ML18036A419
| ML18036A419 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/04/1991 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18036A420 | List: |
| References | |
| DPR-33-A-186, DPR-52-A-199, DPR-68-A-158 NUDOCS 9111140045 | |
| Download: ML18036A419 (47) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 RROWNS FERRY NUCLEAR PLANT ONIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.186 License No. DPR-33 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated September 13, 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; 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.
9111140045 911004 PDR ADOCK 05000259 i,
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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-33 is, hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised.through Amendment No. 186, 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 its date of issuance and shall be implemented no later than November 6, 1991.
FOR THE NUCLEAR REGULATORY COMMISSION 0)-
Q Frederick J.
Hebtfon, Director Project.Directorate II-4 Division of Reactor Projects - I'/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
-November 4, 1991
ATTACHMENT TO LiCENSE AMENDMENT N0.186 FACILITY OPERATING LICENSE NO.
DPR-33 DOCKET 'NO. 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 nomber ana contain marginal lines indicating the area of change.
".Denotes overleaf page.
REt".OVE
- 3. 2/4. 2-48 3.2/4. 2-49 3.9/4'.9-5 3.9/4.9-6 INSERT 3.2/4.2-48*
3.2'/4. 2-49 3 9/4 95 3.9/4.9-6
II
TABLE 4.2.8 (Continued)
SURVEILLANCE REQUIRENEHTS FOR IHSTRUNENTATIOH THAT INITIATE OR CONTROL THE CSCS Function Core Spray Loop A Discharge Pressure (PI-75-20)
Functional Test N/A Calibratlon once/6 months Instrument Check once/day Core Spray Loop 8 Discharge Pressure (PI-75-48)
RHR Loop A Discharge Pressure (P I 51)
RHR Loop B Discharge Pressure (PI-74-65)
Instrument Channel-RMR Start N/A N/A H/A Tested during functional test of RHR pump (refer to Section 4'.8) once/6 months once/6 months once/6 months N/A once/day once/day once/day N/A Instrument Channel Thermostat (RHR Area Cooler Fan)
.once/month once/6 months N/A Instrument Channel Core Spray A or C Start Instrument Channel-Core Spray B or D start Instrument Channel-Thermostat (Core Spray Area Cooler Fan)
Tested during functional test of core spray (refer to Section 4.5.A).
Tested during functional test of.
core spray (refer to Section 4.5.A).
once/month H/A N/A once/6 months H/A H/A H/A
TABLE 4'.B (Continued)
SURVEILLANCE REQUIREHEHTS FOR IHSTRUHEHTATIOH THAT INITIATE OR COIITROL THE CSCS Function Functional Test Calibration Instrument. Check RHR Area Cooler Fan Logic Core Spray Area Cooler Fan Logic Instrument Channel Core Spray Hotors A or D Start Tested during functional test of instrument
Ho other test required.
Tested during logic system functional test of instru-ment channels, core spray motor start and thermostat (core spray area cooler fan).
Ho other test required.
Tested during functional test of core spray pump (refer to Section 4.5.A) ~
H/A H/A H/A H/A H/A H/A Instrument Channel Core Spray Notors B or C Start Tested during functional test of core spray pump (refer to Section 4.5.A).
H/A H/A Instrument Channel
- Core Spray Loop 1 Accident Signal Instrument Channel-Core Spray Loop 2 Accident Signal RHRSk Initiate Logic RPT Initiate Logic RPT Breaker Tested during logic system functional test of core spray system.
Tested during logic system functional test of core spray system.
once/18 months once/month once/operating cycle H/A H/A H/A H/A H/A H/A N/A H/A N/A H/A
4 AUXILIARYEL CTR C L S STEM LIMITING CONDITIONS FOR. OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.
a Elect c
E u ment 4.9.A'.
ec a
S st
'3.
Buses and Boards Available 3.
Logic Systems a.
The respective start bus is energized for each common station-service; trans'former designated as an offsite. power source.
a.
Both divisions of the common accident signal logi'c system shall be tested, every 18 months to demonstrate that it will function on actuation of the core spray system of each reactor to.provi'de an automatic start signal to all 4 units 1 and 2
diesel generators.
b.
The 4-kV'us tie board is energized and capable of supplying power to the units 1 and 2 shutdown boards if a cooling tower transformer is designated as an offsite power source.
b.
Once every 18 months, the condition under which the 480-V load shedding logic system is required shall be simulated us'ing pendant test switches and/or pushbutton test switches to demonstrate that the load shedding logic system would initiate load shedding signals on
'the diesel auxiliary
- boards, RMOV boards, and the 480-V shutdown boards.
c.
The units 1.and
- 2. 4-kV shutdown boards are energized.
BFN Unit 1 3.9/4.9-5 Amendment 186
4 AUXILIARY C RICAL SYSTEM LIMITING CONDITIONS FOR 'OPERATION SURVEILLANCE REQUIREMENTS 3.9.'A.
Aux lia Electrica E u ment 4.9.A.
Aux a
ect cal S ste 3.9.A.3. (Cont'd) d.
The.'480-V shutdown boards lA and 1B are energized.
e.
The units 1 and '2 diesel'uxiliary boards are energized.
f.
Loss of voltage and degraded voltage relays OPERABLE on 4-kV, shutdown boards
'A, B, C, and D.
g.
Shutdown buses 1 and 2
energized.
h.
The 480-V reactor motor-operated valve (RMOV) boards 1D 6 1E are energized with motor-generator (mg) sets lDN, 1DA, 1EN',
and 1EA in service.
4.
The three 250-V. unit batteries,,
.the four shutdown board
'batteri'es, a battery charger for eachbattery, and associated battery boards are OPERABLE.
4.
Undervoltage Relays a.
(Deleted) b.
Once every 18 months, the conditions under
,which the loss of voltage and degraded voltage relays are required; shall be simulated with an undervoltage on each shutdown board to demonstrate that the associated diesel generator will start.
BFN Unit 1 3.9/4.9-6 Amendment 186
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE 'VALLEY AUTHORITY DOCKET NO. '50-260
.BROWNS FERRY.NUCLEAR PLANT UNIT 2 AI1ENDMENT TO FACILITY OPERATING LICENSE Amendment No. 199 License No. DPR-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
'The appl.ication for amendment by Tennessee Valley Authority (the licensee) dated September 13, 1991 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and, the Commission's'ules 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,endangeri'ng the health and'afety of the public,,and (ii) that such activities wil.l be conducted in compl,.iance 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 regul'ations and all appli'cable requirements have been satisfied.
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 Facil,ity Operating License No. DPR-52 is hereby amended to read as follows:
(2)
Technical'S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 199, 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 its date of issuance and shall be implemented no later than November 6, 1991.
FOR THE NUCLEAR'EGUL'ATORY COHHISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 4, 1991 Frederick J.
Heb n, Director Project Directorate II-4 Division of'Reactor Projects - I/II Office of,Nucl'ear Reactor Regulation.
II 41
ATTACHMENT TO.LICENSE AMENDMENT NO.1 99 FACILITY OPERATINC LICENSE NO. DPR-52 DOCKET NO. 50'-260 Revise the Appendix A Technical Specifications, by removing the pages identified b'elow and inserting the enclosed;pages.
The revised pages are identified by thf captioned amIendment number and cortain marginal lines indicating the area of change.
- Denotes overleaf page.
REMOVE 3'.2/4.2-48 3.2/4.2-49 3.'9/4.9-5 3.9/4.9-6 3.9/4.9-15 3.9/4.9-15a INSERT 3.2'/4.2-48*
3.2/4.2-49 3'.9/4. 9-5 3.9/4.9-6 3.9/4. 9-15*
3.9/4.9-15a.
TABLE 4.2.B (Continued)
SURVEILLANCE REQUIREMENTS FOR INSTRUMEHTATIOH THAT INITIATE OR CONTROL THE CSCS Function Core Spray Loop A Discharge Pressure (PI.75-20)
Core Spray Loop B Discharge Pressure (PI-75-48)
Functional Test H/A H/A Calibration Once/6 months Once/6 months Instrument Check Once/day Once/day RHR Loop A Discharge Pressure (P I 51)
RHR Loop B Discharge Pressure (PI-74-65)
Instrument Channel-RHR Start Instrument Channel Thermostat (RHR Area Cooler Fan)
Instrument Channel Core Spray A or C Start Instrument Channel-Core Spray B or D start Instrument Channel-Thermostat (Core Spray Area Cooler Fan)
H/A H/A Tested during functional test of RHR pump (refer to section 4.5.8) once/month Tested during functional test of core spray (r'efer to section 4.5.A).
Tested during functional test of core spray (refer to section 4.5.A).
once/month Once/6 months Once/6 months N/A Once/6 months H/A H/A Once/6 months Once/day Once/day N/A H/A H/A H/A H/A
'P
TABLE 4.2.8 (Continued)
SURVEILLANCE REOUIREMENTS FOR INSTRUMEHTATIOH THAT INITIATE OR CONTROL THE CSCS Function RHR Area Cooler Fan Logic Functional Test Tested during functional test of instrument
Ho other test required.
Calibration H/A Instrument Check H/A Core Spray Area Cooler Fan Logic Instrument Channel Core Spray Motors A or D Start Instrument Channel Core Spray Motors B or C Start Tested during logic system functional test of instru-ment channels, core spray motor start and thermostat (core spray area cooler fan).
Ho other test required.
Tested during functional test of core spray pump (refer to section 4.5.A) ~
Tested during functional test of core spray pump (refer to secti~n 4.5.A) ~
N/A H/A H/A N/A N/A H/A Instrument Channel
- Core Spray Loop 1 Accident Signal Tested during logic system functional test of core spray system.
H/A N/A Instrument Channel-Core Spray Loop 2 Accident Signal RNRSll Initiate Logic RPT Initiate Logic RPT Breaker Tested during logic system functional test of core spray system.
Once/18 months Once/month Once/operating cycle H/A N/A N/A H/A H/A N/A H/A H/A
Cl C
'4 A
C RICAL 'SYS E
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.
Auxil E ect ical E ui ment 4.9.A.
.Aux a
E ectrica S ste 3.
Buses and Boards Available 3.
Logi'c Systems, a.
The respective start bus is energized for each common station-service transformer designated as an offsite power source.
a.
Both divisions of the common accident signal logic system shall be tested every 18 months to demonstrate that it will function on actuation.of the. core spray system of each reactor to provide an automatic start signal to all 4 units 1 and 2
diesel generators.
b.
The 4-kV bus ti'e board is energized and capable of supplying power to the units 1 and 2 shutdown boards if a cooling tower transformer is designated as an offsite power source; b.
Once every '18 months, the,condi'tion, under which the 480-volt load
- shedding. logic system is required shall be simulated using pendant test switches and/or
,pushbutton test switches
,to demonstrate that the load shedding logic system would initiate load shedding signals on the diesel auxiliary
- boards, RMOV'oards, and
,the 480-V shutdown boards.
c.
The. units 1 and 2 4-kV shutdown boards are energized.
BFN Unit 2 3.9/4.9-5 Amendment 1.99
0
I 4
AUXILIARY CTR CAL S STEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.
Auxil a E ectr cal E ui ment 3.,9.A.3. (Cont'd) 4.9.A.
Auxi a
Elect ca S ste d.
The 480-V shutd'own boards 2A and 2B are, energized.
e.
The units, 1 and 2 diesel auxiliary boards are energized.
f.
Loss of voltage and degraded voltage relays OPERABLE. on 4-kV shutdown boards A, B, C, and D.
g.
Shutdown buses 1 and 2
energized..
h.
'The 480-V reactor motor-operated valve (RMOV)
'boards 2D 6 2E are energized
.:with motor-generator (mg) sets
- 2DN, 2DA, 2EN, and 2EA in service.
4.,
The three 250-V unit batteries,
,the four shutdown board batteries, a battery, charger for each battery, and associated
.battery boards are
- OPERABLE.
4.
Undervoltage Relays a.
(Deleted) b.
Once every 18 months, the conditions under which the loss of voltage and degraded voltage relays are required shall be simulated with an undervoltage on each shutdown board to demonstrate that the associated diesel generator will start.
BFN Unit.2 3.9/4.9 6
,Amendment 199
4 AUXILIARYELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILL'ANCE 'REQUIREMENTS 3.9.C.
0 eration in Cold Shutdown 4.9;C 0 eration in Cold Shutdown Whenever the reactor 'is in COLD SHUTDOWN CONDITION with'rradiated fuel in the
- reactor, the availability of electric power. shall be as specified in Section 3.9.A except as specified herein.
1.
No additional surveillance is required.
l.
At least
.two 'Units 1 and 2
diesel generators and their associated 4-kV shutdown boards shall be OPERABLE.
2.
An additional source of power-energized and capable of supplying power to the Units 1 and '2 shutdown boards consisting of at 1'east one of the following:
a.
One of the offsite power sources specified in 3.9.A.l.c.
b.
A third OPERABLE diesel generator.
3.
At least one 480-V shutdown board for each un'it must be OPERABLE.
4.
One 480-V RMOV board mg set is required for each RMOV board (2D or 2E) required'o support operation of the RHR system in accordance with 3.5.B.9.
BFN Unit 2 3.9/4.9-15 AMENDMEHT'HO 1 8 6
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4.
AUXILIARYELEC RICAL S S
EM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.'9.D Unit e el Ge ators Re ui d for U t 2 0 e at o
4.9.D U t e u D esel Ge e ators ed t
0 era 'o 1.
Whenever any of the following equipment is required to be OPERABLE in accordance with the corresponding section of these technical specifi-
- cations, the Unit 3,diesel generator aligned to supply emergency power to that equipment shall be OPERABLE.
a.
Standby gas treatment train C in accordance with T.S. 3.7.B (diesel generator 3D).
b.
Control room emergency, ventilation train B'n accordance with T.S. 3.7.E (diesel generator 3B or 3C).
2.
When the diesel generator aligned to supply emergency power to the equipment in 3.9.D.l.a -or b is inoperable, the equipment may be considered OPERABLE for the purpose of satisfying the corresponding technical specification during the succeeding 30 days provided that the redundant train(s) of'quipment and their normal and emergency power supplies are OPERABLE.
- 3. If Specification 3.9.D.2 cannot be met, the affected equipment shall be declared inoperable.
l.a Diese Ge e ators Surveillance requirements are as. specified in T.S. 4.9.A.l.a, 4.9.A.l.c, 4.9.A.l.d and 4.9.A.l.e.
l.b DC Powe S ste Surveillance requirements are as specified in T.S.
4.9.A.2.
l.c Lo ic S stems Both divisions of the common accident signal logic system shall be tested every 18 months to demonstrate that it will function on actuation of the core spray system of the reactor to provide an automatic start signal to each diesel generator.
l.d Unde volta e
Re a s Surveillance requirements are as specified in T.S. 4.9.A.4.
2.
No surveillance required.
3.
No surveillance required.
BFN Unit 2 3,9/4 '
15a Amendment 199
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCI.EAR PLANT UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE
'Amendment No..158 License No. 'DPR-68 1.
The, Nuclear Regulatory Commission (the Commission) has found. that:
A.
The application for amendment
.by Tennessee Valley Autgority (the licensee) dated September 13, 1991, complies with the standards and requirements of the Atomic.Energy:Act of 1954, as amended (the Act),
and the Commission' 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 th,is.amendment;will not'be,inimical to the common defense and security or to the health, and safety of the publi'c; 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.,
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2.
Accordingly, the license is amended'y changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating, Li'cense No.
DPR-33 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. 158, are hereby incorporated in the license.
The l.icensee shall operate the facility in accordance;with the Technical Specifications.
3.
This license amendment's effective as of its date of issuance and shall be implemented no later than November 6, 1991.
FOR THE NUCLEAR REGULATORY COMMISSION Frederick J.
Hebd n, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications, Date of Issuance:
November 4, 1991
4i II il
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ATTACHMENT TO LICENSE, AMENDMENT NO.
158'ACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Revise the Appendix A, Technical Specifications by removing the pages identifiecl below and inserting the enclosed pages.
The revised pages are identified by the captioned amendmerIt number and contain marginal lines indicating the area of change.
- Denotes overleaf page.
REMOVE.
3.2/4.2-47
'3.2/4. 2-48'
.9/4. 9-'5 3.9/4.9-6 3.9/4.9-14a 3.9/4. 9-14b INSERT 3'. 2/4. 2-47*
3.2/4'.2-48 3.9/4.9-5, 3.9/4.9-6 3.9/4.9-14a 3.9/4.9-14b*
0 1I
TABLE 4'.B (Cont'd)
SURVEILLANCE REQUIREHEHTS FOR INSTRUNEHTATION THAT INITIATE OR CONTROL THE CSCS Function Core Spray Loop A Discharge Pressure (PI-75-20)
Core Spray Loop B Discharge Pressure (PI-75-48)
RHR Loop A Discharge Pressure (PI-74-51)
RHR Loop B Discharge Pressure (PI-74-65)
Instrument Channel RNR Start I
Instrument Channel-Core Spray B or D start Instrument Channel-Thermostat (Core Spray Area Cooler Fan)
Instrument Channel Thermostat (RHR Area Cooler Fan)
Instrument Channel-Core Spray A or C Start Functional Test H/A N/A N/A H/A Tested during functional test of RNR pump (refer to Section 4.5.8) once/month Tested during functional test of core spray (refer to Section 4.5.A);
Tested during functional test of core spray (refer to Section 4.5.A) ~
once/month
- Calibration once/6 months once/6 months once/6 months once/6 months N/A once/6 months H/A H/A once/6 months Instrument Check once/day once/day once/day once/day H/A H/A N/A H/A H/A
0 IC<
TABLE 4.2.B (Cont'd)
SURVEILLANCE REQUIRENENTS FOR IHSTRUHEHTATIOH THAT INITIATE OR CONTROL THE CSCS Function Functional Test Calibration Instrument Check RHR Area Cooler Fan Logic Core Spray Area Cooler Fan Logic Instrument Channel-Core Spray Notors A or D Start Instrument Channel Core Spray Notors B or C Start Tested during functional test of instrument
Ho other test required.
Tested during logic system functional test of instru-ment channels, core spray motor start and thermostat (core spray area cooler fan).
No other test required.
Tested during functional test of core spray pump (refer to Section 4.5.A).
Tested during functional test of core spray pump (refer to Section 4.5.A).
H/A H/A H/A H/A N/A H/A RPT Initiate Logic RPT Breaker Instrument Channel
- Core Spray Loop 1 Accident Signal Instrument Channel-Core Spray Loop 2 Accident Signal once/month once/operatihg cycle Tested during logic system functional test of core spray system.
Tested during logic system functional test of core spray system.
N/A H/A N/A N/A H/A H/A H/A RHRSII Initiate Logic once/18 months N/A H/A
II II
4 'UXIL A CTR CAL SYSTEM,'IMITING:CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS'.9.A.
A il a ec ca ui ent 4.9.A.
ux a
ect a
S ste 3.
es d
o v i ble 3.
a.
The respective start bus is energ'ized for each common station-service transformer designated as an offsite power source.
a.
Both divisions of the accident signal logic system shall be tested.every 18 months to demonstrate that it will function on actuation of the core spray system of the reactor to provide an automatic start signal
'to all 4 diesel generators.
b.
The 4-kV bus tie board is energized if a cooling tower transformer is designated as an offsite power source.
c.
The. 4-kV shutdown boards (3EA, 3EB,
- 3EC, 3ED) are energized.
d.
The 480-V shutdown boards.
3A and '3B are energized.
BFN Unit 3 3.9/4.9-5 Amendment 158
llew
R C RIC SYSTE LIMITING CONDITIONS 'FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.
Auxil a Electr cal u
ent 4.9.A.
ect ical S stem 3.9.A:.3. (Cont'd) e.
Loss of voltage and degraded voltage relays OPERABLE on 4-kV shutdown boards
- 3EA, 3EB,
- 3EC, and 3ED.
f.
The 480-V diesel auxiliary boards 3EA and 3EB are energized.
g.
The 480-V reactor motor-operated valve (RMOV) boards 3D Ec 3E are energized with motor-generator (mg) sets
'3DN, 3DA, 3EN, and 3EA in service.
4.
The 250-V shutdown board.
3EB battery, all three unit batteries, a battery charger for each battery,,
and associated battery boards are OPERABLE.
4., Undervolta e Rela s
a.
,(Deleted) b.
Once every 18 months, the conditions under.
which the loss of voltage and degraded voltage relays are required shall'e simulated with an undervoltage on each shutdown board to demonstrate that the associated diesel generator will start.
BFN Unit 3 3.9/4.9-6
,Amendment 158
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4 AUXILIA C
IC L S S
M LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.D Unit Diesel Generato s
Re u ed or t
0 eration 4.9.D t
Re u D ese e
e ators ed or U t 0
e at o
1.
Whenever any of the following equipment is required to be OPERABLE in accordance with,the corresponding section of any units technical specifi-
- cations, the Unit 3 diesel generator aligned to supply emergency power to that equipment shall be OPERABLE.
a.
Standby gas treatment train C in accordance with T.S. 3.7.B (diesel generator 3D).
'b.
Control room emergency ventilation train B in accordance with T.S. 3.7.E (diesel generator 3B or 3C).
2.
When the diesel generator aligned to supply emergency power to the equipment in 3.9.D.l.a or b is inoperable, the equipment may be considered OPERABLE for the purpose of satisfying the corresponding technical specification during the succeeding 30 days provided that the redundant train(s) of equipment and their normal and emergency power supplies are OPERABLE.
- 3. If Specification 3.9.D.2 cannot be met, the affected equipment shall be declared inoperable.
l.a Diese Gene at s
Surveillance requirements are as specified in T.S. 4.9.A.l.a, 4.9.A.l.c, 4.9.A.l.d and 4.9.A.l.e.
l.b DC ower S ste Surveillance requirements are as specified in T.S.
4.9.A.2.
Both divisions of the common accident signal logic system shall be tested every 18 months to
)
demonstrate that it will function on actuation of the core spray system of the Unit 2 reactor to provide an automatic start signal to each diesel generator.
l.d U de volta e
ela s
Surveillance requirements are as specified in T.S. 4.9.A.4.
2.
No surveillance required.
3.
No surveillance required.
BFN Unit 3 3.9/4.9 14a Amendment 158
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THIS PAGE INTENTIONALLYLEFT BLANK BFN Unit 3 3.9/4.'9-14b AMENDMENT1N. T 5.0
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