ML18037A536
| ML18037A536 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/25/1993 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18037A537 | List: |
| References | |
| DPR-33-A-200, DPR-52-A-218, DPR-68-A-173 NUDOCS 9311050125 | |
| Download: ML18037A536 (33) | |
Text
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UNlTED STATES NUCLEAR REGULATORY COMMISSION WASHlNGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROMNS FERRY NUCLEAR PLANT UNIT 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
200 License No.
DPR-33 The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
E ~
The application for amendment by Tennessee Valley Authority (the licensee) dated:March 19,
- 1993,
.as supplemented on. September 2,
- 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 The issuance of 'this amendment is in accordance with 10'FR Part 51 of the Commission's regulations and all applicable requirements have been satisfi'ed.
93ii050i25 93i025'DR ADOCK 05000259' PDR'
i 0
2.
Accordingly, the license is amended by changes to the Technical Specifications as indi'cated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No.
DPR-33 is hereby amended to read as follows:
3.
(2) Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revi'sed through Amendment No. 200, are hereby incorporated in the license.
The
,licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 25, 1993 Frederick J.
Heb on, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regul.ation
ATTACHM NT TO LICENSE A ENDHENT NO.
CI TY OP RA ING C
NS NO. 'DPR-33 DOCK
. 50-259 Revise the Appendix 'A Technical Specifications by removing the pages identified below and-inserting the enclosed-pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating. the area of change.
Overleaf" pages are provided to maintain document completeness.
R NOV 3.9/4.9-3
-3.9/4.9-4 3.9/4.9.-21 3.9/4.9-22 INS T
3.9/4;9-3
.3.9/4.9-4*
3.9/4.9-21 3.9/4.9-22*
10 0
4.
3-9.A.
4.9.A.
3-9.A.l.c.
(Cont'd) 4.9.A.l.b (Cont'd)
(4) The Athens 161-kV line is available to the units 1
and 2 shutdown boards through a common station-service transformer when unit 1 is in Cold Shutdown and unit 3 is not claiming the Athens line as an offsite source.
NOTE FOR (3) AND (4):
With no cooling tower pumps or fans running, a cooling tower transformer may be substituted for a common station-service transformer.
load sequencing, and operates for greater than or equal to five minutes while its gener-ator is loaded with the emergency loads.
(3)
On diesel, generator breaker trip, the loads are shed from the emer-gency buses and the di'esel output breaker recloses on the auto-start signal, the emergency buses are energized with permanently connected
- loads, the auto-connected emergency loads are energized through load sequencing, and the diesel operates for greater than or equal to five minutes while its generator is loaded with the emergency loads.
c.
Once a month the quantity of diesel fuel available shall be logged.
d.
Each diesel generator shall be inspected in accordance with instructions based on the manufacturer's recommendations once every 24 months.
e.
quarterly the quality of each diesel generator's (A, B, C, and D) seven-day fuel supply shall be checked.
The fuel oil quality shall be within the acceptable limits specified in Table 1
of ASSAM-D975-89...
BFN Unit 1
3.9/4.9-3 AEENDMKX HO. 200
!0 I
C S
S M
G CO TIONS FOR OPERAT 0 SURVEILL'ANCE RE UIRE S
3.9.A.
a E ectrical ui ment 4.9.A.
ux a
Electrica S ste
- 2. The reactor shal'1 not be started up (made critical) from the HOT STANDBY COHDITIOH unless all of the following conditions are satisfied:
2 ~
DC Power System Unit Batteries (250-V), Diesel-Generator Batteries (125-V) and Shutdown Board Batteries (250-V) a.
At least one offsite power source is available as specified in 3.9.A.l.c.
a.
Every week the specific gravity, voltage and temperature of the pilot cell and overall battery voltage shall be measured and logged.
b.
Three units 1 and 2 diesel generators shall be OPERABLE.
b.
Every three months the measurement shall be made of voltage of each cell to nearest O.l volt, specific gravity of'ach cell, and temperature of every fifth cell.
These measurements shall be logged.
c.,
An additional source of power consisting, of one of the following:
(1) A second offsite power source available as specified in 3.9.A.l.c.
c.
At least once every 24
- months, a battery rated discharge (capacity) test shall be performed and the voltage,
- time, and output current measurements shall be logged.
(2), A fourth OPERABLE units 1 and 2 diesel generator.
.d.
Requirements 3.9.A.3 through 3.9.A.6 are met.
BFH Unit 1 3.9/4.9-4 AMENDMENTNO. y g 8
4.9 The monthly test of the diesel generators is primarily to check for fai'lures and deterioration in the system since last use.
The diesels will-be loaded to at least 100 percent of its continuous rating (i.e., Z 2600 KW) while engine and generator temperatures are stabilized (about one hour).
A minimum 75-percent load will prevent soot formation in the cylinders and injection nozzles.
'Operation up to an equilibrium temperature ensures that there is no overheating problem.
The tests also provide an engine and generator operating history to be compared with subsequent engine-generator test data to identify and to correct any mechanical or electrical deficiency before it can result in a system failure.
Diesel testing once per 18 months (i.e., at least.once per fuel cycle) at a minimum load of 2800
'KW for an interval of not less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, assures that each diesel generator will'be capable of supplying the maximum load during the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of a loss of offsite power/loss of coolant accident.
This test also demonstrates each diesel generator's long-term load carrying capability.
The test during refueling outages is more comprehensive, including
.procedures that are most effectively conducted at that time.
These include automatic actuation and functional capability tests to verify that the generators can start and be ready to assume load in 10 seconds.
The maintenance inspection will detect any signs of wear long, before failure.
BFN tests the 7-day diesel generator fuel.oil supplies in accordance with Table 1 of ASTM-D975-89.
Each fuel oil supply is tested quarterly.
Battery maintenance with regard to the floating charge, equalizing
- charge, and electrolyte level will be based'n the manufacturer's instruction and sound maintenance practices.
In addition, written records will be maintained of the battery performance.
The plant batteries will deteriorate with time but precipitous failure is unlikely.
The type of surveillance called for in 'this specification is that which has been demonstrated through experience to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.
The equal'izing charge, as recommended by the manufacturer, is vital to maintaining the ampere-hour capacity of the battery and will be applied as recommended.
The testing of the logic systems will verify the ability of the logic systems to bring the auxiliary electrical system to running standby readiness with the presence of an accident signal from any reactor or an undervoltage signal on the 4-kV shutdown boards.
The periodic simulation of accident signals in conjunction with diesel generator voltage available signals will confirm the ability of the 480-V load shedding logic system to sequentially shed and restart 480-V loads if an accident signal were present, and diesel generator voltage was the only source. of electrical power.
BFN Unit 1
3'.9/4.9-21 ANEtKHENT NO. 200
4.9 Q~S S
(Cont'd)
REZERKKCCSS 1.
Hormal Auxiliary Pover System (BFHP FSAR Subsection 8.4)
.2.
Standby AC Pover Supply and Distribution (BFHP FSAR Subsection 8.5) 3.
250-V DC Pover Supply and Distribution (BFHP FSAR Subsection 8.6) 4.
Memorandum from Gene M. Wilhoite to H.. J.
Green dated December 4, 1981 (LOO 811208 664) and memorandum from C. E. Winn to H. 'J. Green dated January 10, 1983 (G02,830112 002)
BFH Unit 1 3.9/4.9-22 AMENDMENTgO, y g p
UNITED STATES NUCLEAR REGULATORY COMMISSION
'WASHINGTON, O.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 218 L'icense No.
DPR-52 The Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by Tennessee Valley 'Authority (the licensee) dated Harch 19,
- 1993, as supplemented on September 2,
- 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.
C.
0.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regul'ations of the Commission; 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; The issuance of this amendment will not be inimical to the common defense and security or to the heal,th and safety of the public; and 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.
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-52 is hereby amended to read as follows:
(2) Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 218, are hereby incorporated in. the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
'FOR THE NUCLEAR REGULATORY 'COMMISSION
Attachment:
Changes to the Technical'pecifications Frederick J.
Hebd n, Director Project Directorate II-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Date of Issuance:
October 25, 1993
ATTAC NT TO I
AC ITY OP ATING LIC NS NO.
DPR-5 DOCKET NO. 50-260 Revise the Appendix A Technical Specifications by removing the pages identified bel'ow and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Overleaf+ pages
.are provided to maintain document completeness.
REHOV 3.9/4.9-3 3.9/4.9-4 3.9/4.9-21 3.9/4.9-22
~INS 3.9/4.9-3 3.9/4.9-4*
3.9/4.9-21 3.9/4;9-22*
I5
4 3-9.A.
4.9.A.
3.9.A.l.c. (Cont'd)
- 4. 9.A. l.b. (Cont 'd) emergency loads through load sequencing, and operates for greater than or equal to five minutes while its generator is loaded with the emergency loads.
(4) The Athens 161-kV line is available to the units 1
and 2 shutdown boards through a common station-service transformer when unit 1 is in Cold Shutdown and unit 3 is not claiming the Athens line as an offsite source.
NOTE FOR (3) AND (4)'-
With no cooling tower pumps or fans running, a cooling tower transformer may be substituted for a common station-servi.'ce transformer.
(3) On diesel generator breaker trip, the loads are shed from the emergency buses and *the diesel output breaker recloses on the auto-start signal, the emergency buses are energized with permanently connected
- loads, the auto-connected emergency loads are energized through load sequencing, and the diesel operates for greater than or equal to five minutes while its generator is loaded with the emergency loads.
c.
Once a month the quantity of di:esel fuel available shall be logged.
d.
Each diesel generator shall be inspected in accordance
- with, instructions based on the manufacturer's recommendations once every 24 months.
e.
Quarterly the quality of each diesel generator's
'(A, B, C, and D) seven-day fuel supply shall be checked.
The fuel oil quality shall be within the acceptable limits. specified in Table 1 of ASTM-D975-89.
BFN Unit 2 3.9/4.9-3 AIKNMHNT50. 218
<0
4 'U LIARY LEC RICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.9.A.
uxiliar Electrical E ui ment 4.9.A.
Auxilia Electrical S st m
- 2. The reactor shall not be started up.(made critical}
from the HOT STANDBY 'CONDITION unless all of.the following conditions are satisfied:
2.
DC Power System Unit Batteries (250-V), Diesel-Generator Batteries (125-V) and Shutdown Board Batteries (250-V) a.
At least one offsite power source is available as specified in 3.9.A.l.c.
a.
Every week the specific gravity, voltage and temperature of the pilot cell and overall battery voltage shall be measured and logged.
b.
- Three units 1 and 2 diesel generators shall be OPERABLE.
b.
Every'hree months the measurement shall be made of voltage of each cell to nearest 0.1 volt, specific gravity of each
- cell, and temperature of every fifth cell.
These measurements shall be logged.
c.
An additional source of power consisting of one of the following:
(1) A second offsite power source available as specified in 3.9.A.l.c.
c.
At least once every 24
- months, a battery rated discharge (capacity) test shall be performed and the voltage,
- time, and output current measurements shall be logged.
(2).A fourth OPERABLE units 1 and 2 diesel generator.
d.
Requirements 3.9.A.3 through 3.9.A.6 are met.
BFN Unit 2 3.9/4.9-4 AMENOMEN gO y5<
il
4.9 ~
(Cont'he monthly tests of the diesel generators are primarily to check for failures and deterioration in the system since last use.
The diesels will be loaded to at least 100 percent of its continuous rating (i.e., 2 2600 KW) while engine and generator temperatures are stabilized (about one hour).
A minimum 75-percent load will prevent soot formation in the cylinders and injection nozzles.
Operation up to an equilibrium temperature ensures that there is no overheating problem.
The tests also provide an engine and generator operating history to be compared with subsequent engine-generator test data to identify and to correct any mechanical or electrical deficiency before it can result in a system failure.
Diesel testing once per 18 months (i.e., at least once per fuel cycle) at a minimum load of 2800 KW for an interval of not less 'than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> assures that each diesel generator will be capable of supplying the maximum load during the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of a loss of offsite power/loss of coolant accident.
This test also demonstrates each diesel generator's long-term load carrying capability.
The test during refueling outages is more comprehens'ive, including procedures that are most effectively conducted at that time.
These include automatic actuation and functional capability tests to verify that the generators can start and be ready to assume load in 10 seconds.
The maintenance inspection will detect any signs of wear long before failure.
BFN tests the 7-day diesel generator fuel oil supplies in accordance with Table 1 of ASM-D975-89.
Each fuel oil supply is tested quarterly.
Battery maintenance with regard to the floating charge, equalizing
- charge, and electrolyte level will be based on the manufacturer's instruction and sound maintenance, practices.
In addition, written records will be maintained of the battery performance.
The plant
,batteries wi1.1 deteriorate with time but precipitous failure is unlikely.
The type of surveillance called for in this specification i:s that which has been demonstrated through experience to provide an indication of a cell becoming irregular or unserviceable long before it becomes a fai'lure.
'The equalizing charge, as recommended by the manufacturer, is vital to maintaining the ampere-hour capacity of the battery and will'be applied as recommended.
The testing of the logic systems will verify the ability of the logic systems to bring the auxiliary electrical system to running standby readiness with the presence of an accident signal from any reactor or an undervoltage signal'n the 4-kV shutdown boards.
The periodic simulation of accident signals in conjunction with diesel generator voltage available signals will confirm the ability of the 480-V load shedding logic system to sequentially shed and restart 480-V loads if an accident signal were present, and diesel generator voltage were the only source of,electrical power.
BFN Unit 2 3.9/4.9-21 BKMX!ENT1%. 218
I
4.9
'BASES (Cont'd)
Specification 4.9.D provides surveillance requirements for Unit 3 diesel'enerators for the purpose of satisfying Specification 3.9.D. It contains less stringent.testing requirements for the Unit 3 diesel generators when they are only being used to support Unit 2 equipment.
REFERENCES 1.
Normal Auxiliary Power System (BFNP FSAR Subsection 8.4)
,2.
Standby AC Power Supply and Distribution (BFNP FSAR Subsection 8.5) 3.
250-V DC Power Supply and Distribution (BFNP FSAR Subsection 8.6) 4.
Memorandum from Gene M. Wilhoite to H. J.
Green dated December 4,
1981 (LOO '811208 664) and memorandum from C. E. Winn,to H. J.
Green dated January 10, 1983 (G02 830112 002)
BFN Unit 2 3.9/4.9-22 AMENOMENTNO. 1 8 1
gD.R RE00
~4 P0 00 I $
I, g
~ Qlvi 0 'O
+y*y4 UNITED STATES'UCLEAR REGULATORY COMMlSSION WASHINGTON, O.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
173 License No. DPR-68 The Nuclear 'Regulatory Commission (the Commission)'as.
found that:
'A.
B.
C.
D.
E.
The application for amendment by Tennessee Valley Authority (the licensee) dated'arch 19,
- 1993, as supplemented on September 2,
- 1993, complies with the standards and requi'rements 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 facil.ity wi,ll operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; The issuance of this amendment wi,ll not be inimical to the common defense and security or to the health and safety of the public; and The issuance of,this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all appl.icable requirements have been satisfied.
2 ~
Accordingly, the l.icense 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-68 is hereby amended to read as follows:
3.
(2) Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. y73, are hereby incorporated in the license.
The licensee shall operate the facil'ity in accordance with the Technical Specifi.cation'his license amendment is effective as of its date of issuance and shal.l
'be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
.Changes to the Technical Specifications Date of Issuance:
Octpbex Q5
$993 Frederick J.
Heb n, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
f 0
il
CHMENT TO LIC NSE AMENDMENT NO.
FACI ITY OPERATING 'LICENSE NO.
DPR-68 DOCK T NO. 50-296 Revise the Appendix A Technical Specifications, by removing the pages identified below and inserting the encl'osed pages.
The revised pages are identi'fied by the captioned amendment number and contain marginal lines indicating the area of change.
Over'leaf* pages are.provided.to maintain document completeness.
REMOV 3.9/4.9-3 3.9/4.9-4 3.9/4.9-20 3.9/4.9-21 INS RT 3.9/4.'9-3 3.9/4.9-4*
3.9/4,9-20 3.9/4.9-21*
ib I
4 3-9,.A.
4.9.A.
3-9.A.l.c.(3)
(Cont'd) 4.9.A.l.b.
(Cont'd)
NOTES'OR (2) AND (3):
through load sequencing, and operates for greater than or equal to five minutes while its gener-ator is loaded with the emergency loads.
If both Athens and Trinity lines are claimed as the two offsite sources for unit 3, no credit may be taken for the Athens-Trinity line tie breaker.
Specifically, the Athens line supplies unit 3 through common station-service transformer A or cooling tower transformer 1, and the Trinity line must supply unit 3 through common station-service transformer B or cooling tower transformer 2.
(3)
On diesel generator breaker trip, the loads are shed from the emergency buses and the diesel output breaker closes on the auto-start
- signal, the emergency buses are energized with permanently connected
- loads, the auto-connected emergency loads are energized through load sequencing, and the diesel operates for greater than or equal to five minutes while its generator is loaded with the emergency loads.
c.
Once a month the:quantity of diesel fuel available shall be loggede d.
Each diesel generator shall be inspected in accordance with instructions based on the manufacturer's recommendations once every 24 months.
e.
Quarterly the quality of each diesel generator's (3A, 3B, 3C, and 3D) seven-day fuel load supply shall be checked.
The fuel oil quality shall be within the acceptable limits specified in Table 1 of ASTN-D975-89.
BFN Unit 3 3.9/4.9-3 AEENH%RZ HO. 173
4.
AUXILIARYELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION 3.9.A.
Auxilia Electrical E ui ment 4.9.A.
Auxiliar Electrical
~Sstem SURVEILLANCE RE UIREMENTS 2.
The reactor shall not be started up (made critical) from the HOT STANDBY CONDITION unless all of the following conditions are satisfied:
2.
DC Power S ste Unit
~Batteries (250-V),
Diesel-Generator Batteries (125-V)and
,Shutdown Board Batteries (250-V) a.
At least one offsite power source is available as specified in 3.9.A.l.c.
a.
Every week the speci'fic gravity,
- voltage, and temperature of the pilot cell, and overall battery voltage shall be measured and logged.
b.
Three units 3 diesel generators shall be OPERABLE.
b.
Every three months the measurements shall be made of voltage of each cell to nearest O.l volt, specific gravity of each cell, and temperature of every.
fifth cell.
These measurements shall be logged.
c.
An additi'onal source of power consisting of one of the following:
(1) A second offsite power source available as specified in 3.9.A.l.c.
(2) A fourth unit 3 diesel generator OPERABLE.
c.
At least once every 24 months, a battery rated discharge (capacity) test shall be performed and the voltage,.
- time, and output current measurements shall be logged.
d.
Requirements 3.9.A.3 through 3.9.A.6 are met.
BFN Unit 3 3.9/4.9-4 AMENOMEe g0. y p g
0 i0 n
A 4-9 ~ (Cont The monthly tests of the diesel generators are primarily to check for fa'ilures and deterioration in the system since last use.
The diesels will be loaded to at least 100 percent of its continuous rating (i.e.
2600 KW) whi.le engine and generator temperatures are stabilized (about one hour).
A minimum 75-percent load will prevent soot formation in the cylinders and injection nozzles.
Operation up.'to an equilibrium
'temperature ensures that there is no overheating problem.
The tests also provide an, engine and generator operating history to be compared with subsequent engine-generator test data to identify and to correct any mechanical or.electrical defici'ency before it can result in a system failure.
Diesel testing once per 18 months (i.e., at least once per-fuel cycle) at a minimum load of 2800 KW for an interval of not less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> assures that each diesel generator will be capable of supplying the maximum load during the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of a loss of offsite power/loss of coolant accident.
This test also demonstrates each diesel generator's long-term load carrying capability.
The test during refueling outages is more comprehensive,.
including procedures that are most effectively conducted at that time.
These include automatic actuation and functional capability tests to verify
.that the generators can start and be ready to assume load in 10 seconds.
The maintenance inspection will detect any signs of wear long before failure.
BFN tests the 7-day diesel generator fuel, oil supplies in accordance with Table 1 of ASSAM-D975 Each, fuel oil supply is tested quarterly.
Battery maintenance with regard to the floating charge, equalizing
- charge, and electrolyte level will be based on the manufacturer's instruction and sound maintenance practices.
In addition, written records will be maintained of the battery performance.
The plant batteries will deteriorate with time but precipitous failure is unlikely.
The type of surveillance called for in this specification is that which has been demonstrated through experience to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.
The equalizing charge, as recommended by the manufacturer, is vital to maintaining.the ampere-hour capacity of the battery and will be applied as recommended.
The testing of the logic system will verify the ability of the logic systems to bring the auxiliary electrical system to running standby readiness with the presence of an accident signal from any reactor or an undervoltage signal on the start buses or 4-kV shutdown boards.
The periodic simulation of accident signals in conjunction with diesel generator voltage available signals wi'l onfirm the ability of the 480-V load shedding logic system to sequential'ly shed and restart 480-V.
loads if an accident signal were present and diesel,generator voltage were the only source of electrical power.
BEN Unit 3 3.9/4.9-20 AlIEtKtiERCM).'73
'F
4.9 BASES (Cont'd)
Specification 4.9.D provides surveillance requirements, for Unit 3 diesel generators for the purpose of satisfying Specification 3.9.D. It contains less stringent testing requirements for the Unit 3 diesel.
generators when they are only being used to support Unit '2 equipment.
References 1.,
Normal Auxiliary Power System (BFNP FSAR Subsection 8.4)~.
2.
Standby AC Power Supply and Distribution (BFNP FSAR'ubsection 8.5) 3.
250-V DC Power Supply and Distribution (BFNP FSAR Subsection.8.6) 4.
Memorandum from G. M. Wi'lhoite to H. J.
Green dated December 4, 1981 (LOO 811208 664) and memorandum from C. E. Winn to H. J.
Green dated January 10, 1983 (G02 830112 002)
BFN Unit 3 3'.9/4.9-21 AMENOMENTNO. 1 5 3