ML20030D852

Amends 75 & 72 to Licenses DPR-33 & DPR-52,respectively, Changing Tech Specs to Reflect Mods Presently Being Accomplished to Electrical Distribution Sys

ML20030D852
Person / Time
Site:	Browns Ferry
Issue date:	09/03/1981
From:	Ippolito T Office of Nuclear Reactor Regulation
To:
Shared Package
ML20030D853	List: ML20030D852 ML20030D854 ML20030D856
References
TAC-10010, NUDOCS 8109170070
Download: ML20030D852 (27)

Text

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UNITED STATES

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s TENNESSEE VALLEY AUTHORITY 00CKET NO. 50- 259 BROWNS FERRY NUCLEAR PLANT, UNIT NO. 1 AMEN 0 MENT TO FACILTIY OPERATING LICENSE Amendment No. 75 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 April 9,1981 as supplemented by letters dated June 8,1981, July 2,1981, July 31,1981 and August 17, 1981, 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 (,1) 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 er 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 applisable requirements have been satisfied.

2 Accordingly,-the license is amended by changes to the Technical Specifications as indicated in the attachment to this license emendment and Aaragraph 2.C(2) of Facility License No. DPR-33 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as

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revised through Amendment No. 75, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

8109170070 81090 [

PDR ADOCK 050002 9i e

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t 2-3 This license amendment is effective within 30 days of issuance.

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FOR THE NUCLEAR REGULATORY COMMISSION

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Thomas A. Ippolito, Chief Operating Reactors Branch #2 l

Division of Licensing i

Attachment:

Changes to the Technical l

, Specifications Date of Issuance: September 3,1981 l

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ATTACHMENT TO ' LICENSE AMENDMENT'NO. 75 FACILITY OPERATING LICENSE NO. DPR-33

_ DOCKET NO. 50-259 Revise Appendix A as follows:

- 1.

Remove. the following pages and replace with identically numbered pages:

292/293 '

294/295 296/297 298/299

'300/301 l

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- 2.

The underlined pages are the pages being changed; marginal lines on

'these pages indicate the revised area. The overleaf page is provided for convenience, i

3.

Add the following new-pages:

l 293.a

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294a-297a 297b 298a l

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q LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RECUIREMENTS e

- e 3 9 AUXILIARY ELECTRICAL SYSTEM 4.9 ~ AUXILIARY ELECTRICAL SYSTEM Applicability Applicability Applies to all tne auxilicry Applies to the periodic testing electrical power syster-require =ents of the auxiliary electrical systems.

Objective Objective To assure an adequate supply of Verify the operability of the electrical power for operation of auxiliary electrical syste=.

those syste=s required for safety.

Specification Specification A. Auxiliary Electrical Ecuipment A. Auxiliary Electrical Ecuip=ent A reactor shall not be started 1.- Diesel Gene:*ators up (made critical) frem the cold condition unless four units 1

a. Each diese3 generator sL 11 and 2 diesel generators are be =anually started and operable, the require =ents of loaded ence each month to 3 9.A.4 through 3 9.A.7 are met de=enstrate operational and two of the following off-readiness. The test shall site power sources are available centinue for at least a one as stated with no credit taken nour period at 75% of rated for the two 500-kV Trinity load or greater.

lines.

During the monthly

- Both 161-kV lines and cc =cn generator test, the diesel station service transfer:ers generater starting air provided the second source is cc= pressor shall be checked from the 500kV system.

for operation and its ability to recharge air

- The unit 1 unit station service receivers. The operation transfer =er TUSS 1B is available.

of the diesel fuel cil-If the unit 2 statien service transfer pu=ps shall be transformers is the second demonstrated, and the source, a minimum of two 500-kV diesel starting time to lines cust be available.

reach rated voltage and.

speed shall be logged.

- The unit 2 unit station service transformer TUSS 2B is

b. Once per operating cycle, a available. If the unit 1 test will be conducted station service transformers is simulating a loss of the second source, a =ini=um of offsite power and similar two 500kV lines must be conditions that would exist available.

with the presence of an actual safety-injection

- Both 161-kV lines, both cooling signal to de=enstrate the 292 Amendment No. 75

LJMITING CONDITIC!!S FOR 0?ERITIC?!

SURVEILLANCE REOUIRE!C!!TS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXIL'? RY ELECTRICAL SYSTEM tower transformers, and the bus following:

t tie board energized and capable of supply power to the units 1

1. Deenergization of the and 2 shutdown boards, provided e=ergency buses and load that the second source is from shedding from.the the 500-kV system.

e=ergency buses.

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- Both 161-kV line,s, one common

2. The diesel starts from station service transformer, and a=bient condition on the one cooling tower transformer auto-start signal, (through the bus tie board) energizes the emergency provided the cooling tower buses with permanently transformer is not parallel to connected loads, the common station service energizes the auto-transfor=er and provided that connected e=srgency the second source is from the loads through the load.

500-kV system.

sequencer, and operates for greater than or A re. actor shall not be started equal to five =inutes up (cade critical) from the Hot while its generator is Standby Condition unless all of loaded with the the following conditions are e=ergency loads, satis fied :

?. On diesel generator

1. One of the off-site power creaker trip, the loads sources listed above is are shed from the available and capable of e=er.gency buses and the supplying auxiliary power to diesel restarts on the the shutdown boards.

auto, start signal, the e=ergency buses are

2. Three units 1 and 2 diesel energized with generators shall be permanently connected operable.

loada, the auto-connected emergency

3. An additional source of power loads are energized consisting of one of the through the load following:

sequencer, and the diesel operates for

a. A second off-site power greater than or equal to source available and five minutes while its capable of supplying power generator is leaded with to the shutdown boards.

the emergency loads.

b. A fourth operable units I

c. Once a month the quantity and 2 diesel generator.

of diesel fuel available shall be legged.

4. Buses and Boards Available

d. Each diesel generator shall

a. Start buses 1A and 1B are be given an annual energized.

inspection in accordance Amendment No. 75

LIMITING CCNDITIONS FOR CPERATICN

-SURVEILLANCE REOUIPEMENTS 3.9 AUXI',IA RY ELECTRICAL SYSTEM 4.9 AUXILIABY ELECTRICAL SYSTEM with instructions based on

b. The units 1 and 2 4-kV the manufacturer's o

shutdown boards are recommendations.

energized.

e. Once a month a sample of

c. The 480-V shutdown boards diesel fuel shall be associated with the unit checked for quality. The are energized, quality shall be within acceptable limits specified

d. The units 1 and 2 diesel in Table 1 of the latest auxiliary boards are revision to ASTM D975 and energized.

logged.

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e. Loss of voltage and degraded

2. D. C. Power System - Unit voltage relays eperable on Batteries (250-volt) Diesel 4-kV shutdown boards A, B, C, Generator Batteries (125-Volt) and D.

and Shutdown Board Batteries (250-Volt) i

f. Shutdown busnes 1 and 2 1

energized.

a. Every week the specific gravity and the voltage of

g. The 480V Rx. MOV Boards the pilot cell, and D&E are energized with M-G temperature of an adjacent Sets IDN, IDA, IEN, and cell and overall battery 9

IEA in service.

voltage shall be measured and logged.

5. The 2do-volt unit and shutdown board batterien and

b. Every three months the a battery charger for each measurement shall be made battery boards are operable.

of voltage of each cell to nearest 0.1 volt, specific gravity of each cell, and 1

6. Logic Systems temperature of every fifth ce

These measurements

a. Common accident signal shi be logged.

Icgic system is operable.

c. A battery rated discharge (capacity) test shall be

b. 480-V load shedding logic performed and the voltage, system is operable.

tine, and output current measurements shall be

7. There shall be a minimum of logged at intervals not to 103,300 gallons of diesel exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

fuel in the standby diesel generator fuel tanks.

i Amendment No. 75-293a

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LIMITING CCNDIT!CNS F03 CPERATICH SURVEILLANCE REQUIREMENTS 3 9 A,UXILI ARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM

3. Logio Systems

a. Both divisions of the cosenon accident signal legio system shall be tested every 6 months to demonstrate that it will function on actuation of the core spray system of each.'eactor to provide an automatic start signal to all 4 units 1 and 2 diesel generators.

b. Once every 6 months, the condition under which the 480 Volt load shedding logic system is required shall be simulated using pendant test switches and/or pushbutton test switches to deronstrato that the load shedding logic system would initiate load shedding signals on the diesel auxiliary boards, reactor MOV boards, and the 480-Yolt shutdown boards.

4. Undervoltage Relays a.

(deleted)

b. Once every 6 =enths, the conditions under which the ices of voltage and degraded voltage relays are required shall be simulated with an undervoltage on each shutdown board to 294 Amendment No. 75 Os

L2MITING CONDIT C"O FOR OPERATION SURVETZ. LANCE F.EQUIRE!'ENTS 3 9 AUXILIKRY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM i

i B. Operation with Inoperable B. Operaticn with Inoperable i

Equipment Equip =ent Whenever a reactor is in Startup

1. When only one offsite power l-mode or Run mode and not in a source is inoperable, all cold condition, the availability units 1 and 2 diesel of electric power shall be as generators and associated specified in 3.9. A except as boards =ust be demonstrated to specified herein, be operable i= mediately and daily thereafter.

1. From and after the date that' only one off-site power

2. N.A.

l source is available, reactor operation is permissible for l

seven days.

2. From and after the date that

3. When one or the units 1 and 2 the 4-kV bus tie board diesel generator is found to l

becomes inoperable, reactor be inoperable, all of the CS, l

operation is permissible RHR (LPCI and Containment i

indefinitely provided one of Cooling) Systems and the tuo required off-site power remaining diesel generators source is not supplied from and associated boards shall be the 161-kV system through the de=onstrated to be operable bus tie board.

i==ediately and daily thereafter.

3. When one of the units 1 and 2

. diesel generator is

4. When one 4-kV shutdown board inoperable, continued reactor is !cund to be inoperable, all operation is permissible re=aining 4-kV shutdown boards during the succeeding 7 days, and associated diesel provided that two offsite generators, CS, and RHR (LPCI power sources are available, and Containment Cooling) and all of the CS, RHR (LPCI Systems supplied by the and Containment Cooling) re=aining 4-kV shutdown boards Systems, and the remaining shall be demonstrated to be three units 1 and 2 diesel operable, immediately and generators are operable. If daily thereafter.

this requirement cannot be met, an orderly shutdown

5. When one shutdown bus is found shall be initiated and the to be inoperable all 1 and 2

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reactor shall be shut down diesel generators shall be and in the cold condition proven operable immediately l

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and daily thereafter.

4. When one units 1 and 2 4-kV

6. When one units 1 and 2 Diesel shutdown board is inoperable, Aux. board is found to be continued reactor operation inoperable, the remaining l

is permissible for a period diesel Aux. bcard and each l

not to exceed 5 days, unit 1 and 2 diesel generator l

295 Amendment No. 75

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., LIMITING CCNDITIONS FOR OPERATICN SUR*'EILLA!:CE RECUIREMENTS 3 9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM demonstrate that the e

associated diesel generator' L

will start.

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c. The loss of v'oltage and degraded 1

l voltage relays which start the j

diesel generators from the 4-kV l

shutdown boards shall be cali-l brated annually for trip and l

reset and the measurements j

logged. These relays shall be calibrated as specified in Table 4.9.A.4.c.

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d. 4-kV shutdown board

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voltages shall be recceded l

once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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5. 480-V RMCV boards D and E

a. Once per operating cycle the automatic transfer.

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feature for 480-V RMOV boards D and E shall be functionally tested to verity auto-transfer capability.

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Amendment No. 73F -

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ILIMITING CONDITICNS FOR OPEKATION SURVEILLANCE RECUIREMENTS 3 9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM provided that two off-site shall be proven operable power sources are available, immediately and daily and the remaining 4-kV thereafter.

shutdown boards and associated diesel generators,

- CS, RHR (LPCI and Containment Cooling) Systems, and all 480-2 1

V emergency power boards are operable. If this requirement cannot be met, an 1 =

orderly shutdown shall be initiated and the reactor shall be shut down and in the i

cold condition by the end of J

the fifth day.

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5. When one of 'he shutdown t

busses is inoperable, reactor operation is permissible for a period of 7 days.

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6. When one of the 480-V diesel Aux. boards becomes inoperable, reactor operation is permissible for a period of 5 days.

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7. From and after the date that a.

I cne of the three 250-7elt

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unit batteries and/or its I

associated battery board is J

'found to be inoperable for j

any reason, continued reactor operation is permissible during the succee' ding seven days. Except for routine surveillance testing, the NRC shall be notified within 24 j

hours of the situation, the l

precautions to be taken during this period, and the plans to return the failed j

ccmponent to an operable j

state.

8. From and after the date that one of the 250-volt shutdown

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board batteries and/or its associated battery board is j

found to be inoperable for

i 296 Amendment No. 75 i

r-o LIHITING CGNDITIONS TOR CPERATION

' SURVEILLANCE RECUIREMENTS 3 9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM any reason,. continued reactor operation is permissible during the succeeding five days in accordance with 3 9.B.7.

9. When one division of the Logic System is: inoperable, continued reactor cperation

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-is per=issible 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 durin6 this period, and the p)ans to return the failed component to an operable state.

10. (deleted)

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The following limiting conditions for operation exists for the undervoltage relays which start the diesel generators on the 4-kV shutdown boards, a.

The loss of voltage relay channe'. which starts the diesel generator for a complete loss of voltage on a 4-kV shutdown board e.ay be inoperable for 10 days pro-vided the degraded voltage relay channel on that shut-down board is operable (with -

in the surveillance schedule of 4.9. A.4.b.)

297 Amendment No. 75I

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e LIMITI?;C CO'IDITISC FOR C?EF.ATIC'l SURVFjLLt.!!CE FE *sUIFE?C.;TS 3 0 3UML,.I ARY ELECTRICAL SYSTEM 4.9 !.tiXILIARY FLEFTRIC/L SYSTEM

b. The degraded voltage relay channel which starts the diesel generator for degrad-ed voltsge 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).

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 inoperabic 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 shut-down board are operable (within the surveille.nce schedule of 4.9.A.4.b).

2. The loss of voltage relay channel on that shutdown board is operable (within the surveillance cchedule 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 provid-ed the other shutdown boards and undervoltage relays are operable.

(Within the Amendment No. 75' l

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LIMITI!;G CCNDITIC!iS FOR CPERATION SURVEILLANCE REQUIREME!iTS I

3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM surveillance schedule of 4.9.A.4.b).

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12. When one 480-volt shutdown board le 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-RMOV board M-G set is inoperable, the reactor may remain in operation for a period not to exceed seven days, provided the remaining.480-V RMOV board m-g sets and their associated loads remain operable.

14. If.any two 480-V RMOV board M-G i

sets become inoperable, the reactor shall be placed in the cold shutdown condition within 24' hours.

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15. If the requirements for operating in the" conditions specified by 3.9.B.1 through 3.9.B.14 cannot be met, an i

orderly shutdown shall be initiated and the reactor i

shall be shutdown 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 />.

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297 b f

' Amendment No. 75 i

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- CIMITING CONDITIONS FOR OPERATION

-SURVEILLANCE REQUIREMENTS tr

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3'.9 AUXILIA2Y-ELECTRICAL SY3 TEM '

4.9 AUXILIARY ELECTRICAL SYSTEM

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• C. Operation in Cold Shutdown Whenever the reactor is IC 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.

t 1.-At least two units 1.and 2 diesel generators and their associated 4-kV shutdown-boards shall be operable.

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• 2. An additional source of power consisting of at least one of

' the folicwing:

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'a. ' The unit 1 or 2 unit j

station' service transformers energized.

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b. One 161-kV-transmission line and-its, associated common station service transformer energized.

c. Either 16'1-kV line, one cooling tower transformer and the bus tie board energized and capable of supplying power to the units 1 and 2 shutdown-boards energized.-

d. A third operable diesel generator.

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3. At least one 480-V shutdown i

board'for each unit must be operable.

4. One 480-V RMOV board motor-generator-(M-G) set is l

required for each RMOV board (D 'or E) required to support operation of the RHR system in accordance with 3.5.B.9.

298 Amendment No. 75' s

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- 9 BASES The objective of this specification is to assure an adequate source of electrical power,to operate facilities to cool the plant-during shutdown and to operate the engineered safeguards following an accident.

There are three sources of alternating current electrical' energy available, namely, the 161-kV transmission system, the 500-kV system by way of either or both nuclear generating units 1 and 2 unit station service transformer B, and the diesel generators.

The generator breaker for units 1 and 2 can provide non-interruptible sources of off-site power from the 500-kV transmission system to the units 1 and 2 shutdown boards.- A source of auxiliary power,can be supplied from the 161-kV transmission system through the common station service transformers or the cooling tower transformer by way of the bus tie board.

The 4-kV bus tie board may remain out of service indefinitely provided one of the required off-site power sources is not supplieo from the 161-kV system through the bus tie board.

The minimum fuel oil requirement of ?O3,300 gallons is sufficient for seven days of full loaC operation of three diesels and is conservatively based on availability of a-replenishment r. o p p ly.

Th6 degraded voltage sensing relays provide a start signal to-the diesel generators in the event that a dateriorated voltage condition exists on a 4-kV shut'down board.

This starting signal is independent of the starting signal 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 l

become inoperable.

The 15-day inoperable time limit specified when one of the three phase-to-phase degraded voltage relays is inoperable is justified based on the two l

out of three permissive logic scheme provited with these l

relays.

A 4-kV shutdown board is allowed to be out of operation for a brief period to allow for maintenance and testing, providing all remaining 4-kV shutdown boards and associated

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diesel generators CS, RHR, (LPCI and Containment Cooling) l Systems supplied by the remaining 4-kV shutdown boards, and i

all emergency 480-V power boards are operable.

There are eight 250-volt d-c battery systems each of which consists of a battery, battery charger, and distr,ibution equipment.

Three of these systems provide power for unit 299

-Amendment No. 75 w

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Tabic 4.9.A.4.c VOLTACC RELAY SETPOINTS/ DIESEL CENERATdR START 3

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Relav location N

Trip I.cvel Se'etine Remarks 1.

4-kV Shutdodn Boards Trip Setpoint:

O volts with a 1.5-second time Start diesel genera-

]j telay tors on loss of of f-Allowable Values:

+.1 second site power.

Trip Range:

1.4 to 1.6 seconds Reset Setpoint:

2870-V q

Allowabic Values:

1 2% of 2870-V Reset Range:

2813-V to 4' 92 7-V I!nd e rvol t a nc 2.

4-kV Shutdc Boards Trip Setpoint:

3920 Second Icvel under-voltage sensing re-Allowable Values:

3900-3940 ays - start diesel w$

generator on degrad-Reset Setpoint:

Reset at i 1.5% above trip value

1. 3 "E#'

o Setpoint Critical Time Timer (seconds)

(seconds) f 3.

4-kV Shutdown Boards 2-211-1A 9.27 + 5%

0.3 Auxiliary timers for (Timers shown for 4-kV shutdown board 2-211-2A 4.00 + 5%

N/A second Icvel under-voltage sensing A.

4-kV shutdoun 2-211-3A 7.43 1 5%

8.2 relays.

boards B. C, and D' 1

2-211-4A 1.3615%

.1. 5 The setpoint ranges similiar, except for change of suffix) specified assure that the operating times will be below the critical times speci-fled.

These ranges are based on timer repeatability of'+ 5%

as specified by the

_i manufacturer.

319 BASES (cen't) i control functions, operative power for unit motor loads, and alternative drive power for a 115-volt a-c unit preferred motor-generator set.

One.250-volt d-c system provides power for common plant and transmission system control functions, drive power for a 115-volt a-c plant preferred motor-generator set, and emergency drive power for certain unit large motor loads.

The four remaining systems deliver control power to the 4160-volt shutdown boards.

Each 250-Volt d-c shu:down board cont.rol power supply can receive power from its own battery, battery charger, or from a spare charger.

The chargers are pc.rered from normal plant auxiliary power or from the standby diesel-driven generator system. Zero resistance short circuits between the control power supply and the shutdown board are cleared by fuses located in the respective control power supply.

Each power supply is located in the reactor building near the shutdown board it supplies. Each battery is located in its own independently ventilated battery rocm.

The 250-volt d-c system is so arranged, and the batteries sized su,ch, that the loss of any one unit battery will not prevent the safe shutdown 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 safeguards control circuit is annunciated in the main control room of the unit affected.

The loss of one 250-Vol't shutdow *.oard battery affects nor=al control power dn'ly for the 4160-Volt shutdown board which is:supplie.s. The station battery supplies loads that are not essential for safe shutdown and cooldown of the nuclear system. This battery was not considered in the

, accident load calculations.

There are two 480-V ac Reactor Motor-Operated Valve (RMOV) Boards that contain motor-generator (M-G) sets in their feeder lines. These 480-V ac RMOV boards have an automatic transfer from their normal to alternate power source (480-V ac shutdown boards).

The M-G sets act as electrical isolators to prevent a fault from propagating between electrical divisions due to an automatic transfer. The 480-V ac RMOV boards involved provide motive power to valves associated with the LPCI mode of the RHR system. liaving an M-G set out of service reduces the ascurance that full RHR (LPCI) capacity will be available when required.

Since sufficient equipment is available to maintain the minimum ccmplement required for RHR (LPCI) operation, a 7-day servicing period is justified. Having two M-G sets out of service can considerably reduce equipment availability. Therefore, the affected unit shall be placed in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Amendment No. 75 3no

4.9 RAtts The monthly tests of the diesel generators are primarily to check for fatture* and deterioration in the system since last use.

The diesels will

=*

he inaded to at least FS percent of rated power while engine and generater temperatures are stabilized (aboo* one hour). The minimum 75 percent load will prevent noot f o rma tion in *,re cylinders and injection nostles. Opera-tien up to an equilibetum teeperature ensures that there is no overheat problea. The tests also provide en ene.ine and generator operating history to he compared with subsequent enP,tne-renerator test data to identify and any acchenical or electrical deficiency before it can result in to correct a system failure.

The test durloc refuelinr. outages is more comprehensive, including proce-dures that are =nst effectively conducted at that time.

These include automarte actuation and functional cappbtitty tests to verify that the cererators can start and be ready to assume load in 10 seconds. The annual innocetion will detect any gians of veer lona before f ailure.

hatecry matnteanner with resard to the floating charte, equ'Itrinr. charte, and elretrolyte icvel will be based on the manuf acturer's instruction and saund maintenance practices. In addition, written records will be eatn-tatue.1 of the b.sttery performance. The plant batteries will deteriorate with time but practpttous failure is unitkely. The tyoc of surveillaner colled for in this specification is that which has been demons' sted through empertence to ps ovide an indication of a cell becoming irregular or unser-viceable tone, before it beenees a failure.

Tbc equ s11 s tne, c h.t r ee, a s recommended by the minufacturer. Is vital to main-tatning the Ampere-hour capacity of the battery, and wt11 be applied as secommended.

The tc*ttne of the loctc mysteas will verif y the ability of the lo2tc sv9te*s t* brine t'n. tortitary elec t rical system to running standbv readinese with t w s' t s e m e of an acrtdant signal from any reactor ur an un.lervoltaee etsnal l oa thc 4-kV shutdown boards.

I ic periodle simuistion nf accidr.nt 9ttnals in conjunction with dieset gene-retor voltane availabic signals will confirm the al 111ty of the 480-volt load shedding locte syst :m to acquent'lally shed and res' art 430-volt loads if an ace tilent stenal were present and diesel tenerator voltste were the only source of elect rical power.

K F F t.M ENCES 1.

Jormal Ausillary Power System (SFNP F5AR subsection 8.4) 2.

Standb.e A.C. Powe r Supply and Ut stributtun (SFN1' FSAR subsection 3.5) 1.

2 50- vol t D.C. Power Supply and Distribution (BFNF FSAR subsection 8.6) 301 Amendment No. 7f s_

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UNITED STATES j -

g NUCLEAR REGULATORY COMMISSION ~

g.

4j WASHINGTON, D. C 20555

%... *.6 s

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-250 BROWNS F2RRY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILTIY OPERAT_ING LICENSE Amendment No. 72 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 April 9,1981 as supplemented by letters dated June 8,1981, July 2,1981, July 31,1981 and August 17, 1981, 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 appifcable 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 License No. DPR-52 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications container in Appendices A and B, as revised through Amendment No. 72, a < hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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'2-'

3.

This. license. amendment is effective within 30 days of issuance.

P-FOR THE NUCLEAR REGULATORY COMMISSION

/

/

Thomas A.

ppolito, Chief 4

Operating Reactors Branc5 #2 Division of Licensing

Attachment:

-Changes'to the Technical Specifications Date of Issuance: September 3,198I

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l 4TTACHMENT.TO LICENSE AMENDMENT NO. 72 FACILITY OPERATING LICENSE NO. DPR-52 3

00CKET NO. 50-260

' Revise Appendix A as follows:

1.

Remove. the following pages and replace with identically numbered pages:

291/292

• 293/294 295/296 297/298 299/300*

301/302 l

2.

• The.underl.ined pages ai e the pages being changed; marginal lines on these l

pages indicate the revised area. The overleaf page is provided for convenience.

t 3.

Add the following new pages:

293a l

294a 297a 2R7b 298a

• The only change on page 300 is a relocation, verbatim, of information formerly on page 299.

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e

3. 4 C/4.3. C Machsnical Vacuu_7 F m_

lint is to limi: the T5, pur;ose of isolating the mechanical vacuum pump telsene of setivity fres the main condenser.

During an accident, fission p r oduc t s would be tranetorted free the reactor thrnugh the main s:eam lines ts the condenser. The fiseton product rad'ose:1vity would be eensed by the ma i-steam line radicactivity soni:sts whi:h initia:e isolation.

&.I.A end

.t.!

1A!!!

T he s u rv e t *.! 4 n :e r ecu i remen: s given under Spe:ifics:1:n 4.!. A and 4.8.3 rr; vide sura,ce ima: li;uid arid ga s eo_s wa s:ss are pre;erly :entrolled ar: -c - : : = r e u :ur: : any rettase of r id i= se:ive 4 : e r ia *. e in :he liquid a r.: caseous ef!!we-:. These s u rve

• i' 4..c c requiremen:s ;r:vid e the ca: a f:: :ne it:ensee and the Cc==! seton cs evalue:e the s:stion's perf or ance 4

rt.a t t se :: rafteartive vastes releasec :s :he enviren=en:.

Reperts en tra quan:!:tes cf radicactive meterials released in effluents shall be furniswed :n 15e Coaniasion en the basis ;f Section 6 of,these technt:41

ecift:attems. Cn the basis of such re cris Lad any addittenal inf sr:s-

n the Ca--ission may obtain ft:n :5e li:ensee or others, the Carnis sion m:? frem ti=e to time require the li:enset : take such ac:icas as :ne CM asten deeze aspecsria t e.

3. t. 3 a.a 4. s. 0 assrs l'.9c ekj ecti. e of this specifi:4 tion is := ass ru ths: leakage fr:s tryrodac, scures, and spe:ial nuclear radica::ive =4:erial seur:es 4:cs c t exc eed allevah'le 11m154.

291 4

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LIMITI?iG C0!!DITIO!!S FOR OPERATIO!!

SURVEILLA! ICE REQUI:,E!Gt:TS 3 9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM Applicability Applicability Applies to all the auxiliary Applies to the periodic testing electrical power system.

requirements of the auxiliary electrical systems.

Objeetive, Objective To assure an adequate supply of Verify the operability of the electrical power for operation of auxiliary electrical system.

those systems required for safety.

Specificatic-n Specification A." Auxiliary Electrical Equipment A. Auxiliary Electrical Equipment A reactor shall not be started

1. Diesel Generators up (made critical) from the cold condition unless four units 1

a. Each diesel generator shall and 2 diesel generators are be manually started and operable, the requirements of loaded once each month to 3.9.A.4 through 3.9.A.7 are met demonstrate operational and two of the folic 41ng off-readiness. The test shall site power sources are available centinue for at least a one as stated with no credit taken hour period at 75". of rated for the two 500-kV Trinity load or greater.

lines.

During the conthly

- Both 161-kV lines and co= mon generator test, the diesel station service transformers generator starting air provided the second source is compressor shall be checked from the 500kV system.

for operation and its ability to recharge air

- The unit 1 unit station service receivers. The. operation transformer TUSS 1B is available.

of the diesel fuel oil If the unit 2 station service transfer pumps shall be transformers is the second demonstrated, and the source, a minimum of two 500-kV diesel starting time to lines must be available, reach rated voltage and speed shall be logged.

- The unit 2 unit station service transformer TUSS 2B is

b. Once per operating cycle, a available.

If the unit 1 test will be conducted 3

statien service transformers is simulating a loss of the second source, a minimum of offsite power and similar two 500kV lines must be conditions that would exist available.

with the presence of an actual safety-injection

- both 161-kV lines, both cooling signal to demonstrate the 292 Amendment No. 72 6

LIMITI!!G CC!iDITIO:iS FOR CPERATIC!!

SUT.VEILLAliCE ?EUIREME!!TS 3 9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM tower transformers, and the bus following:

tie board energized and capable of supply power to the units 1

1. Deenergization of the i

and 2 shutdown boards, provided emergency buses and load that the second source is from shedding *com the the 500-kV systen, emergency buses.

- Both 161-kV lines, ene common

2. The diesel starts from station service transformer, and ambient condition on the one cooling tower transformer auto-start signal, (through the bus tie board) energizes the emergency provided the cooling tower buses with permanently transformer is not parallel to connected loads, the co= mon station service energizes the auto-transformer and provided thau connected emergency the second souree is from the loads through the load 500-kV system.

sequencer, and operates for greater than or A reactor shall not be started equal to five minutes up (made critical) from the Hot while its generator is Standby Condition unless all of leaded with the the following conditions are emergency loads.

satisfied:

3. On diesel generator

1. One of the off-site power breaker trip, the loads sources listed above is are shed from the available and capable of emergency buses and the supplying auxiliary power to diesel restarts on the the shutdown boards.

auto-start signal, the emergency buses are

2. Three units 1 and 2 diesel energized with generators shall be permanently connected operable.

loads, the auto-connected emergency

3. An additional source of power ioads are energized consisting of one of the through the load following:

sequencer, and the diesel operates for

a. A second off-site power greater than or equal to source available and five minutes while its capable of supplying power generator is loaded with to the shutdown boards, the emergency loads.

b. A fourth operable units 1

c. Once a month the quantity and 2 diesel generator.

of diesel fuel available shall be logged.

4. Buses and Boards Available

d. Each diesel generator shall

a. Start buses 1A and 1B are be given an annual energized.

inspection in acccrdance 293 Amendment No. 72 e

l LIMfTTHC CONDf7 IONS FOR OPERATTO!!

SURVEILLANC:

JUTREME';TS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY f.ECTRICAL SYSTEM l

3. Logie systems I

a. Both divisiens of the common accident signal loS e system shall be i

(

j tested every 6 months to j

demonstrate that it will function on actuation of the core spray system of each reactor to provide an automatic start signal to l

all 4 units 1 and 2 diesel l

generators.

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b. Once every 6 months, the l

condition under which the -

l 480-Volt load shedding l

logic system is required shall be simulated using pendant test switches and/or pushbutten test switches to demonstrate that the load shed. ding icgic system would initiate load shedding signals on the diesel auxiliary boards, reactor MOV boards, and the 480-Volt shutdown 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 l

shall be simulated with an undervoltage on each shutdown board to 294 Amendment No. Y2 l

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r-1.!MITING CCHDITIO*:S FOR OPETATICN SURVEILLANCE RECUIEE!'ENT3 3.9 AUXILI ARY ELECTRICAL SYSTEM 4.9 AUXILI ARY ELECTOICAL SYSTEM with instructions based on

b. The units 1 and 2 4-kV the manufacturer's shutdown boards are recommendations.

energized.

e. Once a month a sample of

c. The 480-V shutdown boards diesel ruel shall be associated with the unit checked for quality. The are energized.

quality shall be within acceptable limits specified

d. The units 1 and 2 diesel in Table 1 of the latest auxiliary boards are revision to ASTM D975 and i

energized.

logged.

e.' Loss of voltage and degraded

2. D. C. Power System - Unit Batteries (250-Volt) Diesel voltage relays operable on Generator Batteries (125-Volt) 4-kV shutdown boards.

and Shutdown Board Batteries C, and D.

(250-Volt)

f. Shutdown busses 1 and 2 energized.

a. Every week the s'ecific p

gravity and the voltage of the pilot cell, and temperature of an adjacent cell and overall battery voltage shall be neasured and logged.

5. The 250-volt unit and shutdown board batteries and

b. Every three nonths the l

l a battery charger for each

=eacurements shall be made l

battery boards are operable.

of voltage of each cell to nearest 0.1 volt, specific gravity of each cell, and

6. Logic Systems teeperature of every fifth I

cell. These measurements

a. Common accident signal shall be logged.

Icgic system is operable.

c. A battery rated discharge (capacity) test shall be l

b. 4SC-7 load shedding logic performed and the voltage, system is operable.

time, and,cutput current I

measurements shall be

7. There shall be a minimum of logged at intervals not to 103,300 gallons of diesel exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, fuel in the standby diesel I

generator fuel tanks.

293 Amendment No. 73 1

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LIMITING C0!!DITIC!!S FOR Ci'EPAYTC:t 3tIRVEILLANCE FRCUIREME!!TS

,3 9 AUXIf.I AHY ELECTRICAL SYSTEM 4.9 AUXILI,*,RY FLECTRICA!. SYSTEM demonstrate that the

. associated diesel generator will start.

c. The loss of voltage and de-graded voltage relay? which start the diesel generators 4-from the 4-kV ehutdown boards shall be calibrated annually for trip and reset and the

=easurements logged. These relays shall be.. calibrated as specified in Table 4.9.A.4.c.

d. 4-kV shutdown board voltages shall be recorded l

once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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Amendment No. 79-

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L L_IMITI!!G CC!!DITICNS FOR OPErJtTIC?!

SUWEILLA!!CE KECUIREMEtITS 3 9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM B.

Operation with Inoperable B. Operation with Inoperable Equipment Equipment Whenever a reactor is in Startup

1. When only one offsite power mode or Run mode and not in a source is inoperable, all cold condition, the availability units 1 and 2 diesel of electric power shall be as generators and associated specified in 3.9. A except as boards must be demonstrated to specified herein.

be operable immediately and daily thereafter.

1. From and after the date that

• only one off-site power

2. N.A.

source is available, reactor operation is permissible for seven days.

~

2. From and a#ter the date that

3. When one of the units 1 and 2 the 4-kV bus tie board diesel generator is found to becomes inoperable, reactor be inoperable, all of the CS, operation is permissible RHR (LPCI and Containment indefinitely provided one of Cooling) Systems and the the required off-site power remaining diesel generators source is not supplied from and associated boards shall be the 161-kV system through the demonstrated to be operable bus tie board.

immediately and daily

.thereafter.

3. When one of the units 1 and 2 diesel generator is

4. When one 4-kV shutdown board inoperable, continued reactor is found to be inoperable, all operation is permissible remaining 4-kV shutdown boards during the succeeding 7 days, and associated diesel provided that tuo offsite generators, CS, and RHR (LPCI power sources are available, and Containment Cooling) and all of the CS, RHR (LPCI Systems supplied by the and Containment Cooling) remaining 4-kV shutdown boards Systems, and the remaining shall be demonstrated to be three units 1 and 2 diesel operatie, immediately and generators are operable. If daily thereafter.

this requirement cannot be met, an orderly shutdown

5. When one shutdown bus is found shall be initiated and the to be inoperable all 1 and 2 reactor shall be shut down diesel generators shall be and in the cold condition proven operable immediately within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and daily thereafter.

4. When one units 1 and 2 4-kV

6. When one units 1 and 2 Diesel shutdown board is inoperable, Aux. board is found to be continued reactor operation inoperable, the remaining is permissible for a period diesel Aux. board and each not to exceed 5 days, unit 1 and 2 diesel generator 295 l

Amendment No. 72

QMXTING CONLITIO?ls FOR OPERATION SURVEILLANCE REOUIREMENTS 3 9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM provided that two off-site shall be proven operable power sources are available, i==ediately and daily and the remaining 4-kV thereafter.

shutdown boards and associated diesel generators.

CS, RHR (LPCI and Containment Cooling) Systems, and all 480-V 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 by the end of the fifth day.

5. When one of the shutdown busses is inoperable, reactor operation is permissible for a period of 7 days.

6. When one of the 480-V diesel Aux. boards becomes inoperable, reactor operation is permissible for a period of 5 days.

5

7. From and after the date that cne of the three 250-Volt 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.

8. From and after the date that one of the 250-volt shutdown board batteries and/or its associated battery board is found to be inoperable for Amendment No. 72

LIMIT!N'1 CONDITICM *0il CPERATICN TURVEILLANCE PEQUTFE ENTO 3 9 AUXILI ARY CLECTRICAL SYSTEM 4.9 AUX 1L!ARY ELECTRICAL SYSTEM any reason, continued reactor operation is permissible during the succeeding five days in accordarca with 3.9.B.7.

9. When one division of the Logic System is inoperable, continued reactor operation is perstasible urder this condition ro s3ven days, provided che L$C3 requirements listed in spec *fication 3 9.B.3 are satisfied. The NRC shall to notified within 24 hcurs of the situation, the precautions to be taken during this period, and the plans La return the failr.d co=ponent to an operable s tate.

10. (deleted)

II' The following limiting condi-tions for operation exists for the undervoltage relays which start the diesel generators on the 4-kV shutdown boarda.

a. The loss of voltage relay channel which starts the diesel generator for a com-plete loss of voltage on a 4-kV shutdown board may be inoperable for 10 days pro-vided the degraded voltage relay channel on I~

297 Amendment No. 73L o k - m ne e

E LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

' 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM C. Operation in Cold Shutdown l

Wh6never the reactor As in cold shutdown condition with irradiated fac1 in the reactor, 9

the availability of electric power shall be as specified in Section 3 9.A except 's specified herein.

1. At least two units 1 and 2 i

diesel generators and their associated 4-kV shutdown boards shall be operable.

2. An additional. source of power consisting of at least one of the following:

I

a. The unit 1 or 2 unit station service transformers energized.

b. One 161-kV transmission line and its associated j

common station service

~

transformer energized.

c. Either 161-kV llne, one cooling tower transformer and tne bus tie board i

energized and capable of supplying power to the units 1 and 2 shutdcun 1

j boards energized.

4

d. A third operable diesel generator.

3. At least one 480-V enutdown board for each unit must be operable.

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298 Amendment No.~72 i

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LIMITING CONDITION 3 FOR OF :RATIC;t SURVEILLANCE REQtTTEEMENT3 3 9 A'iXILIARY ELECTRICAL 3737EM 4.9 AUXILIARY ELECTRICAL SYSTEM that shutdown board is oper-able (within the surveillance schedule of 4.9.A.4.b).

b. The degraded voltage relay channel which starts the diesel generator for degrad-ed voltage on a 4-kV shut-down board e.ay be inoperabic for 10 days provided the loss of voltage relay chanac1 on that shutdown board is oper-able (vichin 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-kV shutdown board may be inoperable for 15 days provided both of the following conditions are satisfied.

1. The oths'r two phase-to-phase degraded voltage relays on that 4-kV shut-down board are operable (within the curveillance 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 degrsded voltage relay channel and the loss of voltage relay channel on a 4-kV shutdown board may be inoperable for 5 days pro-vided the other 297a Amendment No. 7JL

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LIMITING CONDIT!ONS FOR CPE?ATICN SUR"EILLANCE REQUIREMENTS 1

3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM shutdown boards and undervoltage relays are operable.

(Within the surveillance schedule of-4.9.A.4.b).

i

12. When one 480-volt 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 j

shutdown 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 operating in the conditions specified by 3.9.3.1 through 3.9.B.12.cannot be met, an orderly shutdown shall be initiated'and the reactor shall be shutdewn 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 />.

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lE Table 4.9.A.4.c VOLTACE S ELAY SETPOINTS/ DIESEL CENERAT0d START o.

5 Relay Location S

Trip Level Settinc Remarks g

1.

4-kV Shutdown Boards Trip Setpoint:

O volts with a 1.5-second time Start diesel genera-

+

. delay tors on loss of of f-

j Allowable Values

+.1 second site power.

Trip Range:

1.4 to 1.6 seconds Reset Setpoint:

2870-V Allowable Values:

1 2% of 2870-V Heset Range:

2813-V to 2927-V j

llndervoltace 2.

4-kV Shutdown Boards Trip Setpoint:

3920 Sec nd level under-voltage sensing re-Allowable Values:

3900-3940 lays - start diesel n

generator on degrad-f!

Reset Setpoint:

Rese( at 3, l'.5% chove trip value E"E**

Setpoint Critical Time Timer (seconds)

(seconds)

.3.

4-kV Shutdown Boards 2-211-1A 0.27 1 5%

0.3 Auxiliary timers for (Timers shown for 4-kV shutdown board 2-211-2A

4. 00 + 5%

N/A sec nd level under-voltage sensing A.

4-kV shutdown 2-211-3A 7.43 1 5%

8.2 relays.

boards B, C, and D, 2-211-4A 1.36 1 5%

~ 1. 5 lie setpoint ranges similiar, except for change of suffix) specified assure that the operating. times will be below the critical times speci-fled.

These ranges are based'on timer repeatability of + 5%

as specified by the manufacturer.

39 BASES The objective of this specification is to assure an adequate source of electrical power to operate facilities to cool tne plant during shutdown and to operate the engineered safeguards following an accident.

There are three sources, of alternating current electrical energy available, namely, the 161-kV transmission system, the 500-kV system by way of either or both nuclear generating units 1 and 2 unit station service tr ansformer B, and the diesel generators.

The generator breaker for units 1 and 2 can provide non-interruptible sources of off-site power from the 500-kV transmission system to the units 1 and 2 shutdown boards.

A source of auxiliary power can be supplied from the 161-kV.

transmission system through the common station service transformers or the cooling tower transformer by way of the bus tie board.

The 4-kV bus tie board may remain out of service indefinitely provided one of the reqafred off-site power sources is not supplied from the 161-kV system through the bus tie board.

The minimum fuel oil requirement of 103,300 gallons is sufficient for seven days of full load operation of three diesels and is conservatively based on availability of a replenishment supply.

l The degraded voltage sensing relays provide a start signal to the diesel generators in the event that a deteriorated voltage condition exists on a 4-kV shutdown board.

This starting signal is independent of tha starting signal 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-day inoperable time limit specified when one of the three phase-to-phase degraded 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, providing all remaining 4-kV shutdown boards and associated diesel generators CS, RHR, (LPCT 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-volt d-c battery systems each of which consists of a battery, battery charger, and distribution equipment.

Three of these systems provide power for unit 299 Amendment-No. 72

39 BASES (con't) control functions, operative power for unit motor loads, and

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alternative drive power for a 115-volt a-o unit preferred motor-generator set.

One 250-volt d-c system provides power for common plant and transmission system control functions, drive power for a 115-volt a-o plant preferred motor-,

generator set, and emergency drive power for certain unit large motor load 1.

The four remaining systems deliver control power-to the 4160-volt shutdown boards.

Each 250-Volt d-c shutdown board control power supply can receive power from its own battery, battery charger, or from a spare charger.

The chargers are powered from normal plant auxiliary power or from the standby diesel-driven generator system. Zero resistance short circuits between the control power supply and the shutdown board are cleared by fuses located in the respective control power supply. Each power supply is located in the reactot building near the shutdown board it supplies.

Each battery is located in its own independently ve.stilated battery room.

The 250-volt d-c system is so arranged, and the batteries sized such, that the loss of any one unit battery will not prevent the safe

. shutdown 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 safeguards control circuit is annunciated in the main control roc.a' of the unit affected. The loss of one 250-Volt ' shutdown board battery affects normal control power only

,1 for the 4160-Volt shutdown board which is supplies. The station battery supplies loads that are not essential for safe shutdoun and cooldown of the nuclear system. This battery was not considered in the accident load calculations.

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. Amendment No. 72

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.t 4. 4 __H,A S T.S_

The monthly t ent o of t he diesel generators 9re primarily to check The for failures and deterioration in the system since last use.

diescle vill be loaded to at least 75 percent of rated power while engine and generator temperatures are stabilited (about one hour).

The minimum 75 percent load will prevent soot formation ?n the cylinders and injection nozzles. Operation up to an equilibrium temperature ensures that there is no overheat problem. The test also provides an engine and generator operating history to be compared with subsequent engine-generator test data to identify and to correct any mechanical or electrical deficiency before it can result in a system failure.

The test during refueling outages is more comprehensive, including These procedures ' that are most ef fectively conducted at that time.

include automatic actuation and functional capability tests to verify that the generators ccn start and be ready to assume load in 10 The annual inspection will detect any signs of wear long seconds.

The diesel generators are shared by units 1 and 2.

before failure.

the capability for the units 1 and 2 diesel generators Therefore, the emergency loads will be perfor=ed during the unit 1 to accept operating cycle using the unit i loads.

Battery maintenance with regerd to the floating charge, equalizing charge, and cicetrolyte le rel will be based on the manufacturer's instruction and sound maintenance practices. In addition, vritten records will be maintained of the battery performance. The plant l

batteries will deteriorate with time but precipitous failure is The type of surveillance called for in this specification unlikely.

is that which has been demonstrated through experience'to provide

[

an indication of a cell becoming irreg01ar or unserviceable long before it becomes a failure.

The equalizing charge, as recommended by the manufacturcr, is vital l

to maintaining the Ampere-hour capacity'of the battery, and will be applied as recommended.

r f

The testing of the logi: systems sill verify the ability of the 1ctic systems to bring the auxiliary electrical system to running standby readiness with the preacnce of an accident signal frcm any reactor or an undervoltage signal on the A-RV shutdown boards.

i The periodic simulation of accident signals in conjunction with diesel generator vultage available signals will confire t.he ability of the 4PO-volt load shedding logic system to sequentially shed and restart 480-volt loads if an accident signal were present and diesal generator voltage were the only source of electrical power.

REFERENCES 1.

Normal Auxiliary Power System (BFNP FSAR subsection 8.4)

Standby A. C. Power Supply and Distribution (BFNP FSAR subsection 8.5) 2.

250-volt D. C. Power Supply and Distribution (BFNP FSAR subsection 8.6 3.

301 Amendment No. 73L

L'HITING cnNntTIONS FOR OPF.AATION SL'RVEILLANCE RECUIREMINTS 3.10 cenK ALTERATIONS 4.10 CORE ALTERATIONS Appifcabili(v Amelicability Applies to the fuel handling Applies to the periodic 'e' ting, t s and cors reactivity limitations, of those interlocks and instru-mentation used during refueling and core alterations.'

Objective Objective To ensure that core reactivity To verify the operability of is within the espability of instrumentation and interlocks the control rods and to prevent used in refueling and core criticality'during refueling, alterations.

Specification Specification A.

,Refueline Interlocko A.

Refueling Inter 1'ocks 1.

The reactor mode switch 1.

Prior to any fuel hand-shall be locked in the ling with the head off

" Refuel" position during the reactor vessel, the core alterations and the refueling interlocks refueling interlocks shall be functionally

~

shall be operable except tested. They shall be specified in 3.10. A.5 tested at veekly ir.ter-as and 3.10.A.6 below.

vals thereafter until no longer required. They shall also be tested fol-loving any repair verk associated with the inter-

~"4 locks.

2.

Fuel shall not be leaded 2.

Prior to perfor=ing con-into the reactor core trol red or control rod unless all control rods drive =aintenance on con-are. fully laserted.

trol eclls witheut renoving i;e1 asse=blies, it shall be denenstrated that the core can be made suberitical by a margin of 0.35 percent ok at any tice during the naintenance with the strongesc operable control rod fully withdrawn and all other operable rods fully inserted. Alterna-tively if the remaining 302 S

e