ML18029A544
| ML18029A544 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/02/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Tennessee Valley Authority |
| Shared Package | |
| ML18029A545 | List: |
| References | |
| DPR-33-A-117, DPR-52-A-112, DPR-68-A-088 NUDOCS 8505200165 | |
| Download: ML18029A544 (68) | |
Text
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UNITED STATES Nti. CEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROMNS FERRY NUCLEAR PLANT UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 117 License No. DPR-33 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated October 22, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comnission'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 CoIImrission; 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 Comnission's regulations and all applicable 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 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 B, as revised through Amendment No. lip, 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 issuance.
FOR THE N
CLEAR REGllLATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
Hay 2, 1985 Domenic B. Vassallo, Chief Operating Reactors Branch b2 Division of Licensing
ATTACHMENT TO LICENSE AMENOMENT NO.
FACILITY OPERATING LICENSE NO.
DPR-33 OOCKET NO. 50<<259 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
292, 293, 293a, 294, 294a, 295, 296, 297, 297a,
- 298, 298a, 299, 300, 301 2.
Insert new pages.
- 292a, 295a, 296a 3.
The marginal lines on these pages denote the area being changed.
4.
Remove page.
297b
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREHENTS 3.9 AUXILIARYELECTRICAL SYSTEM 4.9 AUXILIARYELECTRICAL SYSTEM Applies to all the auxiliary electrical power system.
O~b'ective To assure an adequate supply of electrical power for operation of those systems required for safety.
S ecification Applies to the pyryodic testing requirements of the auxil:ary electrical system:
~Ob'ective Verify the operability of the auxiliary electrical system.
S ecification A.
Auxilia Electrical E ui ment A.
Auxiliar Electrical S stem 1.
The reactor shall not be started up (made critical}
from the cold condition unless the following are satisfied:
a.
Diesel generators A,
B, C, and D operable.
b.
Requirements 3.9.A.3 through 3.9.A.6 are met.
1.
Diesel Generators a
~
Each diesel generator shall be manually started and loaded once each month to demonstrate opera-tional readiness.
The test shall continue for at least a 1-hour period at 75/ of rated load or greater.
c ~
At least two of the following offsite power sources are available:
(1}
The 500-kV system is available to the units 1 and 2 shutdown boards'hrough the unit 1
station-service transformer TUSS 1B with no credit taken for the two 500-kV Trinity lines. If the unit 2 station-service trans-former is the second
- source, a minimum of two 500-kV lines must be available.
b.
During the monthly generator test, the diesel generator starting air com-pressor shall be checked for operation and its ability to recharge air receivers.
The operation of the diesel fuel oil transfer pumps shall be demonstrated, and the diesel starting time to reach rated voltage and speed shall be logged.
Once per oper'ating
- cycle, a test will be conducted simu-lating a loss of Amendment No.
117 292
LIMITING CONDITIONS R OPERATION SURVEILIANCE REQUIREMENTS UNIT 1
3.9 AUXILIARYELECTRICAL SYSTEM 4.9 AUXILIARYELECTRICAL SYSTEM (2)
The 500-kV system is available to the units 1 and 2
shutdown boards through the unit 2 station-service trans-former TUSS 2B with no credit taken for the two 500"kV Trinity lines.
If the unit 1
station-service transformer is the second
- source, a
minimum of two 500-kU lines must be available.
(3)
The Trinity 161-kU line is available to the units 1 and 2
shutdown boards through both common station-service
.transformers.
NOTES
~OR (3):
(a) If unit 3 is claiming the Trinity line as an offsite
- source, see unit 3 technical specifi-
- cations, section 3.9.A.l.c.2.
offsite power and similar conditions thathould exist with the presence of an actual safety-injection signal to demonstrate the following:
(1)
Deenergization of the emer-gency buses and load shedding from the emergency buses.
(2)
The diesel starts from ambient con-dition on the auto-start signal, ener-gizes the emer-gency buses with perma-nently connected
- loads, ener-gizes the auto-connected emer-gency loads through load'equencing, and operates for greater than or equal to five, minutes while its gene-rator is loaded with the emer-gency loads.
(3)
On diesel gene-rator breaker trip, the loads are shed from the emergency buses and the diesel restarts on the auto-start signal, the emergency buses are energized with permanently Amendment No. ll?
292a
SURVEILLANCE REQUIREHENTS
~.9 AUXILIARYELECTRICAL SYSTEH 4.9 AUXILARY ELECTRICAL SYSTEH (b) If unit 2 xs 1n cold
- shutdown, only one common station-service transformer is required.
(4)
The Athens 161-kV line is available to the units 1 and 2
shutdown boards through a
common station-service transformer when unit 2 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.
2.
The reactor shall not be started up (made critical) from the hot standby condition unless all of the following conditions are satisfied:
At least one offsite power source is available as speci-fied in 3.9.A.l.c.
connected
- loads, the
>Puto-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 given an annual inspection in accordance with instructions based on the manu"acturer's recommendations.
e.
Once a month a sample of diesel fuel shall be checked for quality.
The quality shall be within acceptable limits specified in Table 1
of the latest revision to ASTH D975 and logged.
2.
DC Power System - Unit Batteries (250-V),
Diesel-Generator Batteries (125-V) and Shutdown Board Batteries (250-V) b.
Three units 1 and 2
diesel generators shall be operable.
Amendment No.
117 293
LIMITING CONDITIONS FOR OPERATION
- 3. 9 AUXILIARYELECTRICAL SYSTEl'I SURVEILLANCE REQUIREHENTS 4.9 AUXILIARYELECTRICAL SYSTEM!
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.
a 0 Eve~ week the spebjfic gravity, volta'ge and temperature of the pilot cell and overall battery voltage shall be measured and logged.
(2)
A fourth operabl.e units 1 and 2 diesel generator.
d.
Requirements 3.9.A.3 through 3.9.A.6 are met.
3.
Buses and Boards Available a
~
The 4-kU bus tie board is energized and capable of supplying power to the units 1 and 2
shutdown boards if a cooling tower transformer iN designated as an offsite power source.
The units 1 and 2
4-kV shutdown boards are energized.
The 480-V shutdown boards lA and 1B are energized.
The respective start bus is energized for each common station-service transformer designated as an offsite power source.
c ~
A battery rated discharge (capacity) test shall be performed and the
- voltage,
.ime, and output current measurements shall be logged at inter-vals not to exceed 24 months.
3.
Logic Systems a
~
Both divisions of the common accident signal logic system shall be tested every 6 months to demon-st=ate 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 gene-rators.
Every three 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.
e.
The units 1 and 2
diesel auxiliary boards are energized.
Amendment No. 1l7 293a
3'.9 AR'ILIARY ELECTRICAL SYSTEli f.
Loss of voltage and degraded voltage relays operable on 4-kV shutdown boards A, B, C, and D.
g.
Shutdown busses 1 and 2 energized.
h.
The 480-V reactor motor-operated valve (RMOV) boards 1D 6 lE are energized with motor-generator (mg) sets
- 1DN, 1DA, 1EN, and lEA in service.
4.
The three 250-V unit, batteries, the four shut-down board batteries, a
battery charger for each
- battery, and associated battery boards are operable.
5.
Logic Systems a.
Common accident signal
~
logic system is operable.
480-V load shedding logic system is operable.
6.
There shall be a minimum of 103,300 gall.ons oE diesel fuel in the standby diesel-generator fuel tanks.
SURVEILLANCE REgUIREi'1ENTS 4.9 AUXILIARYELECTRICAL SYSTE>j b.
Once every 6 months, the cpndition under which~Pe 480-V load shedding logic system is required shall be simulated using pendant test switches and/or push-button 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 shut-down boards.
4.
Undervoltage Relays a.
(Deleted) b.
Once every 6 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.
c.
The loss of voltage and degraded voltage relays.which start.
the diesel generators from the 4-kV shutdown boards shall be calibrated annually for trip and reset and the measurements logged.
These relays +all be calibrated as specified in Table 4.9.A.4.c.
Amendment No. 117 294
LIi'1ITING CONDITIONS OR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEH SURVEIILANCE RE UIREHENTS 4.9 AUXILIARYELECTRICAL SYSTEN d.
4-kU shutdown board voltages shall be reposed once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
5.
480-U R10U Boards lD and 1E I
a.
Once per operating cycle the automatic transfer feature for 48Q-V tu'iOV boards 1D and lE shall be functionally tested to verify auto-transfer capability.
Amendment No.
117 294a
LI~IITING CONJ ITIONS F
OPERATION
. 3.9 AUXIlIARYELECTRICAL SYSTE>l B.
0 eration with Ino erable E~ui ment Whenever the reactor is in Startup mode or Run mode and not in a cold condition, the availability of electric power shall be as specified in 3.9.A except as speci. fied herein.
SURVEILLANCE REQUIREl'1ENTS 4.9 AUXILIARYELECTRICAL SYSTE'1 B.
0 aration with I~no erable E~ui ment t
r i-1.
When onl~one offsite power source is operable, all units 1 and 2 diesel generators and associated loards must be demon-strated to be operable immediately and daily thereafter.
1.
From and after the date that only one offsite power source is available, reactor operation is per-missible for 7 days.
2.
From and after the date that the 4-kV bus tie board becomes inoperable, reactor operation is permissible indefinitely provided one of the required offsite power sources is not supplied from the 161-kV system through the bus tie board.
3.
When one of the units 1
and 2 diesel generator is inoperable, continued reactor operation is permissible during the succeeding 7 days, provided that 2 offsite power sources are available as specified in 3.9.A.l.c and all of the CS, RHR (LPCI and containment cooling)
- systems, and the remaining three units 1 and 2
diesel generators are operable.
If this requirement cannot be
- met, an orderly shutdown shall be initiated and the reactor shall be shut down and in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
3.
4.
When a required offsite power source is unavailable to unit 1
because the 4-kV bus tie board or a start bus is inoperable, all unit 1
and 2 diesel generators and associated boards shall be demonstrated operable immediately and daily thereafter.
The remaining offsite source and associated buses shall be checked to be energized daily.
When one of the units 1
and 2 diesel generators is found to be inoperable, all of the CS, RHR (LPCI and containment cooling) systems and the remaining diesel generators and associated boards shall be demonstrated to be operable immediately and daily thereafter.
When one 4-kV shutdown board is found to be
'noperable, all remaining 4-kV shutdown boards and associated diesel gene-
- rators, CS, and RHR (LPCI and containment cooling) systems supplied by the remaining 4-kV shutdown boards shall be demon-,
strated to be operable immediately and daily thereafter.
Amendment No. 117 295
LIHITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIRE".IENTS
.3.9 AUXILIARYELECTRICAL SYSTEH 4.9 AUXILIARYELECTRICAL SYSTEH 4.
When one units 1 and 2
4-kV shutdown board is inoperable, continued reactor operation is permissible for a period of 5 days provided that 2 offsite power sources are available as specified in 3.9.A.l.c and the remaining 4-kU shutdown boards and associated diesel generators, CS, RHR (LPCI and containment cooling) systems, and all 480-U emergency power boards are operable.
If this requirement cannot be
- met, an orderly shutdown shall be initiated and the reactor shall be shut down and in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
5.
When a shutdown bus is found tq >be inoperable, all 1 aN 2 diesel gene-rators shall be proven operable immediately and daily thereafter.
6.
When one units l and 2
diesel auxiliary board is found to be inoperable, the remaining diesel auxiliary board and each unit 1 and 2
diesel generator shall be proven operable immediately and daily thereafter.
5.
7.
When one of the shutdown buses is inoperable, reactor operation is permissible for a period of 7 days.
When one of the 480-U diesel auxiliary boards becomes inoperable, reactor operation is permissible for a period of 5 days.
From and after the date that one of the three 250-V unit batteries and/or its associated battery board is found to be inoperable for any
- reason, continued reactor operation is permissible during the succeeding 7 days.
Except for routine surveillance
- testing, NRC shall be notified within 24 Amendment No. 117 295a
3.9 AUXII.IARYELECTRICAL SYSTEH SURVE LLANCE REQUIRE."1ENTS 4.9 AUXILIARYELECTRICAL SYSTE,"1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the situation, the precautions to be taken during this period, and the plans to return the failed component to an operable state.
8.
From and after the date that one of the 250-V shutdown board batteries and/or its associated battery board is found to be inoperable for any
- reason, continued reactor operation is permissible during the succeeding five days in accordance with 3.'9.B.7.
10.
When one division of the logic system is inoperable, continued reactor operation is permissible under this condition for seven
- days, provided the CSCS requirements listed in specification 3.9.B.3 are satisfied.
The NRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the situation, the precautions to be taken during this period, and the plans to return the failed component to an operable state.
(deleted)
The following limiting conditions for operation exist for the undervoltage relays which start the diesel generators on the 4-kV shutdown boards.
a.
The loss of voltage relay channel which starts the diesel generator for a complete loss of Amendment No.
117 296
~
rj LDlITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEH SURVEILLANCE REQUIREilENTS 4.9 AUXILIARYELECTRICAL SYSTEH b.
c ~
voltage on a 4-kV shutdown board may be inoperable for 10 days provided the degraded voltage relay channel on that shutdown board is operable (within the surveillance schedule of 4.9.A.4.b).
The degraded voltage relay channel which starts the diesel generator for degraded voltage on a 4-kV shutdown board may be inoperable for 10 days provided the loss of voltage relay channel on that shutdown board is operable (within the surveillance schedule of 4.9.A.4.b).
One of the three phase-to-phase degraded voltage relays provided to detect a degraded voltage on a 4-kV shutdown board may be inoperable for 15 days provided both of the following conditions are satisfied.
1.
The other two phase-to-phase degraded voltage relays on that 4-kV shutdown board are operable (within the surveillance schedule of
'.A.4.b).
Amendment No. 117 296a
Th loss of voltage relay channel on that shutdown board is operable (within the surveillance schedule of 4.9.A.4.b).
d.
The degraded voltage relay channel and the loss of voltage relay channel on a 4-kV shutdown board may be inoperable for 5 days provided the other shutdown boards and under-voltage relays are operable.
(Within the surveillance schedule of 4.9.A.4.b).
~ LIilITINGCONDITIONS OPERATION
, 3.9 AUXILIARYELECTRICAL SYSTE>1 2 ~
e SURVEILLANCE REQUIRE>1ENTS 4.9 AUXILIARYELECTRICAL SYSTE,'1 12.
When one 4SO-V shutdown board is found to be inoperable, the reactor will be placed in hot standby within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
and cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 13. If one 480-V R1QV board mg set is inoperable, the reactor may remain in operation for a period not to exceed seven
- 14. If any two 480-V BlQV board mg sets become inoperable, the reactor shall be placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Amendment No.
117 297
'- LIMITING CONDITIONS FOR OPERATION AUXILIARYELECTRICAL SYSTEM
- 15. If the requirements for operating in the conditions specified by 3.9.B.l through 3.9.B.14 cannot be met, an orderly shutdown shall be initiated and the reactor shall be shut.
down and in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.9 AUXILIARYELECTRICAL SYSTEM Amendment No.
117 297a
LIHITING CONDITIONS FOR OPERATION d.9 AUXILIARYELECTRICAL SYSTEH SURVEILLANCE REQUIREHENTS 4.9 AUXILIARYELECTRICAL SYSTE.'I C.
0 eration in Cold Shutdown Whenever the reactor is in cold shutdown condition with irradiated fuel in the
- reactor, the availability of electric power shall be as specified in Section 3.9.A except as specified herein.
1.
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 least one of the following:
a
~
One of the offsite power sources specified in 3.9 '.l.c.
b.
A third operable diesel generator.
3.
At least one 480-V shutdown board for each unit must be operable.
4.
One 480-V RHOV board mg set is required for each RHOV board (1D or lE) required to support operation of the RHR system in accordance with 3.5.B,9.
Amendment No. 117 298
Table 4.9.A.¹.C VOLTAGE REf AY SETPOINTS/PTESEL GENERATOR START Rela Location Tri Level Settin Remarks 1.
4-kV Shutdown Boards Trip Setpoint:
Allowable Values:
Trip Range:
Reset Setpoint:
Allowable Values:
Reset Range:
0 volts with a 1.5-second time delay
+.1 second 1.4 to 1.6 seconds 2870-V
+ 2$ of 2870-V 2813-V to 2927-V Start diesel generators on lossof offsite power.
Undervolta e
2.
4-kV Shutdown Boards Trip Setpoint:
3920 Second level undervoltage sensing Allowable Values'.
3900-3940 relays start diesel generator Reset Setpoint:
Reset at
< 1.5$ above trip value on degraded voltage.
3.
4-kV Shutdown Boards (Timers shown for 4-kV shutdown board A.
4-kV shutdown boards B, C, and D, similar, except for change of suffix.
Timer 2-211-1A 2-211-2A 2-211-3A 2-211-4A Setpoint (seconds) 0.3
+ 10$
¹.0
+ 10$
6.9
+ 10$
1 ~ 3
+ 10$
Critical Time (seconds)
I N/A N/A 8.2 1.5 Auxiliary timers for second level undervoltage sensing relays.
The setpoint ranges specified assure that the operating times will be below the critical times specified.
These ranges are based on timer repeatability of + 5$ as specified by the manufacturer.
~e Amendment No. 117 298a
3 9
BASES elect The objective of this specification is to assure an ade"uat ctrical power to operate facilities to cool the la d
qua e source of and to o crate th o
e p ant urging shutdown p
e e engineered safeguards following an accident.
There ar three sources of alternating current elect 1
gy A ~
na the 161-kV transmission
- system, the 500-kV trans ec rica energy ave ~able na diesel generators.
em, e
transmission
- system, and the The unit station-service transformer B f h
sta service transformer B for unit 2 provide noninter or unit or the unit sta p
e nonxn erruptzble sources of s ut own boards.
Auxiliar er rom e
- V transmission system to the units 1 and 2
A xiliary power can also be supplied from the 161-kV transmission system through the common stat throu h t on s a ion-service transformers or 4-kU bus tie board ma remai roug he cooling tower transformers by way of the bu o
e us tie oard.
The o
the re uired offsite f
h ar may remain out of service indefinitely provided ite power sources is not supplied from the 161-kU one system through the bus tie board.
The minimum fuel oil requirement of 103 300 11 sev en days of full load operation of three diesels and is conservativel ga ons is sufficient for based on availability of a replenishment supply.
The de raded volta e
g ge sensing relays provide a start signal to the.diesel generators in the event that.
a deteriorated volta d'o age con ition exists on own oards.
This starting signal is independent of the
'tarting signal generated by the complete loss of volta e r 1
d
'1) continue to function and s
age re ays an wil) volta e should the 1
and start the diesel generators on compi t 1
f g
he loss of voltage relays become inoperable.
The 15-da ee osso de z
inoperable time limit specified when one f th h
h ne o
e t ree phase-to-phase egraded voltage relays is inoperable is justified based on the two out of three permissive logic scheme provided with these relays.
A 4-kV shutdown board is allowed to be out of o eriod to e ou o
operation for a brief perio to allow for maintenance and testing prov'd d ll shutdown boa i e a
remaining 4-kU oards and associated diesel generators, CS,
- boards, and all emergency 480-V power boards are operable batter batter There are eight 250-U dc battery systems h f h
h eac o
w ic consists of a
- ery, attery charger, and distribution equipment.
Three of these unit mot systems provide power for unit control fun t'c ions, operative power for nit motor loads, and alternative drive power for a 115-V ac unit-preferred mg set.
One 250-V dc system p o 'd f
em provi es powe r for common plant and transmission system control funct d
ac lant-c ions, rive power for a 115-V p an -preferred mg set, and emergency drive po f
large motor loads.
The four remainin s
ower or certain unit systems deliver control power to Each 250-V dc shutdown board control power su 1
ca b t b t h
- ery, a tery c arger, or from a spare charger.
The chargers are powered from normal plant auxiliary power or from the stindb the control power supply and the h
d ro resistance short circuits e
s ut own board are cleared b
fuses located in the respective control power 1
E located in the reactor building near the shutd b
supp y.
ach power su I
is Each batter is e
s ut own board it supplies, a
ery is located in its own independently ventilated battery room.
Amendment No.
117 299
The 250-U dc s
s e
c sys em is so arranged, and the battereies sized so that the loss of any one unit battery will not prevent the safe shutdown and cooldown of all three units in the event f th 1
f and a design basis accident in any one unit.
Los f
o e
oss o
offsite ower d
g'afeguard control circuits is annunciated in the main batter af control room of the unit affected.
The 1
f 250-V oss o
one shutdown board which it su lies.
exy affects normal control power only for the 4 160-V pp ies.
The station battery supplies loads tlht are not or e,
-, ~shutdown board essential for safe shutdown and cooldown f th 1
battery was not considered in the accident load calculations There are two 480-U ac RMOV boards that contain m
1'h 480-U RMOU h
ac boards have an automatic transfer from their norma to a ternate power source (480-V ac shutdown boards).
The m
e act. as electrical isolators to prevent f
lectrical divisions due to an automatic transfer.
Th 4
en a
au t from propagatin between boards involved rovide mot ic rans er.
The 480-V ac RMOV provide motive power to valves associated with the LPCI mode of the RHR system.
Having an mg set out of service assurance that full RHR (LPCI)
S'
) capacity will be available when re uired.
':.ce sufficient equipment is available to maintain the minimum complement required for RHR (LPCI) o erat o
- ation, a 7-day servicing p~ri~d i j s i ie aving two mg sets out of service can considerably reduce equipment availability; therefore, the affected unit shall be a
cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
uni s
a e placed in The offsite ower source r p
equirements are based on the capacity of the u
respective lines.
The Trinity line is lirn't d t 1
nits because of the load limitations of CSST's A and 8.
rni e o supp ying two o eratin pp ying one operating unit because of the load limitations of the Athens line.
'I'he limitin c
g ondxtxons r
tended to e
system from supplying more than two units in the event a sing e
ai ure in the offsite power system.
Amendment No.
117 300
4.9 BASES The monthl test of th d'ailures an the diesel generators is primarily t h
k f d deterioration in the system since last use, The diesels th d
c ec or will be loaded to at least 75 percent of rated h'l ra e
power w ile en ine and 75-r generator temperatures are stabilized
( b h
-percent load will prevent soot formation in the cylinde s and injection nozzles.
Operation u
to a
p o an equilibrium temperature ensures a
ere is no overheating problem.
The tests also provide an en ine a
generator operating history to be compared with subsequent engine-generator test data to identif and to o correct any mechanical or e iciency efore it can result in a system failure.
The test during refueling outages is more comprehensive, includin procedures that are most effectively condu t d h
include automatic actuation and functional ca abilit n uc e
at t at time.
These the gene ato s ca sta t and b n s ar an e ready to assume load in 10 seconds.
The annual inspection will detect any signs f
1 b
s o
wear ong efore failure.
Battery maintenance with regard to the fl t'
- charge, and electrolyte level will be based on the manufacturer's instruction and sound maintenance practices.
I dd'ecords will b i
e maintained of the battery performance.
The plant batteries will deteriorate with time but preci it f l y.
e ype o
surveillance called for in this specification is that which has been demonstrated through experience to
'd indication off a cell becoming irregular or unserviceable ion b f becomes a failure.
e ong e ore it The equalizing charge, as recommended by the manuf t
manu acturer, is vital to maintaining the ampere-hour capacity of the batter d
ll as recommended.
a
- ery, an wi be applied The testing of the logic systems will verify the abilit f
h s stems to brin y
i g the auxiliary electrical system to running standby a i ity o t e logic readiness with the presence of an accident signal f n ervoltage signal on the 4-kV shutdown boards.
igna rom any reactor or an 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.
REFERENCES 1.
Normal Auxiliary Power System (BFNP FSAR Subsection 8.4) 2.
Sta 8.5)
Standby AC Power Supply and Distribution (BFNP FSAR S b u section 3.
250-Volt DC Power Supply and Distribution (BFNP FSAR Subdection 4.
Memorandum from Gene M. Milhoite to H. J.
Green dated December 4,
1981 (LOO 81120& 664) and memorandum from C. E. Minn to H. J.
Green dated January 10, 1983 (G02 830112 002)
Amendment No. 117 301
~p,R RECy (4
Po Cy
~i oO I
~+
+>>*e>>
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT UNIT'2 AHENDMENT TO FACILITY OPERATING LICENSE Amendment No. 112 License No.
DPR-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated October 22, 1984, 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 Comnission; 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.
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-52 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained i'n Appendices A and B,
as revised through Amendment No. 112, are hereby incorporated in the license.
The licensee shall operate the facili+ in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuagce.
FOR THE NUC EAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 2, 1985 Domenic B. Vassallo, Chief Operating Reactors Branch P2 Division of Licensing
I t
ATTACHMENT TO LICENSE AMENDMENT NO. 112 FACILITY OPERATING LICENSE NO.
DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
292, 293, 293a, 294, 294a, 295, 296, 297, 297a,
- 298, 298a, 299, 300, 301 2.
Insert new pages.
- 292a, 295a, 296a 3.
The marginal lines on these pages denote the area being changed.
4.
Delete page.
297b
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREHENTS AUXILIARYELECTRICAL SYSTEM 4.9 AUXILIARYELECTRICAL SYSTEM Applies to all the auxiliary electrical power system.
O~b'ective
.To assure an adequate supp y of electrical power for operation of those systems required for safety.
S ecification Applies to the peg$ pdic testing requirements of the auxiliary electrical system.
O~b ective Uerify the operability of the auxiliary electrical system.
S ecification A.
Auxiliary Electrical E ui ment A.
Auxiliary Ele'ctrica) System b'.
Diesel generators A,
B, C, and D operable.
Requirements 3.9.A.3 through 3.9.A.6 are met.
C.
At least two of the following offsite power sources are available:
(1)
The 500-kU system is available to the units 1 and 2 'shutdown boards through the unit 1
station-service transformer TUSS 1B with no credit taken for the two 500-kU Trinity lines'f the unit 2 station-service trans-former is the second
- source, a minimum of two 500-kU lines must be available.
292 Amendment N0..112 1.
The reactor shall not be started up (made critical) from the cold condition unless the following are satisfied:
~ e
~
1.
Diesel Generators a.
Each diesel generator shall be manually started and loaded once each month to demonstrate opera-tional readiness.
The test. shall continue for at least a 1-hour period at 75',~ of rated load or great.er.
During the monthly generator test, the diesel generator starting air com-pressor shall be checked for operation and its ability to recharge air receivers.
The operation of the diesel fuel oil transfer pumps shall be demonstrated, and the diesel starting time to reach rated voltage and speed shall be logged.
b.
Once peP operating
- cycle, a test will be conducted simu-lating a loss of
Lii'lITING CONDITIONS FO OPERATION SURVEILLANCE RE UIREi'KNTS Q.9 AUXILIARYELECTRICAL SYSTEH 4.9 AUXILIARYELECTRICAL SYSTEn (3)
The Trinity 161-kV line is available to the units 1 and 2
shutdown boards through both common station-service transformers.
NOTES FOR (3):
(a} If unit 3 is claiming the Trinity line as an offsite
- source, see unit 3 technical specifi-
- cations, section 3.9.A.l.c.2.
Amendment No.
112 292a (2)
The 500-kV system is available to the units 1 and 2
shutdown boards through the unit 2 station-service trans-former TUSS 2B with no credit taken for the two 500-kV Trinity lines.
If the unit 1
station-service transformer is the second
- source, a
minimum of two 500-kV lines must be available.
offsite power and simi ar conditions thatj.would exist with the presence of an actual safety-injection signal to demonstrate the following:
(1)
Deenergization of the emer-gency buses and load shedding from the emergeni" buses.
(2)
The diesel starts from ambient con-dition on. the auto-start
- signal, ener-gizes the emer-gency buses with perma-nently connected
- loads, ener-gizes the auto-connected emer-gency loads through load sequencing, and operates for greater than or equal to five minutes while its gene-rator is loaded with the emer-gency loads.
(3}
On diesel gene-rator breaker trip, the loads are shed from the emergency buses and the diesel restarts on the auto-start, signal, the emergency buses are energized with permanently C N ~ r
~
~
~ ~
LDJITING CONDITIONS FOi PERATION 3.9 AUXILIARYELECTRICAL SYSTEM SURVEILLANCE REQ IREJJENTS 4.9 AUXILIARYELECTRICAL SYSTEM (b) If unit 1
is in cold
- shutdown, only one common station-service transfor er is required.
(4)
The Athens 161-kV line is a'vailable 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 tover transformer may be substituted for a common station-service transformer.
2.
The reactor shall not be'tarted up (made critical) from the hot standby condition unless all of the folloving conditions are satisfied:
At least one offsite power source is available as speci-fied in 3.9.A.l.c, connected
- loads, the puto-connected
>gmergency 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.
Each diesel generator shall be given an annual inspectior
'.n accordance with instructions based on the manufacturer's recommendations.
e.
Once a month a sample of diesel fuel shall be checked for quality.
The quality shall be within acceptable limits specified in Table 1
of the latest xevision to ASTH l}975 and logged.
2.
DC Power System - Unit Batteries (250-U),
Diesel-Generator Batteries (125-V) and Shutdown Board Batteries (250-U) b.
Three units 1 and 2
diesel generators shall be operable.
Amendment No.
112 293
LIMITIiNG C0%)ITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS
-3.9 AUXILIARYELECTRICAL SYSTEM 4.9 AUXILIARYELECTRICAL SYSTEM 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.
a
~
Every week the specific gravity,
- voyage, and temperature o.'he pilot cell and overall battery voltage shall be measured and logged.
d.
3.
Buses and Boards Available a ~
The respective start bus is energized for c~ch common station<<
service transformer designated as an offsite power source.
b.
The 4>>kV bus 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.
C ~
The units 1 and 2
4-kV shutdown boards are energized.
The 480-V shutdown boards 2A and 2B are energized.
(2)
A fourth operable units 1 and 2 diesel generator.
Requirements 3.9.A.3 through 3.9.A.6 are met.
b.
c ~
3, Logic Systems a
~
Both divisions of the common accident signal logic system shall be tested every 6 months to demon-strate 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'iesel gene-rators.
Every three 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.
A battery rated discharge (capacity) test shall be performed and the
- voltage, time, and output, current measurements shall be logged at inter-vals not to exceed 24 months.
e.
The units 1 and 2
diesel auxiliary boards are energized.
Amendment No.
112
'I ~ p'
~
~ 'La~~i ~
293a
~
LI lITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIRE>1ENTS 3.~9 AUXILIARYELECTRICAL SYSTEH Loss of voltage and degraded voltage relays operable on 4-kU shutdown boards A, B, C, and D.
g.
Shutdown busses 1 and 2 energized.
h.
The 480V 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 shut-down board batteries, a
battery charger for each
- battery, and associated battery boards are operable.
5.
Logic Systems a.
Common accident signal logic system is operable.
b.
480-U load shedding logic system is operable.
b.
Once every 6 months, the condition unde whichyghe 480-volt load sKedding logic system is required shall be simulatei using pendant test switches and/or push-button test switches to demonstrate that the load shedding logic system would rnatch,ate load shedding signals on the diesel aux"iary
'oards, rmov boards, and the 480-V shut-down boards.
4.
Undervoltage Relays
'a ~
b.
(Deleted)
Once every 6 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.
4.9 AUXILIARYELECTRICAL SYSTEM'1 6.
There shall be a minimum of 103,300 gallons of diesel fuel in the standby diesel generator fuel tanks.
c ~
The loss of voltage and degraded voltage relays which start the diesel generators from the 4-kV shutdovn boards shall be calibrated annually for trip and reset and the measurements logged.
These relays skall be calibrated as specified in Table 4.9.A.4.C.'mendment No.
112 294
LlillTING CONDITIONS FOR OPERATION i3.9 AUXILIARYELECTRICAL SYSTE."I SURVEILLANCE REQUIREilENTS 4.9 AUXILIARYELECTRICAL SYSTE.'I d.
4-kV shutdown board voltages shall be reel'd5ed once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
5.
480V R1OV Boards 2D and 2E a.
Once per operating cycle the automatic transfer feature for 48QV RIOV boards 2D and 2E shall be functionally tested to verify auto-transfer capability.
Amendment No.
112 294a
LIMITING CONDITIONS FO PERATIOil 3
9 AUXILIARYELECTRICAL SYSTE.'J B.
0 eration with Ino erable E~ui ment Whenever the reactor is in Startup mode or Run mode and not in a cold condition, the availability of electr'c power shall be as specified in 3.9.A except as specified herein.
SURVEILLAÃCE RE IREHENTS 4.9 AUXILIARYELECTRICAL SYSTEM'I
~Eui ment When only'>one offsite power source is operable, all units 1 and 2 diesel generators and associated boards must be demon-strated to be operable immediately and daily thereafter.
1.
From and after the date that only one offsite power source is available, reactor operation is per-missible for 7 days.
2.
From and after the date that the 4-kV bus tie board becomes inoperable, reactor operation is permissible indefinitely provided one of the required offsite power sources is not supplied from the 161-kV system through the bus tie board.
3.
When one of the units 1
and 2 diesel generator is inoperable, continued reactor operation is permissible during the succeeding 7 days',
provided that 2 offsite power sources are available as specified in 3.9.A.l.c and all of the CS, RHR (LPCI and containment cooling)
- systems, and the remaining three units 1 and 2
diesel generators are operable.
If this requirement cannot be
- met, an orderly shutdown shall be initiated and the reactor shall be shut down and in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
3.
4.
When a required offsite power source is unavailable to unit 1
because the 4-kU bus tie board or a start bus is inoperable, all unit 1
and 2 diesel generators and associated boards shall be demonstrated operable immediately and daily thereafter.
The remaining offsite source
. and associated buses shall be checked to be energized daily.
When one of the units 1
and 2 diesel generators is found to be inoperable, all of the CS, RHR (LPCI and containment cooling) systems and the remaining diesel generators and associated boards shall be demonstrated to be operable immediately and daily thereafter.
When one 4-kV shutdown board is found to be inoperable, all remaining 4-kU shutdown boards and associated diesel gene-
- rators, CS, and RHR (LPCI and containment, cooling) systems sup)lied by,the remaining 4-kV shutdown boards shall be demon-strated to be operable immediately and daily thereafter.
Amendment
.No. ll2 295
LlflITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIRE.'1EXTS
- 3.9 AUXILIARYELECTRICAL SYSTE'.1 4.9 AUXILIARYELECTRICAL SYSTEM When one units 1 and 2
4-kV shutdown board is inoperable, continued reactor operation is permissible for a period of 5 days provided that 2 offsite power sources are available as speci fied in. 3.9.A. 1. c and the remaining 4-kV shutdown boards and associated diesel generators, CS, RHR (LPCI and containment cooling) systems, and all 480-U emergency power boards are operable.
If this requirement cannot be
- met, an orderly shutdown shall be initiated and the reactor shall be shut down and in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
5.
When a shutdown bus is found to be inoperable, all 1 ange diesel gene-rators shaK1 be proven operable imraediatelv and daily thereafter.
6.
When one uni s
1 and 2
diesel auxiliary board is found to be inoperable, the remaining diesel auxiliary board and each unit 1 and 2
diesel generator shall be proven operable immediately and daily thereafter.
When one of the shutdown buses is'inoperable, reactor operation is permissible for a period of 7 days.
6.
When one of the 480-V diesel auxiliary boards becomes inoperable, reactor operation is permissible for a period of 5 days.
7.
From and after the date that one of the three 250-V unit batteries and/or its associated battery board is found to be inoperable for any
- reason, continued reactor operation is permissible during the succeeding 7 days.
Except for rout,'ine surveillance
- testing, NRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the situation, Amendment No. 112 295a
'v
'IJ'TING CONDITIONS PO PERATION 3.9 AUXILIARYELECTRICAL SYSTE'i SURE'EILLANCE RE IRE.'KNTS 4.9 AUXILIARYELECTRICAL SYSTE.'I 8.
the precautions to be taken during this period, and the plans to return the failed component to an operable state.
From and after the date that one of the 250-V shutdown board batteries and/or its associated battery board is found to be inoperable for any
- reason, continued reactor operation is permissible during the succeeding five days in accordance with 3.9:B.7 9.
10.
%hen one division of the logic system is inoperable, continued reactor operation is permissible under this condition for seven days, provided the CSCS requirements listed in specification 3.9.3.3 are satisfied.
The NRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the situation, the precautions to be taken during this period, and the plan to return the failed component to an operable state.
{deleted)
The following limiting conditions for operation exist for the undervoltage relays which start the diesel generators on the 4-kV shutdown boards.
Amendment No. 112 296
LI~alITIiXG COiiDITIOKS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEH SURVEILLANCE REOUIRE lENTS 4.9 AUXILIARYELECTRICAL SYSTE>l a
~
b.
The loss of voltage relay channel which starts the diesel generator for a complete loss of volta'ge on a 4-kV shutdown board may be inoperable for 10 days provided the degraded voltage relay channel on that shutdown board is operable (within the surveillance schedule of 4.9.A.4.b).
The degraded voltage relay channel which starts the diesel generator for degraded voltage on a 4-kV shutdown board may be in operable for 10 days provided the loss of voltage relay channel on that shutdown board is operable (within the surveillance schedule of 4.9.A.4.B).
c ~
One of the three phase-to-phase degraded voltage relays provided to detect a degraded voltage on a 4-kU shutdo'wn board may be inoperable for 15 days provided both of the following conditions are satisfied.
Amendment No. 112 296a
LlilITING CONDITIONS FOR OPERATIO'8 3.9 AUXILIARYELECTRICAL SYSTEM'l SURVEILLANCE REQUIRE:lENTS 4.9 AUXILIARYELECTRICAL SYSTE'.I 1.
The other two phase-to-phase degraded voltage relays on that 4-kV shutdown board are operable (within the surveillance schedule of 4.9.A.4.b).
2.
The loss of voltage relay channel on that shutdown board is operable (within the surveillance schedule of 4.9.A.4.b).
d.
The degraded voltage relay channel and the loss of voltage relay channel on a 4-kV shutdown board may be inoperable for 5 days provided the other shutdown boards and undervoltage relays are operable.
(Mithin the surveillance schedule of 4.9.A.4.b).
12.
%hen one 480-V shutdown board is found to be inoperable, the reactor will be placed in hot standby within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold shutdown within g4 hours.
- 13. If one 480-V 1QIOV board mg set is inoperable, the react, or may remain in operation for a period not to exceed seven
- days, provided the remaining 480-U RHOU board mg sets and their associated loads remain operable.
AmendmeatM, D2,
LI>fITING CONDITIONS FOR OPERATION
- 3. 9 AUXILIARYELECTRICAL SYSTEt1
- 14. If any two 480-U RHOV board mg sets become inoperable, the reactor shall be placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 15. If the requirements for operating in the conditions specified by 3.9.B.l through 3.9.B.14 cannot be met, an orderly shutdown shall be initiated and the reactor shall be shut down and in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURUEI LLQlCE REQUIRE'.EATS 4.9 AUXILIARYELECTRICAL SYSTE'.l Amendment No. 112
~tJ&AI 29?a
Lli'iITING CONDITIONS FOR OPERATION
~3.9 AUXILIARYELECTRICAL SYSTEH C
C.
0 eration in Cold Shutdown SURVEILLANCE REQUIREHENTS 4.9 AUXILIARYELECTRICAL SYSTEH Vhenever the reactor is in cold shutdown condition with irradiated fuel in the
- reactor, the availability of electric power shall be as specified in Section 3.9.A except as specified herein.
l.
At least two units l and 2 diesel generators and their associated 4-kU shutdown boards shall be operable.
2.
An additional source of power energized and capable of supplying power to the units l and 2 shutdown boards consisting of at least one of the following:
a.
One of the offsite power sources specified in 3.9.A.lac.
b.
A third operable diesel generator.
3.
At least one 480-V shutdown board for each unit must be operable.
4.
One 480-U RHOU board mg set is required for each RHOU board (2D or 2R) required to support operation of the RHR system in accordance with 3.S.3.9.
Amendment, No.
112 298
Table 4.9.A.4.C VOLTAGE RELAY SETPOINTSIDIESEL GENERATOR START Rela Location
'Tri Level Settin Remarks 1.
4-kV Shutdown Boards 4
mX-L L
t I
e Trip Setpoint:
Allowable Values:
Trip Range:
Reset Setpoint:
Allowable Values:
Reset Range:
0 volts with a 1.5-second time delay
+.1 second 1.4 to 1.6 seconds 2870-V
+ 2$ of 2870-V 2813-V to 2927-V Start diesel generators on lossof offsite power.
Undervolta e
2.
4-kV Shutdown Boards Trip Setpoint:
3920
~ Allowable Values:
3900-3940 Reset Sctpoint:
Reset at
< 1.5$ above trip value Second level undervoltage sensing relays start diesel generator on degraded voltage.
3.
4-kV Shutdown Boards (Timers shown for 4-kV shutdown board A.
4-kV shutdown boards B, C, and Dg similar, except for change of suffix.)
Timer 2-21 'I-1A 2<<211-2A 2-211-3A 2-211-4A Setpoint (seconds) 0.3
+ 10$
4.0
+ 10$
6.9
+ 10$
1.3
+ 10$
Critical Time (seconds)
I NiA N/A 8.2 1.5 Auxiliary timers for second level undervoltage sensing relays.
The setpoint ranges specified assure that the oper ating times will be below the critical times speci ficd.
These ranges ar e based on timer repcatability of + 5$ as specified by the manufacturer.
Amendment No. 112 29ea
The objective of this specification is to d
assure an a equate source of electrical power to operate facilities to cool the la and to o crate th oo e p ant during shutdown three sources of 1
p e
he engineered safeguards following an acc'd 1h i ent.
ere are the 161-kV t of alternating current electrical energy av '1 bl ai a
e, name y, 1
ransmission
- system, the 500-kU transmission s s'e diesel generators.
mission system and the The unit station-service transformer B for unit 1 or th service transformer B for uni r uni or t e unit st"tion-er or unit 2 provide noninterruptible sources of shutdown boards.
Auxilia n
site power from the 500-kV transmission system to th d
e units an 2
transmission s stem throu uxxlxary power can also be supplied from the 161-kV y
gh the common station-service transformers or t rough the cooling tower transformers by way of the bus tie b The 4-kV bus tie board ma re a
e us tie oard.
ore of the re may remain out of service indefinitely provided ore o
the required offsite power sources is not supplied from the 161-kU system through the bus tie board.
The minimum fuel oil requirement of l03 300 allo ff'even days of full load o erat s
o u
oa operation of three diesels and is conservatively ase on availability of a replenishment supply.
The degraded voltage sensing relays'provide a start signal to the diesel generators in the event that a deteriorated v lt d
a 4-kV o
age con ition exists. on a
shutdown board.
This starting signal is 'nd d t f h
in epen ent o t e ar ing signa generated by the complete loss of voltage relays and will continue to function and start the diesel generators on complete loss of voltage should the loss of voltage relays become inoperable.
The 15-da inoperable time limit specified when one of the three phase-to-phase Jegraded voltage relays is inoperable is justified based on the two out of three permissive logic scheme provided with these relays.
A 4-kV shutdown board is allowed to be out of operation for a brief period to allow for maintenance and testing, provided all remaining 4-kV shutdown boards and associated diesel generators, CS, RHR, (IPCI and containment cooling) systems supplied by the remaining 4-kV shutdown
- boards, and all emergency 480-V power boards are operable.
There are eight 250-V dc battery svstems, each of which consists of a battery, battery charger, and distribution equipment.
Three of these systems provide power for unit control functio n
ions, operative power for unit motor loads, and alternative drive power for a 115-V ac'nit-preferred mg set.
One 250-V dc system provides power for common plant and transmission system control function d
'ons,rive power for a 115-volt ac plant preferred mg set and emerge c
d mergency rive power for certain unit large motor loads.
The four remaining system d
1'o the 4,160-V shutdown boards.
ys em e iver control power o
Each 250-V dc shutdown board control power sup 1
its er supp y can receive power from c arger.
e chargers i s own battery, battery charger, or from a spare cha Th are powered from normal plant auxiliary power or from the standby diesel-driven generator system.
Zero resistan h
ance s ort circui'ts between he control power supply and the shutdown board are cleared by fuses located in the respective control power supply.
Each power su 1
is located in the reactor building near the shutdown board it supplies.
Each battery is located in its own independently ventilated battery room Amendment No: 112 299
Thee 250-U dc sys em is so arranged, and the ba o that the ry n t prevent the safe shutdown and atte will not d
d
' 'd o
a
,t ree units in the event o
asis acci ent in anv one unit.
xt.
Loss of control po er to re sa eguar control circuits is annunci t in he m in b
ff 1
e unit a ected.
The loss of h
h
~
1
~
Th
~
pp p ies.
e station batte su 1
battery was not considered a
e s ut own and cooldown o~f the nuclear system.
This const ere in the accident load calculations.
There are two 480-U ac RMOU boards that contaiin mg sets xn their ieeder
'normal to alternate power source (480-U ac s u 1
1 1
(
o-c h t o o
).
g electrical divisions due to an automatic rom propagating between bo d 'l d
o d
e prove e motive power to valves associated with the LPCI g
g o
of service r es the S'f 1
a u
CI capacity will be ava complement required for RHR (LPC ) operation, a 7-da servici ipmen is available to maintain justified.
Having two mg sets out of service can co il bil t
- th fo th fffe ed
-t h 11 b pl d i The off he offsite power source requirements are based on 1'h T
rxnity ine is limited to su 1 in units because of the load limitations of <SST's A and B.
The is limited to supplying one operatin unit beca ng c ndx sons are contended to 1 f 1 'h ff'ystem from supplyin more than re in e o site power system.
Amendment No. 112 300
4.9 BASES The monthl te t failures y
ests of the diesel generators are primarily t h
k f ocec.
or.
will be loa r s and deterioration in the system since last Th d'ed to at least 75 percent of rated power while engine and s
use.
e iesels generator temperatures are stabilized (about one hour).
The minimum 7S percent load will prevent soot formation in the c 1' nozzles.
Operation u
'n e cy xn ers ypd.'injection is no overheatin Operation up to an equilibrium tempreature ensure th h
r at t ere operating histo to be g problem.
The tests also provide an engine a
d data to iden i e an generator compared with subsequent engine-generato t
ntify and to correct any mechanical or electrical deficienc before it can result in a system failure.
ec rica e xciency The test during refueling outages is more comprehensive n
1 d' res that are most effectively conducted at that time.
These rocedure
, i c u ing include automatic actuation and functional b'1'ona capa i ity tests to verif that the generators can start and be ready t 1
d h
c assume oa in l0 seconds.
T e annual inspection will detect any signs of wear long before failure.
The diesel generators are shared by units 1 and 2.
Th f
ca abilit for t p
y he units 1 and 2 diesel generators to accept the an ere ore, the the unit L loads.
emergency loads will be performed during the un't 1
e uni operating cycle using Battery maintenance with regard to the floating charge, equilizing
- charge, and electrolyte level will be based on the manufacturer's instruction and sound maintenance practices I
dd' a
ition, written records will be maintained of the battery performance.
The plant batteries will deteriorate with time but precipitous f '1 unlike).,
y.,
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 i'rregular or unserviceable Lon b
becomes a failure.
icea e
ong efore it The equalizing charge, as recommended by the manufacturer, is vital to as recommended.
maintaining the Ampere-hour capacity of the battery a
d 'll b 1'he testing of the logic systems willverify the abil't f
h 1
s stems to b y
ring the auxiliary electrical system to running standby 0
e a i i y o t e ogic readiness with the presence of an accident. sig 1 f undervoltage signal on the 4-kV shutdown boards.
signa rom any reactor or an The periodic simulation of accident signals in conjunction with diesel.
generator voltage available signals will confirm the"ability of the 480-volt load shedding logic system to sequentially shed and restart 480-volt loads if an accident, signal were pres nt d d' voltage were the only source of electrical power.
sen an iese generator Amendment No.
112 301
l
-4 9 BASES REFERENCES e
1.
Normal Auxiliary Power System (BFNP FSAR Subsection 8 4) 2.
Standby AC Power S
y Po er Supply and Distribution (BFNP FSAR Subsection 8.5) 3.
250-Volt DC Power S
er 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.
H. J.
Green dated January.
10 1983 (G02 Amendment No. 112
- ,ply 1
~
301a
pe ~ECy,~Np
'~4 O
I n.
f
~.
IO0
/+
P Qi" kg**4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
88 License No.
DPR-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated October 22, 1984, 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 CoIIWIission; 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 ComIIission's regulations and all applicable 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 Facility Operating License No.
DPR-68 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.
88, are hereby incorporated in the license.
The licensee shall operate the facilig in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issu5kce.
FOR THE NUCL AR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 2, 1985 Domenic B. Vassallo, Chief Operating Reactors Branch P2 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
88 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
vii, 316, 317, 318, 319, 320, 321, 322, 323, 324, 325, 326, 327, 328, 329$
330 2.
The marginal lines on these pages denote the area being changed.
3.
Delete pages.
- 325b, 326a
4.2.E 4.2.F 4.2.C 4.2.H Test and Calibration Frequent Detection lnstruaentation q
y for Dryvcll Leap Hf Test and Instruaentstion on requency for Surveillance SurveLllance Requfreaents I
Instr~entatfon s
or Cont s
Co trol Roon Isolation Hfnfaun Test and Calibratf1 quency for Flood Protection ratfon Fre 1y 101 102 103 L04 4.2.J 3.5.-1 3.5.1 4.6.A 3.7.*
3.7.8 3.7.C
).e.D 3.7.E
).J.F Seisaic NonftorinS Instruaenc Surve ruaent Surveillance Requfrcacnts Hfnbaua RHRSM and EECM Pua p AssfSnaent HAPLHCR vs. Averse>> Plaanar sure Reactor Coolant Systea Inse nservfce Inspection Schedule, Prfnary Contafnaent Isolation Valves Testable Penetratfons vith Double 0 RinS Scale Testable Pen ~tratfons ufth Testable 8 ~ lfovs Air Tested Isoiarfon Valves Ptfaary Contafnnent Isolation Valves vhf Priaarv Contafreaent IsolatLon Valves Lu Sf i Cl LLL 105 156a
$8)y 182,
- 182a, 182b 09 262 268 269 270 279 280 3.7.0 3.7.H 4.8.A 4.8.8 4.9rA.4.c
- 3. LL.A 6.S.A Deleted Testable Electrical Pcnetratfons Radioactfve 'Liquid Masts SaaplfnS and A
nS a
Analysis Radiooactfve Cascous Haste Saa Li
~ap n8 and Analysis Voltage Rafa Se y
tpofntslDiesel Cenerator Start Fire Protectfon S stea y
ea Hydraulic Rcquireaents Mfnfnua Shfit Crcv Requfrenents
'83 310
)5)n
)90 Amendment No, 88 vff
LI'lITIvG CONDITIO'tS I'ERATIOH SURVEILINCE IREHEhTS 3.9 AUXILIARYELECTRICAL SYSTE".I 4.9 AUXILIARYELECTRICAL SYSTEil A licabilit Applies to the auxiliary electri'cal power system.
~Ob 'ective To assure an adequate supply of electrical power for operation of those systems required for safety.
S ecification A.
Auxiliary Electrical E~uimment Applies to the periodic testing requirements of the auxiliary electrical system.
O~b'ective Verify the operability of the auxiliary electrical system.
S ecification A.
Auxilia Electrical E~ui ment 1.
Diesel Generators b.
Diesel generators 3A, 3B, 3C, and 3D operable.
Requirements 3.9.A.3 through 3.9.A.6 are met.
1.
The reactor shall not be started up (made critical) from the cold condition unless the following are satisfied:
a e Each unit 3 diesel generator shall be manually started and loaded once each month to demonstrate operational readiness.
The test shall continue for at least a 1-hour period at 75'/ of rated load or greater.
c ~
At least two of the following offsite power sources are available:
(1)
The 500-kV system is available to the unit 3 shutdown boards through the unit 3 station-service transformer TUSS 3B with no credit taken for the two 500-kV Trinity lines.
During the monthly generator test the diesel generator starting air compressor shall be checked for operation and its ability to recharge air receivers.
The operation of the diesel fuel oil transfer pumps shall be demonstrated and the diesel starting time to reach rated voltage and speed shall be logged.
Amendment No. 88 316
LIMITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTE<l SURVEILLANCE REQUIREMENT (2)
NOTE FOR (2):..
The Trinity 161-kV line is available to the unit 3 shutdown boards through a
common station-service or cooling tower transformer.
If units 1 and 2 are both in operation and claiming the Trinity line as an offsite
- source, TUSS 3B must be claimed as the other offsite source for unit 3.
AUXILIARYELEC RICAL SYS b.
Once per operating
- cycle, a test will be conducted simu-lating a loss of off-site power and similar "onditions that would exist with the presence of an actual safety-injection signal to demonstrate the following:
(1)
Deenergization of the emer-gency buses and load shedding from the emergency buses.
(3)
The Athens 161-kV NOTE FOR (3):
line is available to the unit, 3 shutdown boards through a
common station-service or cooling tower transformer.
'Zf either unit 1 or unit 2 is claiming the Athens line as an offsite
'source, it may not be claimed as an offsite Amendment No. 88
- claimed as the two offsite sources for unit 3, no credit may be taken for the Athens-Trznity line tie breaker.
Speci-fically, the Athens line supplies unit 3
through common station-service trans-former A or cooling tower transformer 1,
source for unit 3.
NOTE FOR (2)AND (3):Zf both Athens and Trinity lines are 317 (2)
The diesel starts from ambient condition on the auto-start
- signal, ener-gizes the emergency buses with permanently connected
- loads, ener" gizes the auto-connected emer-gency loads through load sequencing and operates for greater than or equal to five minutes while its gene-rator is loaded with the emer-gency loads.
(3)
On diesel gene-rator breaker trip, the loads are shed from
LIHITING COiVDITIONS FOR OPERATION
>.9 AUXILIARYELECTRICAL SYSTEH SURVEILLANCE REQUIREHENTS 4.9 AUXILIARYELECTRICAL SYSTEH NOTF.:
(Continued) and the Trinity line msst supply unit 3 through common station-service transformer B or cooling tower transformer 2.
a
~
At least one offsite power source is available as specified in 3.9.A.l.c.
b.
Three unit 3 diesel generators shall be operable.
2.
The reactor shall not be started up (made critical) from the hot standby condition unless all of the following conditions are satisfied:
the emergency
, buses and the
>)diesel restarts on the auto-start signal, the emergency buses are ener-gized 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 ~
d.
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.
(2)
A fourth unit 3 diesel generator operable.
Requirements 3.9.A.3 through 3.9.A.6 are met.
c.
Once a month the quantity of diesel fuel available shall be logged.
d.
Each diesel generator shall be given an annual inspection in accordance with instructions based on the manufacturer's recommendations.
e.
Once a month a sample of diesel fuel shall be checked for quality.
The quality shall be within acceptable limits specified in Table l of the latest revisional to ASTH D975 and logged.
Amendment No. 88 318
I
L,INITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREHENTS v"
3.9 AUXILIARYELECTRICAL SYSTE!l a
~
The respective start bus is energized for each common station-service transformer designated as an offsite power source.
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.
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 R10V boards 3D and 3E are energized with 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.
5.
.Accident signal logic system is operable.
A.
3.
Buses and Boards Available a.
Every week the specific gravity, v'oltage, and temperature of the pilot cell, and b.
overall battery voltage shall be measured and logged.
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.
A battery rated discharge (capacity) test. shall be performed and the
- voltage, time, and output current measurements shall be logged at intervals not to exceed 24 months.
3.
I.ogic Systems a.
Both divisions of the accident signal logic system shall be tested every 6
months to demons%ate'hat it will function on actuation of the core spray system of the reactor to provide an automatic start signal to all 4 diesel generators.
4.9 AUXILIARYELECTRICAL SYSTEM 2.
DC Power System - Unit Batteries (250-V),
Diesel-5 jaerator Batteries (125"V) and Shutdown Board Battery (250-V)
Amendment No. 88 319
LI>IITING CONDITIONS FO.
PERATION
,3.9 AUXILIARYELECTRICAL SYSTEN 4
6.
There shall be a minimum of 103,300.gallons of diesel fue1 in the unit 3 standby diesel-generator fuel tanks.
a
~
b.
(deleted)
Once even~6
- 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.
SURVEILLANCE RE IREa1ENTS 4.9 AlKILIARYELECTRICAL SYSTE.'1 4.
Undervoltage Relays c ~
d.
The loss of voltage and degraded voltage relays which start the diesel generators from the 4-kV shutdown boards shall be calibrated annually for trip and reset and the measurements logged.
. These relays shall be calibrated a
specified in Table 4.9.A.4.c.
4-kV shutdown board voltages shall be recorded once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
5.
480-U 1910V Boards 3D and 3E a
~
Once per operating cycle, the automatic transfer feature for 480-V B10V boards 3D and 3E hall be functionally tested to verify auto-transfer capability.
Amen dqjt,nt,.Nq8Q,.
320
LIHITIVG C0%)ITIO'AS FOR OPERATIO',l 3.9 AUXILIARYELECTRICAL SYSTEH SURVEILLANCE REOUIRE'.KITS 4.9 AUXILIARYELECTRICAL SYSTE'.I B.
0 eration with Ino erable E~ui ment Whenever the reactor is in Startup mode or Run mode and not in a cold condition, the availability of electric power shall be as specified in 3.9.A, except as specified herein.
B.
0 eration with Lnooerable
~ui ment When only one offsite power source is operable, all unit 3 diesel generators and associated boards must be demonstrated to be operable immediately and daily therea fter.
1.
Prom and after the date that only one offsite power source is available, reactor operation is permissible under this condition for seven days.
2.
When one unit 3 diesel generator (3A, 3B, 3C, or 3D) is inoperable, continued reactor operation is permissible during the succeeding 7
- days, prov:ded that two'ffsite power sources are available as specified in 3.9.A.1.c and all of the CS, RHR (LPCI and containment cooling)
- systems, and the remaining three unit 3 diesel generators are operable.
If this requirement cannot be
- met, an orderly shutdown shall be initiated and the reactor shall be shut down and in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.
Prom and after the date that the 4-kV bus tie board becomes inoperable, reactor operation is permissible indefinitely provided one of the required offsite power sources is not supplied from the 161-kV system through the bus tie board.
2.
3.
4.
When one unit 3 diesel generator is found to be inoperable, all of the CS, RHR (LPCI and containment cooling) systems and the remaining unit 3 diesel generators and associated boards shall be demonstrated to be operable immediately and daily thereafter.
When a required offsite power source is unavailable because the 4-kV bus tie board or a start bus is inoperable, all unit 3 diesel generators and associated boards shall be demonstrated operable immediately and daily thereafter.
The remaining offsite source and associated buses shall be checked to be energized daily.
When one unit 3 4-kV shutdown board is found to be inoperable, all remaining unit 3 4-kV shutdown boards and associated diesel generators, CS and RHR (LPCI and containment cooling) systems supplied by the remaining 4-kU shutdown boards shall be demonstrated to be operable, immediately and daily thereafter.
Amendment No..88 321
LDIITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIRE.'KNTS
. 3.9
'AUXILIARYELECTRICAL SYSTEH
.9 AUXILIARYELECTRICAL SYSTE'.1 4.
When one unit 3 4-kV shut-down board is inoperable, continued reactor operation is permissible for a period of 5 days, provided that two offsite power sources are available, as specified in 3.9.A.l.c and the remaining unit 3 4-kV shutdown boards and associated diesel generators, CS, RHR (LPCI and containment cooling)
- systems, and all uni..
3 480-V emergency power boards are operable.
If this requirement cannot be met, an orderly shut-down shall be initiated and the reactor shall be shut down and in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 5.
Whe~ one 480-V diesel auxiliary board is found inoperable,zfhe remaining diesel auxiliary board and each unit 3 diesel shall be verified operable immediately and daily thereafter.
6.
From and after the date that one of the 480-V diesel auxiliary boards becomes inoperable, reactor operation is permissible for a period of 5 days.
From and after the date that the 250-V shutdown board 3EB battery or one of the three 250-V unit batteries and/or its associated battery board is found to be inoperable for any reason, continued reactor operation is permissible during the succeeding seven days.
Except for routine surveillance testing, the NRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the situation, the precautions to be taken during this period, and the plans;to return the failed component to an operable state.
Amendmeht No. 88 322
IHITING CONDITIONS OPERATION SURE'EILLANCE REQUIRE."KITS 3.9 AUXILIARYELECTRICAL SYSTELl 4.9 AUXILIARYELECTRICAL SYSTE.'I 7.
When one division of the logic system is inoperable, continued reactor operation is permissible under this condition for seven days, provided the CSCS requirements listed in Specification 3.9.B.2 are satisfied.
The NRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the situation, the precautions to b taken during this period,
'nd the plans to return the failed component to an operable state.
8.
(deleted) 9.
The following limiting conditions for operation exists for the undervoltage relays which start the diesel generator on the 4-kV shutdown boards.
a
~
b.
The loss of voltage relay channel which starts the diesel generator for a complete loss of voltage on a 4-kU shutdown board may be inoperable for 10 days provided the degraded voltage relay.channel on that shutdown board is operable (within the surveillance schedule of 4.9.A.4.b).
The degraded voltage relay channel which starts the diesel generator for degraded voltage on a 4-kU shutdown board may be Am'endment No. 88 323
LKHITING CONDITIONS OPERATION 3.9 AUXILIARYELECTRICAL SYSTEH r
inoperable for 10 days provided the loss of voltage relay channel on that shutdown board is operable (within the surveillance schedule of 4.9.A.4.b).
SURVEILLANCE RE UIRE,"KNTS 4.9 AUXILIARYELECTRICAL SYSTEH c.
One of the three phase-to-phase degraded voltage relays provided to detect a degraded voltage on a 4-kV shutdown board may be inoperable for 15 days provided both of the following conditions are satisfied.
1.
The other two phase-to-phase degraded voltage relays on that 4-kV shutdown board are operable (within the surveillance schedule of 4.9.A.4.b).
2.
The loss of voltage relay channel on that shutdown board is operable (within the surveillance schedule of 4.9.A.4.b).
d.
The degraded voltage relay channel and the loss of voltage relay channel on a
4-kV shutdown board may be inoperable for 5 days provided the other shutdown Amendment No.
88 324
LINITING CO%)ITIONS F R OPERATION 3.9 AUXILIARYELECTRICAL SYSTE>J SURVEILLANCE REQUIREMENTS 4.9 AUXILIARYELECTRICAL SYSTE>l boards and under-volt~ge relays are operable.
(Within the surveillance schedule of 4.9.A.4.b).
10.
When one 480-V shutdown board is found to be inope able, the reactor will be placed in hot
~ standby within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 11. If one 480-V RIOV board mg set is inoperable, the reactor may remain in operation for a period not to exceed seven days, provided the remaining 480-V RIOV board mg sets and their associated loads remain operable.
- 12. If any two 480-V R10V board mg sets become inoperable, the reactor shall be placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 13. If the requirements for operation in the conditions specified by 3.9.B.l through 3.9.B.12 cannot be met, an orderly shutdown shall be initiated and the reactor shall be shut down and in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Amendment No. 88 325
LIHITIlG COVDITIONS F PERATIOV SURVEILLANCE IREHEVTS 3.9 AUXILIARYELECTRICAL SYSTEH C.
0 eration in Cold Shutdown Condition 4.9 AUXILIARYELECTRICAL SYSTEH Whenever the reactor is in the cold shutdown condition with irradiated fuel in the
- reactor, the availability of electric power shall be as specified in Section 3.9.A except as specified herein.
l.
At least two unit 3 diesel generators and their associated 4-kU shutdown boards shall be operable.
2.
An additional source of power energized and capable of supplying power to the unit 3 shutdown boards consisting of at least 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 unit 3 <8O-U shutdown board must be operable.
4.
One 480-U tuiOU board motor generator(mg) set is required for each rmov board (3D or 3E) required to support operation of the RHR system in accordance with 3.5.B.9.
Amendment No. 88 326
Table 4.9.A.4.C VOLTAGE RELAY SETPOINTS/DIESEL GENERATOR START Bela Location Tri Level Settin Remarks l.
4-kV Shutdown Boards Trip Setpoint:
Allowable Values:
Trip Range:
Reset Setpoint:
Allowable Values:
Reset Range:
e Q volts with a 1.5-second time delay
+.1 second i.4 to le6 seconds 2870-V
+ 2$ of 2870-V 2813-V to 2927-V Start diesel generators on loss of offsite power.
i 2.
4-kV Shutdown Boards I
Undervolta e
Trip Setpoint:
3920 Allowable Values:
.3900-3940 Beset Setpoint:
Reset at < 1.5$ above trip value Second level undervoltage sensing relays - start diesel generator on degraded voltage.
3.
4-kV Shutdown Boards (Timers shown for 4-kV shutdown board 3EA.
4-kV shutdown boards 3KB, 3EC, and similar, except for change of suffix.)
Timer 2-211-1A 2-211<<2A 2-211-3A 2>>211-4A
- 3ED, Setpoint (seconds)
Q.3
+ 105 4.0
+ 10$
6.9
+ 10$
1 3
+10ci Critical Time (seconds)
N/A N/A 8.2 1.5 Auxiliary timers for second level undervoltage sensing relays.
The setpoint ranges specified assure that the operating times will be below the critical times specified.
These ranges are based on timer repeatability o1' 5$ as specified by the manufacturer.
Amendment No. 88 327
3)P BASES The objective of this specification is to assure an ade uate sou electrical po~er to operate facil'ti "
and to operate the engineered safe uards fo w'
r fol)o xng here
~
g
~
rces o
a ternatin current e
transmission s stem The unit-station-service transformer B for>>nit 3 provides a
noninterruptible source of offsite power from the 500-kV system to the unit rom e
transmission 3 shutdown boards.
Auxiliary power can also be
, supplied from the 161-kV transmission system through the common station-service transformers or throu h the cool'f h
b 'o d.
T us ie oar The 4-kV bus tie board may remain out of service indefinitely provided one of the re uired offs' ot u pl' fro the 161-kV
~
system through the bus tie board.
The minimum fuel oil requirement of 103, 300 allen. is d
of f 11 lo d o t'o of 3 d 1
1 b'1 o
a rep enishmeat supply.
The degraded voltage sensing relavs provide a start si na t
th t th t d
a a
eteriorated voltage condition exists on a
s ut own board.
This starting signal is independent of the startin signal generated by t':e complete loss of volta e relays a
d w'o function and start thc diesel e loss of voltage s ou the loss of voltage relays become inoperable.
The 15-day e t ree p.hasc-to-phase inoperab'.c tijae limit specified when one of th h
h irie ase on the two out egraded voltage relays is inoperable is just' d b d
of three permissive logic scheme provided with these relavs
~
v
~
eriod t A 4-kU shutdown board is allowed to be out of o t
f o
operation for a brief perio to allow for maintenance and testing prov'd d ll shutdown board vi e a
remaining 4-kV boards and associated diesel generators, CS,
- boards, and all emergency 4SO-V power boards are operable The 480-V diesel auxiliary board may be out of seivicc for short periods for tests and maintenance.
There are five 250-V dc battery systems. associated with uni.t 3, each of which consist of a battery, battery charger, and distribution equipment.
Three of these systems provide power for unit control functions, operative power for unit motor loads, and alternative drive power for a 115-V ac unit-preferred mg set.
One 250-V dc system provides power for common plant and transmission system control functions, drive power for a 115-V ac plant-preferred mg set, and emergency drive power for certain unir large motor loads.
>hc fifth battery system delivers control power to a 4-kV shutdown board.
The 250-V dc system is so arranged and the batteries sized s
rhat thc loss of any one unit battery will not prevent the safe shutckwn and cooldown of all three units in the event of the loss of offsite power and a design basis accident in any one unit.
Loss of control power to any engineered safeguard control circuit is annunciated in the m:jin cojjtrol room of the unit affected.
Amendment No. 88 328
~ ~
a
~
~ ~, ~
W ew
The station batte g supplies loads that are not essential for safe shutdown and cooldown of the nuclear system.
This battery was not considered in the accidnet load calculations.
There are two 480-V lines.
These 480-ac RMOV boards that contain mg sets in the' d
8 -V ac RMOV boards hav an automatic transfer from their eir ee er normal to alternate power source (480-V ac shutdown boards The m
sets act as electrical isolators to prevent a fault f electrical divi i a
au rom propa ting between boards involved rov ivisions due tc an automatic transfer.
The 480-V iQIOV ac mode of the RHR s stem.
provide motive power to valves associated with th LPCI ys em.
Having an mg set out of service reduces the wi Since sufficient e
u assurance that full RHR (LPCI) capacity will b
'1 bl i
e avai a
e when required.
icien equipment is available to maintain the minimum complement required for RHR (LPCI) operati 7-d ra son, a
- ay servicing period is j s i ie Having two mg sets out of service can considerably reduce equipment availability; therefore, the affected unit shall be la cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
nx s
a e p aced in The offsite power source requirements are based on the a
respective lines.
The Trinit line is sty ine is limited to supplying two oper ecause o
e oad limitations of CSST's A and B.
The Athens line is limited to supplying one operating unit because of the load limitations of the Athens line.
The limit'ng conditions are intended to r
en e
system from supplying more than two units in the event of a single failure in the offsite power system.
Amendment No. 88 329
4'3 BASES The monthly tests of the diesel enerator g
o r
p ystem since cast use.
The diesels e erxoration in the s
oa e
to at least 75 percent of rated ower w generator temperatures are stabilized (ab 75-percent load w'll event so oa wi prevent soot formation in the cylind+ and ion nozz es.
Operation u
to p
an equilibrium temperature ensures e is no overheating problem.
The test a
h' comp re ith or es ata to identify and to correct any mechanical or rica e icienc before y
it can result in a system failure.
The test during refueling outa es is mor procedures that ages xs more comprehensive, including at are most effectively conducted'at include automatic actuat' f
th t th to s n t d b a ion an unctional ca abil Th u l i sp ct'o
'll detect a
s art an e read to a
etect any signs of wear long before failure.
Battery maintenance with regard to the floatin char e
e u'harge, and electrolyte level will be based on the manufacturer's maintenance practices.
In addit'o records will be maintained of th b
batteries will deteriorate with t' o
e attery performance.
unlikely.
The type of surveillance called for in this s ec' ime ut precipitous failure is that which has been demonstrated throu h ex o g
. perxesce to provide an becomes a failure.
o a ce ecoming irre ular or g
r unserviceable long before it The equalizing charge, as recommended by th f
maintaining the ampere-hour capacity of the'at
~
e manu acturer is vite'.
as recommended.
o e'ttery, and will be applied The testing of the logic system will verify the abilitv of the systems to bring the auxiliary elect l
readiness with the presence of a d
o c rica system to runnin an acci ent signal from an 'eacto undervoltage signal on the start buse 4-kV h
s or s utdovn boards.
c or or an The periodic simulation of accident signals in con'unction w'enerator voltage available signal load shedding logic system to sequentiall h d d
s wi con irm the abilit of t an accident signal vere present and diesel generator ia y s e
and restart 4
source of electrical power.
iese generator voltage vere the only REFERENCES l.
Normal Auxiliary Power System (BWP FSAR,,su section 8.4) 2.
Standby A.C. Power Supply and Distribution (BFNP F FSAR subsection 8.5) 3.
. 250-volt D.C.
P v
. Power Supply and Distribution (BFHP FSAR subsection Sr6) 4.
.Memorandum from G.
M. t'ilhoite to H. J.
Green d
'LOO 811208 664) d o
d
( -.:: '::.)ro """""
'"'"""'mendment No 88~
330