ML20063G150
| ML20063G150 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/07/1994 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20063G156 | List: |
| References | |
| NUDOCS 9402150342 | |
| Download: ML20063G150 (17) | |
Text
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+4 UNITED STATES y
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NUCLEAR REGULATORY COMMISSION iW f
WASHINGTON, D.C. 20555-0001 o%
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9..v.c DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 180 License No. DPR-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated June 14, 1990, as supplemented November 17, 1993, 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; 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 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.
0 q93\\G 0 3 9402150342 940207 PDR ADOCK 05000334' PDR
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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-66 is hereby amended to read as follows:
(2) Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.180, 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, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 3
Attachment:
Changes to the Technical Specifications Date of Issuance: February 7, 1994 t
h 9
ATTACHMENT TO LICENSE AMENDMENT NO.180 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of Appendix A, Technical Specifications, with the enclosed ' pages as indicated.
The revised pages are identified by amendment number and contain vertical-lines indicating the areas of change.
Remove Insert 3/4 8-5 3/4 8-5 6
3/4 8-7 3/4 8-7 3/4 8-10 3/4 8-10 B 3/4 8-1 B 3/4 8-1 B 3/4 8-2 B 3/4 8-2 1
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DPR-66 ELECTRICAL POWER SYSTEMS FHUTDOWN LIMITING CONDITION FOR OPERATION I
3.8.1.2~
As a minimum, the following A.C.
electrical power sources shall be OPERABLE:
a.
One circuit between the offsite transmission network and-the onsite Class 1E distribution system, and b.
One diesel generator with:
{
i 1.
Day ano engine-mounted fuel tanks containing a minimum of 900 gallons of fuel, 2.
A fuel storage system containing a minimum of 17,500 gallons of fuel, and f
3.
A fuel transfer pump.
APPLICABILITY: MODES 5 and 6, AND During movement of irradiated fuel i
with no fuel assemblies in the reactor vessel,-and During movement of loads over irradiated fuel with no fuel assemblies in the reactor vessel.
ACTION:
f With less than the above minimum - required A.C.
electrical. power sources OPERABLE, immediately suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel, and movement of loads over irradiated fuel until the minimum required A.C.
electrical power sources are restored to OPERABLE.
status.
SURVEILLANCE REQUIREMENTS i
I 4.8.1.2 The above required A.C.
electrical power sources shall be' demonstrated OPERABLE by the performance of each of the Surveillance i
Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for requirement 4.8.1.1.2.a.6.
1 BEAVER VALLEY - UNIT 1 3/4 8-5 Amendment No.180 I
.l 1
DPR-66 ELECTRICAL POWER SYSTEMS A.C.
DISTRIBUTION - SHUTDOWN
[
LIMITING CONDITION FOR OPERATION 3.8.2.2 As a minimum, one of the following trains of A.C.
Busses shall be OPERABLE and energized in the specified manner:
a.
Train "A" A.C.
Emergency Busses consisting of:
1.
4160-Volt Emergency Bus #1AE,-
2.
480-Volt Emergency Bus #8N, 3.
120-Volt A.C.
Vital Bus
- I energized from its associated inverter connected to D.C.
Bus #1-1, and 4.
120-Volt A.C.
Vital Bus #III energized from its associated inverter connected to D.C. Bus #1-3.
b.
Train "B" A.C.
Emergency Busses consisting of:
1.
4160-Volt Emergency Bus #1DF, 2.
480-Volt Emergency Bus #9P, 3.
120-Volt A.C.
Vital Bus
- II energized from its associated inverter connected to D.C.
Bus #1-2, and 4.
120-Volt A.C.
Vital Bus
- IV energized from its associated inverter connected to D.C.
Bus #1-4.
APPLICABILITY: MODES 5 and 6, AND During movement of irradiated fuel i
with no fuel assemblies in the reactor vessel, and i
During movement of loads over irradiated fuel with no fuel assemblies in the reactor vessel.
i ACTION:
With the above required train of A.C.
Emergency Busses not fully energized in the required manner, immediately suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel and movement of loads over irradiated fuel.
Initiate corrective action to energize the required electrical busses in the specified manner as soon as possible.
SURVEILLANCE REQUIREMENTS I
4.8.2.2 The specified busses shall be determined energized in the required manner at least once per 7 days by verifying correct breaker alignment and indicated voltage on the busses.
BEAVER VALLEY - UNIT 1 3/4 8-7 Amendment No.180
_m m
DPR-66 ELECTRICAL POWER SYSTEMS i
D.C.
DISTRIBUTION - SHUTDOWN LIMITING CONDITION FOR OPERATION r
3.8.2.4 As a minimum, one of the following trains of D.C. electrical equipment and busses shall be OPERABLE and energized in the specified' manner:
a.
Train "A"
(orange) consisting of the following:
1.
125-volt D.C.
Busses No. 1-1 & 1-3, and 2.
125-volt D.C. Battery Banks 1-1 & 1-3 and Chargers 1-1
& 1-3.
b.
Train "B"
(purple) consisting of the following:
1.
125-volt D.C.
Busses No. 1-2 & 1-4, and 2.
125-volt D.C. Battery Banks 1-2 & 1-4 and Chargers 1-2 1-4.
APPLICABILITY:
MODES 5 and 6, AND 1
During movement of irradiated fuel l
with no fuel assemblies in the reactor vessel, and i
During movement of loads over irradiated fuel with no fuel assemblies in the reactor' vessel.
- l ACTION:
I With the above required train of D.C. electrical equipment and busses not fully OPERABLE, immediately suspend all operation involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel
~
and movement of loads over irradiated fuel.
Initiate' corrective action to restore the required train of D.C. electrical equipment and busses to OPERABLE status as soon as possible.
t SURVEILLANCE REQUIREMENTS 4.8.2.4.1 The above required 125-volt D.C. bus train shall be l determined OPERABLE and energized at least once per 7 days. by -
verifying correct breaker alignment and indicated power availability.'
4.8.2.4.2 The above required 125-volt battery bank and chargers shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.
BEAVER VALLEY - UNIT 1 3/4 8-10 Amendment No.180
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DPR-66 3/4.8 ELECTRYCAL POWER SYSTEMS u
BASES I
3/4.8.1. 3/4.8.2 A.C.
SOURCES.
D.C.
SOURCES AND ONSITE POWER l
DISTRIBUTION SYSTEMS i
The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety related equipment' required for 1) the safe shutdown of the facility and 2) the mitigation and control of accident conditions within the facility.
-The minimum specified independent and redundant A.C.
and D.C.
power sources and
)
distribution systems satisfy the requirements of General Design Criterion 17 of Appendix "A" to 10 CFR 50.
The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation.
The OPERABILITY of the power sources are consistent with the initial condition assumptions of the safety analyses and are based upon maintaining at least one redundant set of onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during' accident conditions coincident with an assumed loss of offsite power and.
single failure of the other onsite A'.C.
source.
The ACTION requirements specified in MODES'S and 6 address the condition where sufficient power is unavailable to recover from postulated events (i.e. fuel handling accident).
Implementation of the ACTION requirements shall not preclude completion of actions to establish a safe conservative plant condition.
Completion of the requirements will prevent the occurrence of postulated events for which mitigating actions would be required.
The OPERABILITY of tha minimum specified A.C.
and D.C.
power i
sources and associated distribution systems during shutdown and l
refueling ensures that 1) the facility can be maintained in the shutdown or refueling condition for extended time periods, 2) sufficient instrumentation and control capability is available for' monitoring and maintaining the unit status, and 3) sufficient power is available for systems (i.e.
Supplemental Leak - Collection and Release System) necessary to recover from postulated events in these MODES, e.g. a fuel handling accident.
The Surveillance Requirement for demonstrating the OPERABILITY of the station batteries are based on the recommendations of Regulatory Guide 1.129,
" Maintenance Testing and ' Replacement of Large Lead Storage Batteries for Nuclear Power Plants," February 1978, and IEEE Std 450-1980, "IEEE. Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations."
l BEAVER VALLEY - UNIT 1-B 3/4 8-1 Amendment No.180 1
DPR-66 ELECTRICAL POWER SYSTEMS BASES e
A.C.
- EOURCES, D.C.
SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS (Continued)
Verifying average electrolyte temperature above the minimum for l
which the battery was sized, total battery terminal voltage on float charge, connection resistance values and the performance of battery I
service and discharge tests ensures the effectiveness of the charging i
system, the ability to handle high disc.harge rates and compares the battery capacity at that time with the rated capacity.
i' Table 3.8-1 specifies the normal limits for each designated pilot cell and each connected cell for electrolyte level, float voltage and specific gravity.
The limits for the designated pilot cells float voltage and specific gravity, greater than 2.13 volts and.015 below the manufacturer's full charge specific gravity or a battery charger s
current that had stabilized at a low value, is characteristic of a charged cell with adequate capacity.
The' normal limits for each connected cell for float voltage and specific gravity, greater than 2.13 volts and not more than.020 below the manufacturer's full charge specific gravity with an average specific gravity of all the connected cells not more than.010 below the manufacturer's full charge specific gravity, ensures the OPERABILITY and capability of the battery.
j Operation with a battery cell's parameter outside the normal limit but within the allowable '.value specified in Table 3.8-1 is permitted for up to 7 days.
During this 7 day period:
(1) the l
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.020 below 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 i
for an individual cell's specific gravity, ensures that an individual cell's specific gravity will not be more than
.040 below the manufacturer's full charge specific gravity and that the overall capability of the battery will be maintained within an acceptable limit; and (4) the allowable value for an individual cell's float voltage, greater than 2.07 volts, ensures the battery's capability to perform its design function.
provides clarification of Specification 3.8.1.1 action Note
- requirements when the diesel generators are inoperable as a_ result of r
Surveillance Requirements 4.8.1.1.2.d.2 and 4.8.1.1.2.e in accordance with Regulatory Guide 1.137 Revision 1 Regulatory Position C.2.a.
t BEAVER VALLEY - UNIT 1 B 3/4 8-2 Amendment No.180
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UNITED STATES
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j NUCLEAR REGULATORY COMMISSION
- Q WASHINGTON. D.C. 20555-0001
%Q % y DUOVESNE LIGHT COMPANY OHIO EDIS0N COMPANY D'E CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLED0 EDISON COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No. NPF-73 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated June 14, 1990, as supplement,d November 17, 1993, 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; 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 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.
i
1
. l t
1 l
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. NPF-73 is hereby amended to read as follows:
l (2) Technical Soecifications i
The Technical Specifications contained in Appendix A, as revised through Amendment No. 60, and the Environmental Protection Plan contained )n Appendix B, both of which are attached hereto are hereby incorporated in the license. DLC0 shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
. k it h
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: February 7,1994 s
-l ATTACHMENT TO LICENSE AMENDMENT NO. 60 i
FACILITY OPERATING LICENSE N0. NPF-73 DOCKET NO. 50-412 Replace the following pages of Appendix A, Technical Specifications, with the
- enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 8-6 3/4 8-6 i
i 3/4 8-8 3/4 8-8 3/4 8-12 3/4 8-12 B3/4 8-1 B3/4 8-1 B3/4 8-2 B3/4 8-2 B3/4 8-3 q
i 6
I i
NPF )
ELECTRICAL POWER SYSTEMS l
-SHUTDOWN LIMITING CONDITION FOR OPERATION-3.8.1.2 As a minimum, the following A.C.
electrical power sources shall be OPERABLE:
a.
One circuit between the offsite transmission network and
- i i
the onsite Class 1E distribution system, and b.
One diesel generator with:
1.
Day tank containing a minimum of 350 gallons of fuel, l
2.
A fuel storage system containing a minimum of 53,225 gallons of fuel, 3.
A fuel transfer pump.
APPLICABILITY:
MODES 5 and 6, AND During movement of irradiated fuel t
with no fuel assemblies in the reactor vessel, and During movement of loads over irradiated fuel with no fuel assemblies _in the reactor vessel.
ACTION:
With less than the above minimum required A.C.
electrical power sources OPERABLE, immediately suspend all operations involving-CORE ALTERATIONS, positive reactivity changes, movement of irradiated-fuel, and movement of loads over irradiated fuel until the minimum required A.C.
electrical power sources are restored to OPERABLE i
status.
SURVEILLANCE REQUIREMENTS 4.8.1.2 The above required A.C.
electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance.
Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for requirement j
4.8.1.1.2.a.6.
P 7
BEAVER VALLEY - UNIT 2 3/4 8-6 Amendment No. 60
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NPF-73 ELECTRICAL POWER SYSTEMS A.C.
DISTRIBUTION - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.2 As a minimum, one of the following trains of A.C.
Busses shall be OPERABLE and energized in the specified manner:
a.
Train "A" A.C.
Emergency Busses consisting of:
1.
4160-Volt Emergency Bus #2AE, 2.
480-Volt Emergency Bus #2N, 3.
120-Volt A.C.
Vital Bus
- I energized from its associated inverter connected to D.C. Bus #2-1, and 4.
120-Volt A.C.
Vital Bus #III energized from its associated inverter connected to D.C.
Bus #2-3.
b.
Train "B" A.C.
Emergency Busses consisting of:
1.
4160-Volt Emergency Bus #2DF, 2.
480-Volt Emergency Bus #2P, 3.
120-Volt A.C.
Vital Bus
- II energized from its associated inverter connected to D.C.
Bus #2-2, and 4.
120-Volt A.C.
Vital Bus
- IV energized from its associated inverter connected to D.C.
Bus #2-4.
APPLICABILITY:
MODES 5 and 6, AND l
During movement of irradiated fuel with no fuel assemblies in the reactor vessel, and l
During movement of loads over irradiated fuel with no fuel assemblies in the reactor vessel, ACTION:
With less the above required train of A.C. Emergency Busses not fully energized in the required manner, immediately suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated
- fuel, and movement of loads over irradiated fuel.
Initiate corrective action to energize the required electrical busses in the specified manner as soon as possible.
SURVEILLANCE REQUIREMENTS 4.8.2.2 The specified busses shall be determined energized in the required manner at least once per 7 days by verifying correct breaker alignment and indicated voltage on the busses.
BEAVER VALLEY - UNIT 2 3/4 8-8 Amendment No. 60
I d
l MPF-73
-1 ELECTRICAL POWER SYSTEMS D.C.
DISTRIBUTION - SHUTDOWN i
LIMITING CONDITION FOR OPERATION t
t 3.8.2.4 As a minimum, one of the following trains of D.C. electrical equipment and busses shall be OPERABLE and energized in the specified manner
- l a.
Train "A"
(orange) consisting of the following:
I 1.
125-volt D.C.
Busses No. 2-1 &_2-3, and 2.
125-volt D.C. Battery Banks 2-1 & 2-3 and Charger 2-1*
& Rectifier 2-3*.
b.
Train "B" (purple) consisting of the following:
1.
125-volt D.C.
Busses No. 2-2 & 2-4, and 2.
125-volt D.C. Battery Banks 2-2 & 2-4 and Charger 2-2*
& Rectifier 2-4*.
APPLICABILITY:
MODES 5 and 6, AND Dur'ing movement of irradiated fuel with no fuel assemblies in the reactor vessel, and During movement of loads over irradiated fuel with no fuel assemblies in the reactor vessel.
ACTION:
With the above required train of D.C. electrical equipment and busses not fully OPERABLE, immediately suspend all operation involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel and movement of loads over irradiated fuel.
Initiate corrective action to restore the required train of D.C. electrical equipment and busses to OPERABLE status as soon as possible.
SURVEILLANCE REQUIREMENTS 4.8.2.4.1 The above required 125-volt D.C.
bus train shall be j determined OPERABLE ' and energized at least once per
'7 days by verifying correct breaker alignment and indicated power availability.
4.8.2.4.2 The above required 125-volt battery bank and chargers / rectifiers shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.
)
Spare Charger 2-7 may be substituted for any one charger or rectifier.
BEAVER VALLEY - UNIT 2 3/4 8-12 Amendment No. 60 -
i NPF-73 3/4.8 ELECTRICAL POWER SYSTEMS BASES j
3/4.8.1. 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS The OPERABILITY of the A.C. and D.C. power sources and associated
)
distribution systems during operation ensures that sufficient power will be available to supply the safety related equipment required for.
2
- 1) the safe shutdown of the facility and 2) the mitigation and control of accident conditions within the facility.
The. minimum specified independent and redundant A.C. and D.C.
power sources-and distribution systems satisfy the requirements of General Design Criterion 17 of Appendix "A" to 10 CFR 50.
The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility.
operation commensurate with the level of degradation.
The OPERABILITY of the power sources are consistent with the initial condition assumptions of the safety analyses and are based upon maintaining at least one redundant set of onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during accident-conditions coincident with an assumed loss of offsite power and single failure of the other onsite A.C.
source.
The ACTION requirements specified in MODES 5 and 6 address the condition where sufficient power is unavailable to recover from postulated events (i.e., fuel handling accident).
Implementation of the ACTION requirements shall not preclude completion of actions to establish a safe conservative plant condition.
Completion of the requirements will prevent the occurrence of postulated events for which mitigating actions would be required.
The OPERABILITY of the minimum specified A.C.
and D.C.
power sources and associated distribution systems during shutdown and refueling ensures that 1) the facility can be maintained in the shutdown or refueling condition for extended time periods and 2) sufficient instrumentation and control capability is available for monitoring and maintaining the unit status, and 3) sufficient power is available for systems (i.e.,
Supplemental Leak Collection and Release System) necessary to recover from postulated events in these
- MODES, e.g.,
a fuel handling accident.
The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are based on the recommendations of Regulatory Guides 1.9, Revision 2, " Selection of Diesel Generator Set Capacity for Standby Power Supplies," December 1979; 1.108, " Periodic Testing-of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977; and 1.137, " Fuel-Oil Systems for Standby Diesel Generators," Revision 1, October 1979,
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BEAVER VALLEY - UNIT 2 B 3/4 8-1 Amendment No. 60 i
NPF-73 3/4.8 ELECTRICAL POWER SYSTEMS BASES 3/4.8.1, 3/4.8.2 A.C.
SOURCES AND ONSITE POWER DISTRIBUTION (Continued) j Appendix A 'to Generic Letter 84-15 and Generic Letter 83-26,
" Clarification of Surveillance Requirements for Diesel Fuel Impurity Level Tests."
The Surveillance Requirement for demonstrating the OPERABILITY of the Station batteries are based on the recommendations of Regulatory Guide 1.129,
" Maintenance Testing and Replacement of Large Lead i
Storage Batteries for Nuclear Power Plants," February 1978, and IEEE Std 450-1980, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations."
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 to handle high discharge rates and compares the battery capacity at that time with the rated capacity.
Table 3.8-1 specifies the normal limits for each designated pilot cell and each connected cell for electrolyte level, float voltage and specific gravity.
The limits for the designated pilot cells float voltage and specific gravity, greater than 2.13 volts and 0.015 below the manufacturer's full charge specific gravity or a battery charger current that had stabilized at a low value, is characteristic of a charged cell with adequate capacity.
The normal limits for each connected cell for float voltage and specific gravity, greater than 2.13 volts and not more than 0.020 below the manufacturer's. full charge specific gravity with an average specific gravity of all the connected cells not more than 0.010 below the manufacturer's full charge specific gravity, ensures the OPERABILITY and capability of i
the battery.
Operation with a battery cell's parameter outside the normal limit but within the allowable value specified in Table 3.8-1 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 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 BEAVER VALLEY - UNIT 2 B 3/4 8-2 Amendment No. 60
NPF-73 3/4.8 ELECTRICAL POWER SYSTEMS l
+
BASES l
3/4.8.1, 3/4.8.2 A.C.
SOURCES AND ONSITE POWER DISTRIBUTION
-(Continued) l i
gravity will not be more than 0.040 below the manufacturer's full I
charge specific gravity and that the overall capability of the battery will be maintained within an acceptable limit; and'4) the allowable value for an individual cell's float voltage, greater than i
2.07 volts, ensures the battery's capability to perform its design function.
on page 3/4 8-2 provides clarification of Specification Note
- 3.8.1.1 Action requirements when the diesel generators are inoperable as a
result of Surveillance Requirements 4.8.1.1.2.d.2 and 4.8.1.1.2.e in accordance with Regulatory Guide 1.137, Revision 1, i
Position C.2.a.
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1
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BEAVER VALLEY - UNIT 2 B 3/4 8-3 Amendment No. 60 l
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