ML18029A228

Proposed Tech Specs Re Auxiliary Electrical Sys Reflecting Changes in 161 Kv Offsite Power Sys Capability

ML18029A228
Person / Time
Site:	Browns Ferry
Issue date:	10/22/1984
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18029A227	List: ML18029A226 ML18029A228
References
TVA-BFNP-TS-203, NUDOCS 8411020320
Download: ML18029A228 (89)

Text

, ENCLOSURE 1

PROPOSED TECHNICAL SPECIFICATION REVISIONS BROWNS FERRY NUCLEAR PLANT (TVA BFNP TS 203) 84ii020320 841022 PDR ADGCK 05000259 P

PDR

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UNIT 1

PROPOSED SPECIFICATIONS

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LIi'IITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEH SURVEILLANCE REQUIREHENTS UNIT 1

4.9 AUXILIARYELECTRICAL SYSTEH (2)

The 500-kV system is available to the units 1 and 2

shutdown boards through the unit 2 station-service trans-former TUSS 28 with no credit taken for the two 500-kV Trinity lines.

If th'e unit 1

station-service transformer is the second

source, a

minimum of two 500-kV lines must be available.

(3)

The Trinity 161-kV line is available to the units 1 and 2

shutdown boards through both common station-service transfor'mers.

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.

292a (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 offsite power and similar conditions that would exist with the presence of an actual safety-injection signal to demonstrate the'ollowing:

(1)

Deenergization of the emer-gency buses and load shedding from the emergency buses.

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0 LIHITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEH SURVEILLANCE RE UIREHENTS 4.9 AUXILARYELECTRICAL SYSTEH (b) If unit'2 is in 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

'n 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.

a ~

At least one offsite power source is available as speci-fied in 3.9.A.l.c.

2.

The reactor shall not be started up (made critical) from the hot standby condition unless all of the following conditions are satisfied:

connected

loads, the auto-connected emergency loads are energized through load sequencing, and the diesel operates for greater than or equal to five

'inutes 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 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 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.

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LIMITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEM SURVEILLANCE REQUIREMENTS 4.9 AUXILIARYELECTRICAI SYSTEM c

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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

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Every week the specific gravity>

voltage and temperature of the pilot cell and overall battery voltage shall be measured and logged.

(2)

A fourth operable 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

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The respective start bus is energized for each common station-service transformer designated as an offsite power source.

b.

, The 4-kV bus tie b.

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Every three months the measurement shall be made of voltage of each cell to near'est 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

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performed and the

voltage,

".ime, and output current measurements shall be logged at inter-vals not to exceed 24 months.

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d.

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.

3.

Logic Systems a

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Both divisions of the common accident signal logic syst'm 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 diesel gene-rators.

e.

The units 1 and 2

diesel auxiliary boards are energized.

293a

0

LIHITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREHENTS 3.9 AUXILIARYELECTRICAL SYSTEH 4.9 AUXILIARYELECTRICAL SYSTEH 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 (RHOV) boards lD 8 1E are energized with motor-generator (mg) sets

1DN, 1DA, 1EN, and 1EA in service.

a.

Common accident signal logic system is operable.

b.

480-V load shedding logic system is operable.

6.

There shall be a minimum of 103,300 gallons of diesel fuel in the standby diesel-generator fuel tanks'.

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.

L'ogic Systems b.

Once every 6 months, the condition under which the 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

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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 shall be calibrated as specified in Table 4 '.A.4.c.

294

LIHITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTE11 SURVEILI,ANCE REQUIREHENTS 4.9 AUXILIARYELECTRICAL SYSTE>1 d.

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-V BIOV Boards 1D and 1E a.

Once per operating cycle the automatic transfer feature for 480-V RfOV boards 1D and lE shall be functionally tested to verify auto-transfer capability.

294a

LINITING CONDITIONS FOR OPERATION

/

3.9 AUXILIARYELECTRICAL SYSTEH SURVEILLANCE RE UIRENENTS 4.9 AUXILIARYELECTRICAL SYSTEN B.

0 eration with Ino erable E~ui ment B.

0 eration with Ino erable EcCEui 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.

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 irom 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 />.

l.

2.

3.

4.

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.

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'mmediately and daily thereafter.

When one 4-kV shutdown board is found to be inoperable, 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.

295

LIHITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIRE11ENTS 3.9 AUXILIARYELECTRICAL SYSTEH 4.9 AUXILIARYELECTRICAL SYSTEH 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-kV 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 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 and 2 diesel gene-rators shall be proven operable immediately and daily thereafter.

6.

When one units 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 therea fter.

5 ~

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.

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

jason, continued reactor operation is permissible during the succeeding 7 days.

Except for routine surveillance

testing, NRC shall be notified within 24 295a

LIHITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEH SURVE LLANCE REQUIREHENTS 4.9 AUXILIARYELECTRICAL SYSTEH hours ot the situation, the precautions to be taken during this period, and the plans to return the failed component to an operable state.

Prom 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.

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 3.9.8.3 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

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The loss of voltage relay channel which starts the diesel generator for a complete loss of 296

LIHITING CONDITIONS FOR OPERATION 3.9 AUKILIARYELECTRICAL SYSTEH SURVEILLANCE RE UIREHENTS 4.9 AUXILIARYELECTRICAL SYSTEH 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).

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'hase-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).

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296a

LIHITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEH SURVEILLANCE RE(}UIREHENTS 4.9 AUXILIARYELECTRICAL SYSTEH 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 under-voltage relays are operable.

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

12.

M>en 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 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 RHOV board mg set is inoperable, the reactor may remain in operation for a period not to exceed seven days, provided the remaining 480-V RHOV board mg sets and their associated loads remain operable.

14. If any two 480-V 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 />.

297

LIMITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEM

15. If the requirements for operating in the conditions specified by 3.9.B.l through 3.9.8.14

'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 297a

LIHITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEi'1 SURVEILLANCE REQUIREHENTS 4.9 AE<ILIARY ELECTRICAL SYSTEil 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.A.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 BIOV board mg set is required for each RHOV board (1D or 1E) required to support operation of the RHR system in accordance with 3.5.B.9.

298

Table 4.9.A.4.C VOLTAGE RELAY SETPOINTS/DIESEL 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 Allowable Values:

3900-3940 Reset Setpoint:

Reset at < 1,5$ above trip value Second level undervoltage sensing relays - start diesel generator on degraded voltage.

Timer Setpoint (seconds)

Cr itical Time (seconds) 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.

e 2-211-1A 2-211<<2A 2-211-3A 2-211-4A 0.3

+ 10$

4.0

+ 10$

6.9

+105, 1.3

+ 104 N/A N/A 8.2 1.5 Auxiliary timers for second level undervol tage sensing r clays.

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.

298a

3.9 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 ar three sources of alternating current electrical energy available, namel name y, the 161-kV transmission

system, the 500-kU transmission

system, and the diesel generators.

The unit station-service transformer B for unit 1 or the unit station-service transformer B for unit 2 provide noninterruptible sources of offsite power from the 500-kV transmission system to the units 1 and 2

'shutdown boards.

Auxiliary power can also be supplied from the 161-kU transmission system through the common station-service transformers or 4-U through the cooling tower transformers by way of the bus tie board.

Th

-k bus tie board may remain out of service indefinitely provided one

'r.e of the required offsite 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 f s v e en days of full load operation of three diesels and is conservatively icien or based 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 voltage 'condition exists, on a 4-kU shutdown boards.

This starting signal is independent of the '

starting signal generated by the complete loss of voltage relays 'and w'll ontinue to function and start the diesel generators on comp1ete loss of 1

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, provided all remaining 4-kV shutdown boards and associated diesel generators, CS,

RHR, (LPCI 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 systems, each of which consists of a attery, battery charger, and distribution equipment.

Three of the s

s y tems provide power for unit control functions, operative power for r

o ese 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-U ac plant-preferred mg set, and emergency drive power for certain unit large motor loads.

The four remaining systems deliver control power to the 4,160-V shutdown boards.

Each 250-V dc 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 standb a

y 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 room.

" 299

1

The 250-V dc system 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 of the loss of offsite power and a design basis acci.dent in any one unit.

Loss of control power to any engineered safeguard control circuits is annunciated in the main control room of the unit affected.

The loss of one 250-V shutdown board battery affects normal control power only for the 4,160-V shutdown board which it supplies.

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 RMOV boards that contain mg sets in their feeder lines.

These 480-V ac RMOV boarrds have an automatic transfer from their normal to alternate power source (480-U ac shutdown boards).

The mg 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.

Having an mg set out of service reduces the assurance that full RHR (LPCI) capacity will be available when required.

S'nce sufficient equipment is available to maintain the minimum complement required for RHR (LPCI) operation, a 7-day servicing period is justified.

Having two mg 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 />.

The offsite power source requirements are based on the capacity of the respective lines'he Trinity line is limited to supplying two operating units because of the load 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 limiting conditions are intended to prevent the 161-kV system from supplying more than two units in the event of a single failure in the offsite power system.

300

4 9

BASES The monthly test of the diesel generators is primarily to check for failures and deterioration in the system since last use.

The diesels

'will be loaded to at least 75 percent of rated power while engine, and generator temperatures are stabilized (about one hour).

The minimum 75-percent load will prevent soot formation in the cylinders and that there s

injection nozzles.

Operation up to an equilibrium temperature

~

r ure ensures a

ere is no overheating problem.

The tests also provide an engine and generator operating history to be compared with subsequent engine-generator test data to identify and to correct any mechanical or

~ electrical deficiency before it can result in a system failure.

The test during refueling outages is more comprehensive includin procedures that are most effectively conducted at that time.

These include automatic actuation and functional capability tests to verify that the generators can start and be ready to assume load in 10 seconds.

The annual inspection will detect any signs of wear long before failure.

Battery maintenance with regard to the floating charge, equalizing

charge, and electrolyte level will be based on the manufacturer's instruction and sound maintenance practices.

In addition, written records will be maintained of the battery performance.

The plant batteries will deteriorate with time but precipitous failure is unlikely.

The type of surveillance called for in this specification. is that which has been demonstrated through experience to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.

The equalizing charge, as recommended by the manufacturer, is vital to maintaining the ampere-hour capacity of the battery, and will be applied as recommended.

The testing of the logic systems will verify the ability of the logic systems to bring the auxiliary electrical system to running standby readiness with the presence of an accident signal from any reactor or an undervoltage signal on the 4-kV shutdown boards.

The periodic simulation of accident signals in conjunction with diesel-generator voltage available signals will confirm the ability of the 480-U load shedding logic system to sequentially shed and restart 480-V loads if an accident signal were present and diesel-generator vol'tage was the only source of electrical power.

REFERENCES 1.

Normal Auxiliary Power System (BFNP FSAR Subsection 8.4) 2.

Standby AC Power Supply and Distribution (BFNP FSAR Subsection 8.5) 3.

250-Volt DC Power Supply and Distribution (BFNP FSAR Subsection 8.6) 4.

Hemorandum from Gene M. Wilhoite to H. J.

Green dated December 4,

1981 (LOO 811208 664) and memorandum from C.

E.

Winn to H. J.

Green dated January 10,'983.(G02 8301-12 002) 301

UNIT 2 PROPOSED SPECIFICATIONS

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LIi1ITIHG COiiDITIONS FOR OPERATION SURVEILLANCE RENDU IREi'lENTS 3.9 AUXILIARYELECTR1CAL SYSTEH 4.9 AUXILIARYELECTRICAL SYSTE>l (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.

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 similar conditions that would exist with the presence of an actual safety-injection signal'o demonstrate the following:

(2)

Deenergization of the emer-gency buses and load shedding from the emergent".

buses.

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 v

~

~~os

~

e p

LI,'IITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREHENTS 3.9 AUXILIARYELECTRICAL SYSTE11

4. 9 AUXILARYELECTRICAL SYSTEM (b) If unit 1

is in cold

shutdown, only one common station-service'ransfor er 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 1 is in cold shutdown and unit 3 is not claiming the Athens line as an offsite source.

NOTE FOR (3)

AND (4)-

Mith no cooling tower pumps or fans

running, a cooling tower transformer may be substituted for a common station-service transformer.

a

~

At least one offsite power source is available as speci-fied in 3.9.A.l.c.

2.

The reactor shall not be'tarted up (made critical) from the hot standby condition unless all of, the following conditions are satisfied:

connected

loads, the auto-connected emergency load's 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 accor'dance 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 revision to ASTL1 D9?5 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.

293

~

R

~ ~

LIi'JITING COi%)ITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEH SURVEILLANCE REQUIRE>IENTS 4.9 AUXILIARYELECTRICAL SYSTE>l C.

An additional source of power consisting of one of the following:

(1}

A second offsite power source available as specified in 3.9.A.l.c.

'a

~

Every week the specific gravity,

voltage, and temperature of the pilot cell and overall battery voltage shall be measured and logged.

(2)

A fourth operable units 1 and 2 diesel generator.

Requirements 3.9.A.3 through 3.9.A.6 are met.

3.

Buses and Boards Available a ~

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.

d.

The units 1 and 2

4-kV shutdown hoards are energized.

The 480-V shutdown boards 2A and 2B are energized.

The respective start bus is energized for each common station-service transformer designated as an offsite power source.

b.

c ~

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.

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 diesel gene-rators.

e.

The units 1 and 2

diesel auxiliary boards are energized; 293a

~

LIHITING CONDITIONS FOR OPERATION 0

SURVEILLANCE REQUIREHENTS 3.9 AUXILIARYELECTRICAL SYSTEH 4.9 AUXILIARYELECTRICAL SYSTEH 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 480V reactor motor-operated valve (RHOV) boards 2D 6 2E are energized with motor-generator (mg) sets 2DN, 2DA, 2EN, and 2EA in service.

a ~

b.

Common accident signal logic system is operable.

480-V load shedding logic system is operable.

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 4.

Undervoltage Relays a

~

b.

(Deleted)

~

Once every 6 months, the conditions under which the lo..s 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.

b.

Once every 6 months, the condition unde=

which the 480-volt 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 aux" iarv

boards, rmov boards, and the 480-V shut-down boards.

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

'-kV shutdown boards shall be calibrated annually for trip and reset and the measurements logged.

These relays shail be calibrated as specified in Table 4.9.A.4.C.

294

l

LIHITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEH SURVEILLANCE REQUIREHENTS 4.9 AUXILIARYELECTRICAL SYSTEH d.

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.

480V RHOV Boards 2D and 2E a.

Once per operating cycle the automatic transfer feature for 480V RHOV boards 2D and 2E shall be functionally tested to verify auto-transfer capability.

294a

LI 1ITING CONDITIONS FOR OPERATION e

3.9 APiILIARYELECTRICAL SYSTEH B.

0 eration with Ino erable

~Eui ment SURVEILLANCE REQUIREHENTS 4.9 AUXILIARYELECTRICAL SYSTEH

~Eui 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.

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'noperable, reactor operation is permissible indefinitely provided one of the required offsite power sources is not supplied fr'om 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 />.

3.

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.

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 assoc'iated 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-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.

295 e

\\

f)l

LIHITING CONDITIONS FOR OPERATION 3.9 AUXILIARYEIECTRICAL SYSTEi'1 SURVEILLANCE REQUIRE'i1ENTS 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-kV 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 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

5.

(v'hen a shutdown bus is found to be inoperable, all 1 and 2 diesel gene-rators shall be proven operable immediately and daily thereafter.

6.

@hen one units 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.

5.

t'ien 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 routine 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, 295a

0

'Ii'1ITING CONDITIONS OPERATION SURVEILLANCE RE UIRE.'lENTS 3.9 AUXILIARYELECTRICAL SYSTEM'1 4.9 AlEILIARYELECTRICAL SYSTE.'1 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 3.9.3.7 Mhen 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 plan to return the failed component to an operable state.

10. (deleted)

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

296

Lla1ITIiVG CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEi1 SURVEILLANCE REOUIRE 1EVTS 4.9 AUXILIARYELECTRICAL SYSTEH a

~

b.

The 1'oss of voltage relay channel which

'starts the diesel generator for a complete loss of 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 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.4.3}.

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.

296a

LIi'lITING CONDITIONS FOR OPERATION SURVEILLPSCE RE UIRE;"iEFTS 3.9 AUXILIARYElECTRICAL SYSTEil 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.

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

12.

When 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 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 R'IOV board mg set is inoperable, the reactor may remain in operation for a period not to exceed seven days, provided the remaining 480-U RiOU board mg sets and their associated loads remain operable.

~~ tMal~

jan%.

E JI 297

LIHITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTE>I

14. 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 />.

15. If the requirements for operating in the conditions specified by 3.9.B.1 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 REQUIRE)'lENTS 4.9 AUXILIARYELECTRICAL SYSTE.'I 297a

3.9 AKZILIARYELECTRICAL SYSTEH C.

0 eration in Cold Shutdown SURVEILLANCE REgUIREHENTS 4.9 AUXILIARYELECTRICAL SYSTEH 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.

l.

At least two units 1 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 1 and 2 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 480-U shutdown board for each unit must be operable.

4.

One 480-V RHOV board mg set is required for each

R10V board (2D or 2E) required to support operation of the RHR system in accordance with 3.5.B.9.

298

Table 4.9.A.4.C-VOLTAGE RELAY SETPOIHTS/DIESEL GENERATOR START Rela Location

'Zri.

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

+ 2C of 2870-V 2813-V to 2927-V Start diesel generators on loss of offsite power.

Undervolta e

2.

4-kV Shutdown Boards Trip Setpoint:

3920

~ Allowable Values:

3900-3940 Reset.Setpoint:

Reset at < 1.5$ above trip value Second level undervoltage sensing relays start diesel generator on degraded voltage.

Timer Setpoint (seconds)

Critical Time (seconds) 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. )

2-211-1A

'-211-2A 2-211-3A 2-211-4 A 0.3

+ 10$

4.0

+ 10$

6.9

+ 10$

1.3

+ 104 W/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 + 5f as specified by the manufacturer.

298a

3.9 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.

1here are three sources of alternating current electrical energy available,

namely, the 161-kV transmission

system, the 500-kV transmission system and the diesel generators.

The unit station-service transformer B for unit 1 or the unit station-service transformer B for unit 2 provide noninterruptible sources of r ffsite power from the 500-kV transmission system to the units 1 and 2

shutdown boards.

Auxiliary power can also be supplied from the 161-kV transmission system'hrough the common station-service transformers or through the cooling tower transformers by way of the bus tie board.

The 4-kV bus tie board may remain out of service indefinitely provided ore of the required offsite 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.

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 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 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, provided all remaining 4-kV shutdown boards and associated diesel generators, CS,

RHR, (LPCI 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 systems, each of which consists 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-volt ac plant preferred mg set, and emergency drive power for certain unit large motor loads.

The four remaining system deliver control power to the 4,160-V shutdown boards.

r Each 250-V dc 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 reactor building near the shutdown board it supplies.

Each battery is located in its own independently ventilated battery room.

299 h

yV

~

w V

The 250-V dc system is so arranged, and the batteries 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 of the loss of offsite power and a design basis accident in any one unit.

Ioss of control power to.

any engineered safeguard control circuits is annunciated in the main control room of the unit affected.

The loss of one 250.-V shutdown board battery affects normal control power only for the 4,160"U 'shutdown board which it supplies..

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 RMOU boards that contain mg sets in their feeder lines.

These 480-V ac RMOV boarrds have an automatic transfer from their

'ormal to alternate power source (480-V ac shutdown boards).

The mg 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 IPCI mode of the RHR system.

Having an mg set out of service reduces the assurance that full RHR (LPCI) capacity will be available when required.

Since suffic'"nt equipment is available to maintain the minimum complement required for RHR (IPCI) operation, a 7-day servicing period is justified.

Having two mg 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 />.

The offsite power source requirements are based on t:he capacity of the respective lines.

The Trinity line is limited to sulplying two operating units because of the load limitations of CSS~'s A and B.

The Athens line is 'limited to supplying one operating unit because of the load limitations of the Athens line.

The limiting conditions are intended to

~ prevent the 161-kV system from supplying more than two units in the ev nt of a single failure in the offsite power system.

Fthymi.V y I f ~ I+I> J 300

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

The diesels will be loaded to at least 75 percent of rated power while engine and generator temperatures are stabilized (about one hour).

The minimum 75 percent load will prevent soot formation in the cylinders and, injection nozzles.

Operation up to an equilibrium tempreature ensures that there is no overheating problem.

The tests also provide an engine and generator operating history to be compared with subsequent engine-generator test data to identify and to correct any mechanical or electrical deficiency before it can result in a system failure.

The test during refueling outages is more comprehensive, including procedures that are most effectively conducted at that time.

These include automatic actuation and functional capability tests to verify that the generators can start and be ready to assume load in 10 seconds.

The annual inspection will detect any signs of wear long before failure.

The diesel generators are shared by units 1 and 2.

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

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.

In addition, written records will be maintained of the battery performance.

The plant batteries will deteriorate with time but precipitous failure is unlikely.

The type of surveillance called for in this specification is that which has been demonstrated through experience to provide an indication of a cell becoming irregular or unserviceable Long before it becomes a failure.

The equalizing charge, as recommended by the manufacturer, is vital to maintaining the Ampere-hour capacity of the battery, and will be applied a's recommended.

The testing of the logic systems will verify the ability of the logic systems to bring the",auxiliary electrical system to running standby readiness with the presence of an accident signal from any reactor or an undervoltage signal on the 4-kV shutdown boards.

The periodic simulation of accident signals in conjunction with diesel generator voltage available signals will confirm the"ability of the 480-volt load shedding logic system to sequentially shed and restart 480-volt loads if an accident signal were present and diesel generator voltage were the only source of electrical power.

301

4.9 BASES REFERENCES 1.

Normal Auxiliary Power System (BFNP FSAR Subsection 8.~)

2.

Standby AC Power Supply and Distribution (BFNP FSAR Subsection 8.5) 3.

250-Volt DC Power Supply and Distribution (BFNP FSAR Subsection 8.6) 4.

Memorandum from Gene M. Milhoite to H. J.

Green dated December 4,

1981 (LOO 811208 664) and memorandum from C. E. Minn to H. J.

Green dated January 10, 1983 (G02 830112 002)

I 30la

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f

) m

UNIT 3 PROPOSED SPECIFICATIONS

4.2.F Minimum Test and Calibration Frequency for Dr c

cy or Dryvcl 1 Le. k Minimum Tesc and Calibration Frequenc quency for S r e 11 ce 101 102

4. 2.C Surveillance Requiremenrs for Concrol Room Inscrumencacion oncro Room Isolation 103 4.2.H Minimum Test and Calibration Fre uenc f

Inscrumencacion on requency for Flood Protection 104 4.2.J 3.5.-1 3.3 '

4. 6.A F 7.A 3+7.8 Seismic Monitoring Instrument S

ument urveillance Requirements Minimum RHRSH and EECH Pump A

1 ump ssignmenc MAPLHCR vs. Average Planar Exposure Reactor Coolant System Inservi I

ce nspection Schedule Piimary Containment Isolation Valves Testable Penecracions vith Do bl u le 0-Ring Seals 105 156a 191 r 182.

182a, 182b 209 262 268 3.7.C 3.>.D 3 ~ 7 ~ E Testable Penecracions vith T b

cata le Bellous Air Tesced Isolbtion Valves Primary Concainmenc Isolation Valves vhich es u c

Terminate Bolov thc 269 270 279 3.J. F Primarv Concainmenc Isolation Valves Loc a ves Located in Hater Sealed 280 3.7.0 3 ~ 7.H Deleced Testable Electrical Pcnetzations 283 4.8.8 4.9.A,4,c 3.11.*

6.8.*

Radioactive Liquid Haste Sampling and Analysts Radioactive Caseous Haste Sampling and Analysis Voltage Relay Setpoints/Diesel Ceneracor Scart Fire Protection System Hydraulic Requirements Minimum Shift Creu Requirements 310 355n 390 vit

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.9 AKiII,IARYELECTRICAI SYSTEM'1 (2)

NOTE FOR,(2):..

The Trinity 161-kU line is available to the unit 3 shutdown boards through a

common station-service o'

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.

AIKIDO,IARY EIECTRICAL SYSTE<f 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.

The Athens 161-kU line is available to the unit 3 shutdown boards through a

common station-service or cooling tower transformer.

I

'If either unit l or unit 2.is claiming the Athens line as an offsite

'source, it may not be claimed as an offsite source for unit 3.

(3)

NOTE FOR (3):

NOTE FOR (2)AND (3):If both Athens and Trinity lines are

claimed as the two offsite sources for unit 3,'no'credit may be taken for the Athens-Trinity line tie breaker.

Speci-fically, the Athens line supplies unit 3

through common station-service trans-former A or cooling tower transformer l, 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 CONDITIONS FOR OPERATION SURVEILLANCE REQUIREHENTS NOTE:

(Continued) and the Trinity line must supply unit 3 through common station-service transformer B or cooling tower transformer 2.

2.

The reactor shall not be started up (made critical) from the hot standby condition unless all of the following conditions "are satisfied:

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.

Co An additional source of power consisting of one of the following:

(l)

A second offsite power source available as specified in 3.9 '.l.c.

(2)

A fourth unit 3 diesel generator operable.

d.

Requirements 3.9.A.3 through 3.9.A.6 are met.

3.9 AUXILIARYELECTRICAL SYSTEH 4.9 AUXILIARYELECTRICAL SYSTEH 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.

Once a month the quantity of diesel fuel available shall be logged.

k d.

Each diesel generator sh'all 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 1

of the latest revision to ASTH D975 and logged.

318

1 1

Ll~a1ITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIRE>IENTS 3.9 AUXILIARYELECTRICAL SYSTE'I 4.9 AUXILIARYELECTRICAL SYSTE>1 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.

I,oss 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 R110V 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 2.

DC Power System - Unit Batteries (250-U),

Diesel-Generator Batteries (125-V) and Shutdown Board Battery (250-V) overall battery voltage shall be measured and logged.

b.

Every three months the measurements shall be made of voltage of each, cell to nearest 0.1 volt, specific gravity of each cell, and temperature of every fifth cell.

These measurements shall be logged.

c.

A battery rated discharge (capacity) test shall be performed and the

voltage, time, and output current measurements shall abc logged at intervals not to exceed 24 months.

3.

Logic Systems a.

Both divisions of the accident signal logic system shall be tested every 6

months to demonstrate'that it will function on actuation of the core spray system of the reactor to provide an automatic start signal to all 4 diesel generators.

a.

Every week the specific gravity, v'oltage,'nd temperature of the pilot cell, and 319

LIHITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEH 6.

There shall be a minimum of 103,300.gallons of diesel fuel in the unit 3 standby diesel-generator fuel tanks.

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.

SURVEILLANCE REQUIREHENTS 4.9 AUXILIARYELECTRICAL SYSTEH 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-V RHOV Boards 3D and 3E a ~

Once per operating cycle, the automatic transfer feature for 480-V RHOV boards 3D and 3E shall be functionally tested to verify auto-transfer capability.

320

LIHITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEM e

SURUEI LI,AiVCE REQUIRE'.1ENTS

4. 9 AKZILIARYELECTRICAL SYSTE.'1 B.

0 eration with Ino erable

~Eui 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 Inoperable E~ei 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 thereafter.

1.

From 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, provided that two 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 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.

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.

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"kU 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"'aily.

When one unit 3 4-kU shutdown board is found to be inoperable, all remaining unit 3 4-kU shutdown boards and associated diesel generators, CS and RHR (LPCI and containment cooling) systems supplied by the remaining 4-kV shutdown boards shall be demonstrated to be operable, immediately and daily thereafter.

321

Lli'1ITING COiVDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTEH SURVEILLANCE REOUIRE.'KNTS 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-kU shutdown boards and associated diesel generators, CS, RHR (LPCI and containment cooling)

systems, and all unit 3 480-U 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.

When one 480-U diesel auxiliary board is found inoperable, the remaining diesel auxiliary board and each unit 3 diesel shall be verified operable immediately and daily thereafter.

5.

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'even 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, t4e precautions to be taken during this period, and the plans.to return the failed component to an operable state.

322

LIl'lITING CONDITIONS FOR OPERATION SURVEILI,ANCE REQUIRE."lENTS 3.9 AUXILIARYELECTRICAL SYSTEH 4.9 AUXILIARYELECTRICAL SYSTEi'l 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, and 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

~

The loss of voltage relay channel which starts the diesel generator for a complete loss of 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).

b.,

The degraded voltage relay channel which starts the diesel generator for degraded voltage on a 4-kV shutdown board may be 323

LDIITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRiCAL SYSTEH SURVEILLANCE RE UIREPENTS 4.9 AUXILIARYELECTRICAL SYSTE>l 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 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 324

~f,

~

~ ~ihP+W @vs

LIHITING CONDITIONS FOR OPERATION 3.9 AUXILIARYELECTRICAL SYSTE11 SURVEILLANCE REQUIRB1ENTS 4.9 AUXILIARYELECTRICAL SYSTEH 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 RfOV board mg set is inoperable, the reactor may remain in operation for a period not to exceed seven

days, provided the remaining 480-V BIOV board mg sets and their associated loads remain operable.

12. If any two 480-V ElOU 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.1 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 />.

~ L4>>

l%>>>>

325

IlilITINGCONDITIONS FO OPERATION 3.9 AUXILIARYELECTRICAL SYSTE>l SURVEILLANCE REQUIRE KNTS

4. 9 AUXILIARYELECTRICAL SYSTEH C.

0 eration in Cold Shutdown Condition 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-kV 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 3 480-V shutdown board must be operable.

One 480-V TQ(OV 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.

326

Table 4.9.A.4.C VOLTAGE RELAY SETPOINTS/DIESEL GENERATOR START Re la Location Tri Level Settin Remarks i

l.

4-kV Shutdown Boards C

i I

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 3EA.

4-kV shutdown boards

3EB, 3EC, and similar, except for change of suffix.)

Timer 2-211-1 A 2-011-2A 2-211-3A 2-211-4 A

3ED, Setpoint (seconds) 0.3

+ 10$

4.0

+

10'.9

+ 10(

1.3

+

10'ritical 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 of + 5$ as specified by the manufacturer.

327

3.9 BASES The ob'ective of j

this specification is to assure an adequate source of electrical pover to operate facilities to cool the unit during shutdown and to operate the engineered safeguards following an accid nt.

There are three sources of alternating current electrical energy available,

namely, the 161-kV transmission

system, the 500-kV transmission

system, and the diesel generators.

The unit station-service transformer B for unit 3 provides a

noninterruptible source of offsite power from the 500-kV transmission.

system to the unit 3 shutdovn boards.

Auxiliary power can also be '

supplied from the 161-kV transmission system through the common station-service transformers or through the cooling tover transformers by way of the bus tie board.

The 4-kV bus tie board may remain out of service indefinitely provided one of the required offsite pover 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 7 days of full load operation of 3 diesels and is conservatively based on availability of a replenishment supply.

I The degraded voltage sensing relays provide a start signal to the diesel 4-generators in the event that.

a deteriorated voltage condition exists o

-kV shutdown board.

This starting signal is independent of the starting signal generated by the complete loss of voltage relays and vill 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 phhase-to-phase degraded voltage relays is inoperable i>> justified based on the two out of three permissive logic scheme provided vith 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 genera'tors, CS, ME, (LPCI and containment cooling) systems supplied by the remaining 4-kV shutdovn

boards, and all emergency 480-V pover boards are operable.

The 480-V diesel auxiliary board may be out of service for short pr riods for tests and maintenance.

There are five 250-V dc battery systems associated with unit 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 unit large motor loads.

ihe fifth battery system delivers control power to a 4-kV shutdown board.

The 250-U dc system is so arranged and the batteries sized so that the loss of any one unit battery will not prevent the safe shutdown and cooidown of all throe units in the event of the loss of offsite power and a design basis accident in any one unit.

Loss of control power to anv engineered safeguard control circuit is annunciated in tho main control room of the unit affected.

328

J

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 accidnet load calculations.

There are two 480-V ac RiOU boards that contain mg sets in their feeder lines.

These 480-V ac RIOU boards have an automatic transfer from their normal to alternate power source (480-U ac shutdown boards).

The mg sets act as electrical isolators to prevent a fault from propagating between electrical divisions due tc an automatic transfer.

The 480-U ac R10U boards involved provide motive power to valves associated with the IPCI mode of the RHR system.

Having an mg set out of service reduces the assurance that full RHR (LPCI) capacity will be available when required.

.Since sufficient equipment is available to maintain the minimum complement required for RHR (LPCI) operation, a 7-day servicing period is justified.

Having two mg 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 />.

The offsite power source requirements are based on the capacity of the respective lines.

The Trinity line is limited,to supplying two operating units because of the load 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 limiting conditions are intended to prevent the 161"kV system from supplying more than two units in the event of a single failure in the offsite power system.

I 329

4-9 BASES The monthl failu y tests of the diesel generators are primarily to check f t

or

'lures and deterioration in the system since last use.

Th d'

se.

e iese s

oa ed to at least 75 percent of rated power while engine and generator temperatures are stabilized (about one hour).

The minimum 75-percent load will prevent soot formation in the cvlinders and injection nozzles.

Operation up to an equilibrium temperature ensures that there is no overheating problem.

The test. also provide an engine and generator operating history to be compared with subsequent eng ne-n ge erator test data to identify and to correct any mechanical ori e ectrical deficiency before it can result in a system failure.

The test du t during refueling outages is more comprehensive, including procedures that are most effectively conducted't that time.

These include automatic actuation and functional capability tests to verify that the generators can start and be ready to assume load in lO seconds.

The annual inspection will detect any signs of wear long before failure.

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.

In addit'o'n, written records will be maintained of the battery performance.

The plant batteries will deteriorate with time but precipitous failure is unlikely.

The type of surveillance called for in this specification. is that which has been demonstrated through experience to provide d

o provi e an in ication of a cell becoming irregular or unserviceable long before it becomes a failure.

The equalizing charge, as recommended by the manufacturer, is vite'. to maintaining the ampere-hour capacity of the battery, and will be ap lied as recommended.

x e app ie The testing of the logic system will verify the ability of the logic systems to bring the auxiliary electrical system to running standby readiness with the presence of an accident signal from any reactor or an undervoltage signal on the start buses or 4-kV shutdown boards.

The periodic simulation of accident signals in conjunction with diesel generator voltage available signals will confirm the ability of the 480-volt load shedding logic system to sequentiallv shed and restart 480-volt loads if an accident signal were present and diesel generator voltage were the onl source of electrical power.

age were t e on y REFERENCES 2.

3.

4.

Normal Auxiliary Power System (BFNP FSAR,subsection 8.4)

Standby A..C. -Power Supply and Distribution (BFNP FSAR subsection 8 5) 250-volt D.C. Power Supply and Distribution (BFNP FSAR subsection 8.6)

Memorandum from G. M. Vilhoite to H. J.

Green dated December 4, 1981 (LOO 811208 664} and memorandum from C.. E. Uinn to H. J.

Green dated January 10, 1983 (G02 830112 002}

330

I ENCLOSURE 2 DESCRIPTION AND JUSTIFICATION (TVA BFNP TS 203)

Technical specification (TS) sections 3.9 and 4.9 for units 1, 2, and 3

have been completely retyped to eliminate excess blank pages, and the text has been revised as discussed.

On units 1 and 2, the 161-kV lines to Browns Ferry Nuclear Plant (BFN) were split into two d'stinct sources, i.e.,

Athens line and Trinity line.

This will simplify the requirements for claiming the 161-kV lines as offsite sources.

TS 4.9.B.2 for units 1 and 2, the bus-tie board operability requirements, were reinstated.

The requirement already exists for unit 3.

In table 4.9.A.4.C of units 1 and 2, the time periods for the undervoltage relay operation on.the 4-kV shutdown boards were revised to reflect more achievable values commensurate with pneumatic relays.

Some time periods were increased, some were decreased, and one was deleted, but the resultant time periods are the same as those for unit 3 which were approved March 29, 1982, in amendment No. 52.

h References between each unit's TS were added as follows.

Notes were added to TS 3.9.A. 1 for units 1 and 2 which refer. operators to unit 3 TS when selecting 161 kV as an offsite source.

For unit 3, notes for TS 3.9.A.1 were added referring operators to units 1 and 2 TS when selecting 161 kV as an offsite source.

The following are proposed revisions which were made to all th. ee units.

The descriptive language throughout 3.9.A was simplified to eliminate ambiguity of offsite source selection.

Zn TS 4.9.A.1, a revision was made to clarify the statement about sequencing loads on diesel generators, thus eliminating the confusion about having a load sequencer The complete text of 3.9 and 4.9 was rewritten to identify specific transformers and to state when substitution may be allowed.

When stating LCOs, the description was changed to state exactly when an orderly shutdown would be completed rather than state "by the nth day."

Also, throughout the text, boards at the 480-V level were individually identified rather than generically stating the boards available.

The sources of normal offsite power to running units were corrected to reflect the B unit station service transformer for 'each unit.

In TS 4.9.A.2a, the requirement to record the temperature of the adjacent cell of the unit batteries, diesel generator batter'es, and shutdown board batteries on a weekly basis was removed.

The temperature for the pilot cell is now to be monitored weekly.

The temperature of each cell is,still being measured and recorded every three months in accordance with 4.9.A.2.b.

These changes more clearly r eflect the surveillances described in the Standard Technical Specification.

Zn the bases, a

statement was added to identify the limitations on the 161-kV system.

The overall effect of the proposed revisions is to simplify the descriptive language to eliminate ambiguity, to reinstate the bus-tie board operability requirements, and to make units 1 and 2 TS more like those of unit 3.

ENCLOSURE 3 DETERMINATION OF NO SIGNIFICANT HAZARDS Browns Ferry Nuclear Plant (TVA 'BFNP TS 203)

Descr 1 tion of amendment re uest:

The 11miting conditions for operation and the surveillance requirements of sections 3.9 and 4.9, auxiliary electr1cal

systems, have been rewritten to reflect the following:

1.

Split the 161-kV lines to BFN into two distinct sources (units 1 and 2

only).

2.

Reinstate the operability requirements for the bus-tie boards, (units 1

and 2 only).

3.

Revise the time periods for the undervoltage relay operation on the 4-kV shutdown boards to ref'lect mor e achievable values commensurate with pneumatic relays (units 1 and 2 only).

4.

Add notes to the LCO sections to make reference to the other units to inform the operators of what offsite sources the other units are using o 5.

Simplify the descriptive language to eliminate ambiguity "of offsite source selection.

6.

Specifically identify transformers and state when substitution may be allowed.

7., Individually 1dentify 480-V boards rather than generically.

8.

Correct the sources of normal offsite power to running units.

9.

Remove the requirement to weekly record the temperature of the adjacent cell of the unit batteries, diesel generator batteries, and shutdown board batteries, and add the requirement of recording the temperature of the pilot cell on a weekly basis.

10.

Revise the basis to reflect the limitations of the 161-kV system.

I Basis for ro osed No Si ificant Hazards Determination:

The Commisssion has provided guidance concerning the application of the standards by providing examples of'ctions that are likely, and not likely, to involve significant hazards considerations (48 FR "14870).

Three examples not likely to involve significant hazards considerations are:

i - A purely administrative change to technical specifications:

for example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature.

0 ii - A change that constitutes an additional limitation, restriction, or control not presently included in the technical specifications:

for example, a narc stringent surveillance requirement vi - A change which either may result in some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, but where the results are clearly within all acceptable criteria with respect to the system or component specified in the Standard Review Plan.

Items 1

g 4 p 5 p 6 g 7, 8, and 10 are being proposed to make necessary corrections, simplify text, remove ambiguity, and make cross-references between units; therefore, they are clearly encompassed by example (i) of actions not likely to involve significant hazards considerations provided by the Commission.

Item 2 above is reinstating a requirement for bus-tie board operability and, therefore, is encompassed by example (ii) of the guidance provided by the Commission.

Item 3 is revising the t1me periods for the undervoltage relay operation on the 4-kV shutdown boards to reflect more achievable values commensurate with pneunatic relays.

Two time periods were increased, two were decreased, and one was removed; but the resultant t1me periods are the same as those for unit 3 which were approved by the Commission by amendment No. 52.

Having been previously approved by the Commisssion for unit 3, the proposed amendment is encompassed by example (v1) of actions not likely to involve signif1cant hazards considerations.

Item 9 removes the requirement to weekly record the temperature of the adJacent cell of the unit batteries, diesel generator batter1es, and shutdown board batteries and adds the requirement to record the temperature of the pilot cell on a weekly basis.

The temperature of each cell is measured and recorded every three months.

The proposed amendment will reflect the same surveillance requirements as those in the Standard Technical Specifications, therefore, it is clearly encompassed by example (vi) of the guidance provided by the Commission.

Since the proposed amendments are encompassed by examples of actions not likely to involve significant hazards considerations, TVA proposes to determine that this amendment involves no significant hazards considerations.