr inoperable are more limiting. It is assumed that the unit is brought to the required mode within the required times by promptly initiating and carrying out the appropriate action statement.
Specification 3.0.2 delineates what additional conditions must be satisfied to permit operation to continue, consistent with the action statements for power sources, when a preferred or emergency power
'I source is not operable.
It allows operarion to be governed by the time limits of the action statement associated with the Limiting Condition for Operation-for the preferred or emergency power source, not the individual action statements for each
- system, subsystem, train, component or device that is determined to be inoperable solely because of the inoperability of its preferred or emergency power source.
- For, example, Specification 3.7.2.1.a requires in part that two emergency diesel generators be operable.
The action statement provides for a maximum out-of-service time when one emergency diesel generator is not operable.
If the definition of operable were applied without consideration of Specification 3.0.2, all systems, subsystems, trains, components and devices supplied by the inoperable emergency power source would also be inoperable.
This would dictate invoking the applicable action statements for each of the applicable Limiting Conditions for Operation.
- However, the provisions of Specification 3.0.2 permit the time limits for continued operation to be consistent with the action statement for the inoperable emergency diesel generator instead, provided the other specified conditions are satisfied.
In this case, this would mean that the corresponding Amendpdnt No.
N4~ 47 3.0-3
preferred power source must be operable, and all redundant
- systems, subsystems,
- trains, components, and devices must be
- operable, or
\\
otherwise satisfy Specification 3.0.2 (i.e., be capable of performing their design function and have at least one preferred or one emergency power source operable)
If they are not satisfied, shutdown is required in accordance with this specification.
AmenchgerA: No.
dA> 47 3.0-4
I
~ )
v)
{iii) residual heat removal loop A.*
(iv) residual heat removal loop B.*
Except during steam generator crevice cleaning operations, at least one of the coolant loops listed in paragraph
- 3. l.1. 1. e hall be in operation while RCS temperature is less than 350'F.
However, both reactor coolant pumps and residual heat removal pumps may be de-e'nergized for up to 1
hour provided 1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and 2) core outlet temperature is maintained at least 10 F g,
below saturation temperature.
If the conditions of 3.1.1.1.e are not
- met, immediately initiate corrective action. to return the required loops to operable status, and if not in cold h.
shutdown already, be in colL shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the conditions of 3.1.1.1.f are not
- met, then suspend all operations involving a reduction in boron concentrat'on of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to. operation.
- The preferred or emergency power source may be inoperable while in cold shutdown.
Amendmyat No.
24, 47 3 ~ 1-3
3 '
AUXILIARYELECTRICAL SYSTEMS 11'pplies to the availability of electrical power for the operation of plant auxiliaries.
3.7.1 To define those conditions of electrical power availability necessary to provide for the continuing availability of engineered safeguards.
S ecification 3.7.1.1 With fuel in the reactor vessel, the following conditions are to be met:
a.
One-independent o'ffsite power source
- operable, or backfeed through unit auxiliary transformer 11; and b.
One train of 480-volt buses (14 and 18, or 16 and 17) operable; and c.
One diesel generator operable with onsite supply of 5,000 gallons of fuel available and either buses 14 and 18, or 16 and 17, capable of being supplied from that diesel generator.
d.
One battery and one dc system, and at least 150 amps of battery charger capacity to the battery must be operable.
3.7.1.2 Actions To Be Taken If Conditions of 3.7.1.1 Are Not Met:
With less than the above minimum required power source
- operable, immediately suspend all operations involving positive reactivity changes, core alterations, movement of Amen~t No. p, 47 3 ~ 7 1
irradiated fuel and initiate corrective action to restore the required power sources to operable status.
3.7.2 S ecification 3.7.2.1 The reactor coolant system shall not be taken above the mode indicated unless the following conditions are met:
a.
Above cold shutdown; 1.
One independent offsite power source operable.
2.
the 480-volt buses 14 and 18 (Train A) and buses 16 and 17'Train B) are energized.
3.
the two diesel generators are operable with onsite supply of 5,000 gallons of fuel available for. each diesel generator.
4.
both batteries and both dc systems are operable.
5.
at least 150 amps of battery charging capacity for each DC system that is in service.
b.
Above 350'F-l.
All conditions of 3.7.2.1a above are met; and 2.
Two offsite sources (34.5 kv-4160 volt station
(
service transformers, 12A with dedicated circuit
- 751, and 12B with dedicated'ircuit 767) are operable.
3.7.2.2 Actions To Be Taken If Conditions of 3.7.2.1 Are Not Met:
a 0 Operation above 350'F may continue with one offsite source inoperable, provided all remaining conditions of 3.7. 2. 1 are met.
b.
With one or both independent offsite sources
- operable, and one diesel generator inoperable above cold shutdown, demonstrate the operability of the remaining diesel generator by:
Amends'.
Lr g,
47 3 a 7 2
- 1. Performing the surveillance requirements identified in Specifications 4.6.1.b.4 and 4.6.1.b.6 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter and restore the inoperable diesel generator to operable status within 7 days; OTHERWISE:
- 2. Reduce to a
mode equal to or below hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
With one safety related 480V Bus (i.e., bus 14 or 16 or 17 or 18) de-energized, re-energize the bus within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or reduce to a mode equal to or below hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in cold. shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, unless corrective actions are complete that permit continued operation (i.e., the bus is returned to service).
d.
With both independent offsite sources inoperable, both diesel generators must be operable.
In addition, restore one independent offsite source within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or reduce to a
mode equal to or below hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to an RCS temperature less than or equal to 350'F within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
e.
Operation above cold shutdown may continue if less than 150 amps of battery charging capacity is available to one dc system, provided at least 150 amps of battery charging capacity is available to each dc system within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. If not available, reduce to a mode equal to or below hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Amendment No.
47 3
~ 7 3
Basis for 3.7.1 and 3.7.2:
The
. electrical systems e'quipment is arranged so that
.no single failure can inactivate enough safeguards equipment to jeopardize the plant safety.
The 480-volt safeguards equipment is arranged on 4
I safeguards buses.
The 4160-volt equipment (none of which is safety-related),'s supplied from 4 buses.
Two separate offsite sources supply s'tation service power to the plant.
The plant auxiliary equipment is arranged electrically so that redundant safeguards loads receive power from separate sources.
Zn the event that 1 offsite source is not available, the remaining offsite source is capable of supplying both trains of safeguards loads.'afeguards loads such as safety injection pumps, containment fans, residual heat removal pumps, and. motor control centers 1C and 1D are divided between the 480-volt buses No.
14 and 16.
Redundant loads including service water pumps are supplied by buses No.
18 and 17.
Together these buses form the Train A and B redundant Class 1E sources.
AC power for safeguards equipment originates from both offsite and onsite sources.
The operability of these power sources and associated distribution systems ensures that sufficient power willbe available to supply the safety-related equipment required for (1) the Amendment No, 3,47 3.7-4
safe shutdown of the plant, and (2) the mitigation and control of accident conditions within the plant.
When the RCS is above cold shutdown, both emergency diesel generators are required to be operable.
The two diesel generators have sufficient capacity to start and run all the engineered safeguards equipment at design loads.
The safeguards equipment operated from one diesel generator can adequately cool the core and maintain the containment pressure within the design value for any loss of coolant incident.
The minimum diesel fuel oil inventory is maintained to assure that both diesels can carry the design loads of required engineered safeguards equipment for at least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, or for one engineered safety feature train for 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />, or for operation under hot standby non-accident conditions for 111 hours0.00128 days <br />0.0308 hours <br />1.835317e-4 weeks <br />4.22355e-5 months <br />."'ommercial oil supplies and trucking facilities exist to assure deliveries within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
The offsite power source consists of separate dedicated 34.5 kV-4160 volt station service transformers served by dedicated 34.5 kV lines (12A transformer with dedicated circuit 751, or 12B transformer with dedicated circuit 767) in operable status.
Either offsite source of power can supply all auxiliary loads and transfer can be accomplished within the time constraints of GDC 17. 'hus, GDC 17 is explicitly met.
With fuel in the reactor vessel a minimum of one, offsite source, one onsite source of AC power and one DC power train are required.
The offsite power source may be provided by one of three configurations:
Amendment No, 47 3.7-5
2.
3.
Transformer 12A served by a dedicated 34.5 kV line (circuit 751), or Transformer 12B served by a dedicated 34.5 kV line (circuit 767), or Backfeed through unit auxiliary transformer 11.
The offsite power source is the preferred source of AC power."
Operability of an offsite source requires that one station service tiansformer served by a dedicated 34.5 kV line is operating and providing power to the unit.
The emergency diesel generator provides power upon loss of the. offsite source.
One emergency diesel'enerator with 5,000 gallons of fuel can provide power to a minimum level of engineered safeguards equipment for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> (the required safeguards loads at cold shutdown/refueling are significantly less than during power operation).
One operable diesel fuel oil transfer pump is required to supply fuel from one of the two fuel storage tanks to the day tank of the operable diesel generator.
With less than one offsite and one onsite AC source of power available and one DC power train, no operations involving positive reactivity changes, core alterations, and movement of irradiated fuel shall occur.
Battery chargers with at least 150 amps capacity shall be in service for each battery so that the batteries will always be at full charge.
This ensures that adequate dc power will be available.
The plant can be safely shutdown without the use of offsite power since all vital loads (safety
- systems, instruments,. etc.)
can be supplied from the emergency diesel generators and the station batteries.
Amendment No. 47 3.7-6
The two diesel generators,
- loads, and the station auxil sources of power immediately 0
each capable of supplying safeguards iary transformers provide four separate available for operation of these loads.
- Thus, the power supply meets the single failure criteria.
Roferences (1)
UFSAR Section 9.5.4 Amendment No.
47 3077
d.
e.
g, h.
'east one so"rce range neutron flux monitor shall be in service.
At least one residual heat removal loop shall be in operation.*
Immediately before reactor vessel head removal and while loading and unloading fuel from the reactor, the minimum boron concentration of 2000 ppm shall be maint'ained in the
= primary coolant system and checked by sampling twice each shift.
Direct communication between the control room and the refueling cavity manipulator crane shall be available whenever changes in core geometry are taking place.
In addition to the requirements of paragraph 3.8.1.d, while in the refueling mode with less than 23 feet of water above the top of the reactor vessel
- flange, two residual heat removal loops shall be operable.*
During movement of fuel or control rods within the reactor vessel
., cavity, at least 23 feet.
of water shall be maintained over the top of the reactor vessel.
- Either the.preferred or the emergency power source may be inoperable for each residual heat removal,.loop.
Amendment j
L~
3.8-2
4.6 4.6.1 Preferred and Emer enc Power S stems Periodic Tests
~1'>>'1' Applies to periodic testing and surveillance requirements of the preferred and emergency power systems.
I To verify that the preferred and emergency power systems will respond promptly and properly when required.
S ecification The following tests and surveillance shall be performed as.
stated:
Diesel Generators At least one diesel generator shall be demonstrated operable:
a.
During cold or refueling shutdown at least once per 31 days by:
1.
Verifying the diesel starts from normal standby conditions, and attains rated voltage and frequency.
Jl Each diesel generator shall be demonstrated operable:
b.
Except during cold or refueling shutdown at least once per 31 days by:
1.
Verifying the fuel. level in the day tank.
2.
Verifying a minimum oil storage of 5,000 gallons for each generator that i.s'hsjte, 3.
Verifying the fuel transfer pump can be started r
and transfer fuel from the'torage system to the day tank.
4.
Verifying the diesel starts.
from normal standby conditions, and attains rated voltage and frequency.
5.
Verifying the generator is synchronized, loaded to at least 1950 kw but less than the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating of 2250 kw and operates for at least 60 minutes but less than 120 minutes.
6.
Verifying the diesel generator is aligned to provide standby power to the associated emergency buses.
Amendment No.
47 4.6-1
c.
The tests in Specification 4.6.1b will be performed prior to exceeding. cold shutdown if the time since the last test exceeds 31 days.
d.
At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank is within the acceptable limits specified in Table 1 of AS'975-78 when checked for viscosity, water and sediment.
e.
At least once per 18 months'during shutdown by:
1.
Inspecting the diesel in accordance with the manuf acturer '
recommendations for this class of standby service.
=
2.
Verifying the, generator capability to reject a"
load of 295 KW without tripping.
3.
Simulating a loss of offsite power in conjunction with a safety injection test signal and:
(a) Verifying de-energization of the emergency buses and load shedding from the emergency buses.
(b) Verifying the
, diesel starts from normal standby condition on the auto-start
- signal, energizes the automatically connected
'emergency loads with the following maximum=
breaker closure times after the initial starting signal for Trains A and B= not being exceeded A
B Diesel plus Safety Injection 20 sec 22 sec Pump plus RHR Pump All Breakers 40 sec 42 sec and operates for
> five minutes while its generator is loaded with emergency loads.*
(c) Verifying that all diesel generator
- pressure, and overcrank, are automatically bypassed upon a safety injection actuation signal.
Amendment No.
47
- 4. 6-2
I 4
g
~
A 4.
This test mav also serve to concurrently meet the reguiiements of 4.6.l.a and b.
Amendment Ho.
47 4-6-2a
1 11 I
~~f 4.6.3 c
~
d 0 e.
Pref Each a ~
At. each time data is
- recorded, new data shall be compared with old to detect signs of deterioration.
Each battery shall be subjected to a load test within a twelve-month period from the last load test; however, to permit the load test to coincide with a scheduled refueling,
+he period may extend for an additional three months.
The battery voltage as a function of time shall be monitored to establish that the battery performs as expected during heavy discharge and that all electrical connections are tight.
Each battery shall be subject to a discharge test at least once per 60 months.
The purpose of this test is to show that the battery capacity is at least 80% of the manuf acturer '
recommendations.
Shen performed, this discharge test may substitute for the load test.
The discharge test shall be performed annually for any battery that shows signs of degradation.
Degradation is indicated when the battery capacity drops more tharr 10% of rated capacity from its average on previous discharge tests, or is below 90t of the manufacturer's rating.
erred (Offsite) Power Su lies offsite power source shall be demonstrated operable:
At least once per 7 days by:
1.
Verifying nominal voltage indications on the high-voltage side of transformers 12A and 12B; and on the 4160 volt buses 12A and 12B.
b.
3.
2.
Verifying 4160 volt circuit breakers 12AX or 12BX, AND 12AY or 12BY are open.
Verifying tie breakers 52/BT16-14, and 52/BT17-18 are open when giant mode is above 200'F.
At least once per 18 months by transferring unit power supply to 4160 volt buses 12A and 12B from the normal circuit, i.e.,
transformer 12A for bus 12A and transformer 12B for bus 12B to the alternate circuit, i.e., transformer 12B for bus 12A and transformer 12A for bus 12B.
AmenchgpM No.
4.6-4
$ s s
1
-0 Basis The tests specified are designed to demonstrate that the diesel generators, will provide power for operation of equipment.
They also assure that the emergency generator system controls and the control systems for the safeguards equipment will function automatically in the event of a loss of all normal 480V AC station service power.
"'he test frequency specified will be often enough to identify and correct any mechanical or'lectrical deficiency before it can result in a
system failure.
The fuel supply and starting circuits and controls are continuously monitored and any faults are indicated by alarms.
An abnormal condition in these systems can be identified without having to test. the diesel generators.
Periodic tests are also specified to demonstrate that the offsite power sources will provide power for operation of equipment.
Offsite power source operability requires correct breaker alignment and indicated power availability from the two preferred power
- circuits, 767 and 751, to the 4160 volt buses.
These requirements are met by monitoring nominal voltage indications on the high-voltage side of transformers 12A and 12B; and on the 4160 volt buses 12A and 12B.
Offsite power source independence requires separate 4160 volt circuits supplying power to the 4160 volt buses.
Interlocks prevent concurrent closure of 12AX and
- 12BX, OR 12AY and 12BY; and surveillance is, specified to ensure separation is maintained.
I Amendrpefit No. +4, 47
- 4. 6-5
ICI I
t Furthermore, to assure independence between redundant Class 1E 480 volt buses 14 and 18 (Train A) and buses 16 and 17 (Train B), tie breakers 52/BT16-14 and 52lBT17-18 are required to be open when the plant mode is above 200'F.
Once tie breakers are
- open, interlocks prevent closure when independent and redundant buses are energized.
I Station batteries may 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, and to ensure that the battery capacity is acceptable.
I J
The equalizing charge, as recommended by the manufacturer, is vital to maintaining 'the ampere-hour capability of the battery.
As a check upon the effectiveness of the equalizing charge, the battery should be loaded rather heavily and the voltage monitored as a function of time.
If a cell has deteriorated or if a connection is'loose,. the voltage under load will drop excessively indicating replacement or maintenance.
The minimum permissible on-site fuel inventory, 10, 000
- gallons, (5,000 gallons for each generator),
is sufficient for operation under loss-of-coolant accident conditions of two engineered safety features trains. for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, or for one train for 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />, or for operation under hot standby non-accident conditions for 111 hours0.00128 days <br />0.0308 hours <br />1.835317e-4 weeks <br />4.22355e-5 months <br />.
"'eferences (1)
UFSAR, Section 8.3 (2)
UFSAR, Section 9.5.4 Amendm~ No.
3(4~
4~
4.6-5A
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