ML20073E219

Amends 152 & 156 to Licenses DPR-24 & DPR-27,respectively, Revising TS 15.3.0, Lco

ML20073E219
Person / Time
Site:	Point Beach
Issue date:	09/23/1994
From:	Hansen A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20073E220	List: ML20073E219 ML20073E222
References
NUDOCS 9409280304
Download: ML20073E219 (17)

Text

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t UNITED STATES ye

.j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20h0001 g

%,.....f WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.152 License No. DPP.-24 i

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Wisconsin Electric Power Company (the licensee) dated May 26, 1994, as supplemented on July 11, 1994, and August 1, 1994, 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; 4

and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license i

amendment, and paragraph 3.B of Facility Operating License No.

DPR-24 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 152, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

9409200304 940923 DR ADOCK 05 26

l 3.

This license amendment is effective immediately upon issuance.

The l

Technical Specifications are to be implemented within 45 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV i

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications l

Date of issuance: September 23, 1994 l

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71 UNITED STATES s

J.if 1 j NUCLEAR REGULATORY COMMISSION a

WASHINGTON. D.C. 205650001 g, y /

s WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.156 License No. DPR-27 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Wisconsin Electric Power Company (the licensee) dated May 26, 1994, as supplemented on July 11, 1994, and August 1, 1994, 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; 1

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to-the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements-have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No.

DPR-27 is hereby amended to read as follows:

B.

Technical Specifications

'The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 156, are hereby incorporated in the license. The licensee shall operate the facility in accordar a with the Technical Specifications.

l 3.

This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: September 23, 1994

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ATTACHMENT TO LICENSE AMENDMENT N05.152 AND 156 TO FACILITY OPERATING LICENSE N05. DPR-24 AND OPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

EfMOVE INSERT TS 15.3.0-3 TS 15.3.0-3 TS 15.3.0-4 TS 15.3.0-4 TS 15.3.7-1 through TS 15.3.7-1 through TS 15.3.7-7 (7 pages)

TS 15.3.7-8 (8 pages)

Table 15.3.14-1 Table 15.3.14-1 TS 15.4.6-2 TS 15.4.6-2 l

Specification 15.3.0.C delineates additional conditions which must be satisfied to permit operation to continue, consistent with the Limiting Condition for Operation statements for power sources, whEn a normal or standby

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emergency power source is not operable.

It specifically prohibits operation when one system, subsystem, train, component or device is inoperable because its normal or standby emergency power source is inopr.rable and a redundant l

system, subsystem, train, component or device 15 ;noperable for another i

reason.

The provisions of this specification permit the action statements associated with individual systems, subsystems, trains, components, or devices to be consistent with the action statements of the associated electrical power

source, it allows operation to be governed by the time limits of the action statement associated with the Limiting Condition for Operation for the normal or standby emergency power source, not the individual action statements for i

each system, subsystem, train, component or device determined to be inoperable solely because of the inoperability of its normal or standby emergency pcwer j

source.

For example, Specifications 15.3.7.B.l.f, g, and h allow a 7 day out-of-t service time for the normal or standby emergency power source for the l

appropriate buses. If the definition of operable were applied without

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consideration of Specification 15.3.0.C., all systems, subsystems, trains, components or devices supplied by the inoperable normal or standby emergency i

power source vnuld also be inoperable. This would invoke the applicable action statements for each of the applicable LCO.

However, the provisions of l

Specification 15.3.0.C permit the time limits fer continued operation to be consistent with the statement for the inoperable normal or standby emergency l

power source instead, provided the other specified conditions are satisfied.

(

In this case, all redundant systems, subsystems, trains, components, and l

devices must be operable, or otherwise satisfy Specification 15.3.0.C (i.e.,

be capable of performing their design function and have at least one normal or one standby emergency power source operable).

If these conditions are not l

satisfied, shutdown is required in accordance with Specification 15.3.0.A.

i Unit 1 - Amendment No. 50, 152 15.3.0-3 Unit 2 - Amendment No. 56, 156 i

As a further example, Specification 15.3.7.A.I.c requires in parts that 4160-volt buses A03 and A04 be energized for the unit to be taken critical.

Specifications 15.3.7.B.I.f, g, and h permit the normal safeguard power source (either bus A03 or A04) to be taken out of service for up to seven days provided normal and standby emergency power to the other required buses are

~

operable and a diesel generator is operating and providing power to the engineered safeguard bus normally supplied by the out-of-service bus.

If the definition of operable were applied without consideration of Specification 15.3.0.C, all systems, subsystems, trains, components, and devices supplied by the inoperable normal power sources (i.e., the out-of-service bus A03 or A04) would also be inoperable.

This would invoke the applicable action statements for each of the applicable LCOs.

However, the provisions of this Specification 15.3.0.C permit the time limit for continued operation to be consistent with the action statement for the inoperable e.ormal power source, in this case seven days, provided the other specified conditions are l

satisfied. These conditions are that for the engineered safeguards systems on the other required buses the standby emergency power source must be operable (as must be the components supplied by the standby emergency power source) and all redundant systems, subsystems, trains, components and devices in the other engineered safeguards systems must be cperable, or likewise satisfy Specification 15.3.0.C (i.e., be capable of performing their design function and have an emergency power source operable).

In other words, the required standby emergency power sources ru be operable and all redundant systems, subsystems, trains, components an; w. ices in both divisions of engineered safeguards systems must also be operable.

If these conditions are not satisfied, shutdown is required in accordance with this specification.

In the cold shutdown and refueling shutdown conditions, Soecification 15.3.0.C is not applicable, and thus the individual action statements for each applicable LCO in these conditions must be adhered to.

Specification 15.3.0.D addresses the momentary loss of power to a component when immediate action is initiated resulting in reenergization from an alternate source, tripping the channel of logic or initiating operator action as specified in Table 15.3.5-2.

Such a situation does Unit 1 - Amendment No. 50,152 15.3.0-4 Unit 2 - Amendment No. 56,156

15.3.7 AUXILIARY ELECTRICAL SYSTEMS Applicability Applies to the availability of off-site and on-site electrical power for plant power operation and for the operation of plant auxiliaries.

Obiective To define those conditions of electrical power availability necessary (1) to provide for safe reactor operation, and (2) to provide for the continuing availability of engineered safeguards.

Specificatiort A.1 Under normal conditions neither one nor both reactors shall be made critical unless the following conditions are met:

a.

At least two 345 KV transmission lines are in servica.

b.

The 345/13.8 KV and the 13.8/4.16 KV station auxiliary transformers associated with the reactor (s) to be taken critical are in service; or one 345/13.8 KV station auxiliary transformer and the associated 13.8/4.16 KV station auxiliary transformer (s) are in service with the gas turbine operating.

c.

4160 Volt unit supply buses A03 and A04 for the unit to be taken critical are energized from their normal supply.

d.

Both units' A05/A06 bus tie-breakers are removed from their cubicles.

e.

Both units' B03/B04 bus tie-breakers are open with control power removed.

f.

A fuel supply of 11,000 gallons is available in each tank which is being relied upon to supply any operable emergency diesel generator (s).

g.

Four of the five safety-related statior, batteries and all four of the main DC distribution systems are operable.

h.

Four battery chargers are operable with one charger carrying the DC loads on each main DC distribution bus: D01, D02, D03 and D04.

i.

120 VAC Vital Instrument Buses Y01, Y02, YO3, YO4, Y101, Y102, Y103, and i

l Y104 for the unit (s) to be taken critical are energized from a safety-j related inverter.

j.

For both units to be made critical, the normal power supply and a standby emergency power supply to all the 4160/480 Volt safeguards buses shall be operable and the buses are energized from their normal supply.

Unit 1 - Amendment No. $/ g)W, 15.3.7-1 Unit 2 - Amendment No.

9 IM,

k.

For Unit I to be made critical, the normal power supply and a standby emergency power supply to the 4160/480 Volt safeguards buses Unit 1 A05/B03, Unit 1 A06/B04, and Unit 2 A06/B04 shall be operable and the buses are energized from their normal supply.

1.

For Unit 2 to be made critical, the normal power supply and a standby emergency power supply to the 4160/480 Volt safeguards buses Unit 2 A05/B03, Unit 2 A06/B04, and Unit 1 A05/B03 shall be operable and the buses are energized from their normal supply.

B.1 During power operation of one or both reactors, the requirements of 15.3.7. A.1 may be modified to allow the following arrangements of systems and components:

a.

If the 345 KV lines are reduced to only one, any operating reactor (s) must be promptly reduced to, and limited to, 50% power.

If all 345 KV lines are lost, any operating reactor (s) will be reduced to supplying its auxiliary load, until one or more 345 KV transmission lines are again available.

b.

If both 345/13.8 KV auxiliary transformers are out of service and only the gas turbine is operating, only one reactor will remain operating and it will be limited to 50% power.

The second reactor will be placed in the hot shutdown condition.

c.

If the 13.8/4.16 KV auxiliary transformers are reduced to only one, the reactor associated with the out of service transformer must be placed in the hot shutdown condition.

d.

With a unit in cold or refueling shutdown or defueled, one pair of buses, l

A05 and A06 or B03 and B04, for that shutdown unit, may be tied together through their common tie breaker for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the required redundant decay heat removal in the shutdown unit and the required redundant shared engineered safety features for the other unit are operable.

If the tie breaker cannot be opened or the conditions of 15.3.7.B.I.e met within 8 hcurs, the operating unit shall be placed in the hot shut-down condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

e.

With a unit defueled, one pair of buses for the defueled unit, A05 and

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A06 or 803 and B04, may be tied together through their common tie-breaker in excess of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided:

1) An evaluation is performed to show that the loads that remain or can be energized by the buses will not cause a potential overload of the Unit 1 - Amendment No.

8

?g 15.3.7-2 Unit 2 - Amendment No. # IN W,

Id,156

associated diesel generator. The applicable Limiting Conditions for

'l Operation of the equipment removed from service shall be entered for-the operating unit.

2) A single train of spent fuel cooling is adequate to cool the spent fuel pool.

2

3) The required redundant shared engineered safety features for the other unit are operable.

f.

The normal power supply or standby emergency power supply to Unit 1 A05/B03 or Unit 2 A06/B04 may be out-of-service for a period not exceeding 7 days provided the required redundant engineered safety features are operable and the required redundant standby emergency power supplies are started within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> befors or after entry into this LCO and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter. If the normal power supply is out-of-service, an operable emergency diesel generator is supplying the affected 4160/480 Volt buses. After 7 days, both units will be placed in' hot 1

shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

g.

The normal power supply or standby emergency power supply to Unit I

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A06/B04 or Unit 2 A05/B03 or both may be out-of-service for a period not

-l exceeding 7 days provided the required redundant engineered safety

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teatures are operable and the required redundant standby emergency power supplies are started within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before or after entry into this LC0 and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter.

If the normal power supply is out-of-service, an operable emergency diesel generator is supplying the affected 4160/480 Volt buses.

After 7 days, the affected unit or units will be placed in hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

h.

The normal power supply or standby emergency power supply to Unit 1 l

A05/B03 and Unit 2 A05/B03, or Unit 1 A06/B04 and Unit 2 A06/B04 may be j

out-of-service for a period not exceeding 7 days provided the required redundant engineered safety features are operable and the require'd redundant standby emergency power supplies are started within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before or after entry into this LC0 and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter.

If the normal power supply is out-of-service, an operable emergency diesel i

i j

Unit 1 - Amendment No.

I g 15.3.7-3 Unit 2 - Amendment Nc. M. 92. IM, 10,152,156

=.

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generator is supplying the affected 4160/480 Volt buses. After 7 days, both units will be placed in hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

1.

One of the four connected safety-related station batteries may be l

inoperable for a period not exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided four battery chargers remain operable with one charger carrying the DC loads of each main DC distribution bus.

j.

If an operating safety-related inverter is rendered inoperable and the l

associated loads transfer to a non-safety-related power source, the loads shall be transferred back to an operable safety-related inverter within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in hot shutdown within an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> of inverter inoperability.

k.

If any safeguards bus is deenergized, the applicable LCOs will be entered for the affected equipment.

Easis This two unit plant has four 345 KV transmission line interconnections.

A 20 MW gas turbine generator, two original and two additional diesel generators are l

installed at the plant. All of these energy sources will be utilized to provide depth and reliability of service to the Engineered Safeguards equipment through redundant station auxiliary power supply systems.

The electrical system equipment is arranged so that no single contingency can inactivate enough safeguards equipment to jeopardize the plant safety.

The 480-volt equipment is arranged on 4 buses per unit. The 4160-volt equipment is supplied from 6 buses per unit.

Two separate outside sources can serve either unit's low voltage station auxiliary transformer.

One is a direct feed from the unit's high voltage station auxiliary transformer and the second is from the other unit's high voltage station auxiliary transformer or the gas turbine via the 13,800 volt l

sys. tem tie bus H01. The normal power supplies for the A05 and A06 buses are the A03 and A04 buses, respectively.

i Separation is maintained in the 4160-volt system to allow the plant auxiliary equipment to be arranged electrically so that redundant items receive their l

power from the two different buses.

For example, the safety injection pumps are supplied from the 4160 volt buses 1-A05 and 1-A06 for Unit No. I and 2-A05 Unit 1-AmendmentNo.g8gm 15.3.7-4 Unit 2 - Amendment No.

g na,

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.and 2-A06 for Unit No. 2; the six service water pumps arn arranged on 480-volt

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buses as follows:

two on bus 1-B03, one on bus 1-804, one on bus 2-B03 and two on bus 2-B04; the four containment fans are divided between 480-volt buses 1-803 and 1-804 for Unit No. I and 2-803 and 2-B04 for Unit No. 2 and so forth.

Redur. dant valves are supplied from motor control centers 1-832 and 1-842 for Unit No. I and 2-B32 and 2-842 for Unit No. 2.

The specifications for the 480 volt safeguards buses, B03 and B04, and the 4160 volt safeguards buses, A05 and A06, direct an independent lineup of power distribution, specifically stating that a normal lineup must be achieved (all safeguards buses associated with a unit are powered through their normal supply breaker with all safeguards bus tie-breakers open) prior to taking a unit critical and during subsequent power operation.

Operability of the safeguards buses is based on maintaining at least one train of on-site emergency power l

operable during accident conditions coincident with an assumed loss of offsite power and a single failure in the other train of on-site emergency power.

l This includes a failure of a tie-breaker to trip, which under certain conditions could result in an overload and a loss of the associated diesel generator.

The LCOs permit abnormal electrical distribution lineups for periods of time in order l

to facilitate such items as maintenance of normal supply breakers or transformers.

In such cases, bus independence may be relaxed under the conditions specified in the LCO.

Extended use of safeguards bus tie-breakers is allowed under specified, controlled conditions.

For example, when a unit is fully defueled, safeguards and safe shutdown systems and equipment dedicated to that unit are not required.

However, spent fuel pool cooling must be maintained.

By limiting the loads supplied by the cross-connected buses, the potential for loss of a diesel generator due to overloading caused by the failure of a tie-breaker to open is minimized. Operability of shared safeguards systems such as auxiliary feedwater and service water must be maintained as required by their applicable LCOs.

The bus tie-breaker specifications have provisions that the required redundant decay heat removal for the shutdown unit and the required redundant shared

)

engineered safety features for the other unit are operable.

The specification that applies only to the defueled condition does not have the provision for the l

required redundant decay heat removal for the shutdown unit.

It has provision Unit 1 - Amendment No. g E Q ? Q 15.3.7-5 Unit 2 - Amendment No, g 9g?g

for verifying the adequacy of a single train of spent fuel pool cooling in lieu of the consideration of decay heat removal for a reactor in cold shutdown.

The Point Beach DC electrical system has been modified so that each of the four main DC distribution buses, which are shared between the two units, has its own power supplies consisting of a safety-related station battery (DOS, 006, D105, D106) and a battery charger.

In addition to these bus-specific power supplies, a swing safety-related battery (D305) is installed which is capable of being connected to any one of the four main DC distribution buses.

Swing battery chargers are also provided. Under normal circumstances, one battery and one battery charger are connected in each main DC distribution bus.

The battery charger normally shall be in service on each battery so that the batteries will always be at full charge in anticipation of a loss-of-AC power incident.

Under unusual circumstances, two of the five safety-related batteries may be out of service for a limited period of time provided one of the two out-of-service batteries is returned to service within the time periods specified in Specification 15.3.7.B.l.i.

These limiting conditions for operation ensure that l

adequate DC power will always be available for starting the emergency generators and other emergency uses.

The emergency diesel generators are the sources of standby cmergency power.

The l

support systems necessary to be operable to ensure the operability of the emergency diesel generators (EDGs) are the EDG starting air system, EDG fuel oil system, EDG ventilation system, and EDG DC control power.

The standby emergency power supply for a 4160 Volt and associated 480 Volt safeguards bus consists of an operable EDG, including all required support systems, and an operable output breaker to that 4160 Volt safeguards bus.

The LCOs for the standby emergency power supplies require the redundant standby emergency power supplies to be started within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entry into these LCOs.

If the standby emergency power supply LC0 is exited within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, then starting of the redundant standby emergency power supplies is not required.

If the LC0 was entered due to a standby emergency power supply failure and the LCO was exited within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, then an evaluation must be completed as soon as possible within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entry into the LC0 to show that the redundant standby power supplies are not susceptible to that failure by common cause or the l

15.3.7-6 Unit 1-AmendmentNo.gfgug Unit 2 - Amendment No. M, N,IM, W.

IM,156

redundant standby emergency power supplies must be started to prove that failure by common cause does not exist within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entry into the LCO.

The EDG starting air system is considered operable when 1) all starting air

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bottles in each bank are operable, 2) the starting air banks can be maintained at a minimum pressure of 165 psig, 3) the air bank crossconnect valve is shut unless bank pressures are being equalized and an operator is stationed at the valve during pressure equalization, and 4) all four starting air motors and their associated valves and relays are operable.

The EDG fuel oil system is considered operable when 1) 11,000 gal. of fuel oil is initially available in the fuel oil storage tank which supplies the diesel l

generators [Because the EDGs consume approximately 205 gallons of fuel per hour when fully loaded, the 11,000 gallon fuel supply in the emergency fuel tank provides sufficient fuel to operate one EDG at design load for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.], 2) the EDG day tank for that EDG is operable and for G-01 and G-02 the l

associated motor-operated fill valve is operable, 3) for G-01 and G-02, at least 1

one of the two base-mounted sump tank fuel oil transfer pumps is operable, and 4) the fuel oil transfer system associated with the EDG is operable.

However, the fuel oil transfer system is allowed to be out-of-service for four hours for G01 and G-02 due to a combined four-hour supply of fuel oil in the diesel base and day tanks which do not reauire a fuel oil transfer pump for flow to the associated rDG.

The fuel oil transfer system is allowed to be out-of-service for two hours for G-03 and G-04 due to a two-hour supply of fuel oil in the day tank.

The transfer system may be out of service for longer periods if an appropriate alternate source of fuel is made available to the diesel generators.

The EDG vent llation system is considered operable when diesel room temperature can be maintained $120'F with the diesel engine operating at full load.

Temperature will be maintained s120 *F if 1) all gravity-operated louvers are operable, and 2) both diesel room exhaust fans are operable QB for G-01 and G-02; l

one diesel room exhaust fan is operable and outside air temperature is $80*F.

Normal DC control power must energize all DC circuits for the associated EDG to be operable.

l Unit 1 - Amendment No. 74,152 15.3.7-7 Unit 2 - Amendment No. 152,156

.The original AEC Safety Evaluation for PBNP states, "Onsite fuel storage capacity is sufficient for a minimum of seven days' caeration of the required safety feature loads which is acceptabic." Therefore, to satisfy this requirement, at least 34,500 gallons of fuel cil will be maintained available for the emergency diesel generators at Point Beach at all times when EDG operability is required.

If only one 345 KV transmission line is in service to the plant switchyard, a temporary loss of this line would result in a reactor trip (s) if the reactor (s) power level were greater than 50%.

Therefore, in order to maintain continuity of service and the possibility of self sustaining operations, if only one 345 KV transmission line is in service to any operating reactor (s), the power level of the affected reactor (s) will be limited to 50%.

If both 345/13.8 KV station auxiliary transformers are out of service, only one reactor will be operated.

The gas turbine will be supplying power to operate safeguards auxiliaries of the operating reactor and acts as a backup supply for the unit's normal auxiliaries.

Therefore, to prevent overloading the gas turbine in the event of a reactor trip, the maximum power level for the operating reactor will be limited to 10J.

These conservative limits are set to improve transmission sp tem reliability only and are not dictated by safety system requirements.

References FSAR Section 8.

Unit 1 - Amendment No.152 15.3.7-8 Unit 2 - Amendment No.1S

TABLE 15.3.14-1 SAFE SHUTDOWN AREA FIRE PROTECTION AUTCMATIC SUPPRESSION MANUAL SUPPRESSION WATER GAS SPRIWLER SUPPRESSION FIRE MOSE FIRE AREA ELEVATION SYSTEM SYSTEM STATION DETECTION 1.

Auxiliary Building South 8'

(x) Partial x

15 x

13 2.

Auxiliary ""itding Center A.

Safe *e ejection Pumps 8'

x B.

Cori et Cooling Water Purp X

3.

Auxiliary Building North 8'

(x) Partist X

9 4

Auxiliary Building West 8' & Below x

16 5.

Auxitiary Butiding South 26' x

3 6.

Auxiliary Building Center 26' x

17 7.

Auxiliary Building North 26' x

7 8.

Auxiliary Buitding Center 46' x

6 9.

Auxiliary Feedwater Ptro Room 8'

x x

11 10.

Vital Switchgear & Battery Room 8'

x x

8 11.

G01 Dieset Generator Room 8'

x x

4

12. G02 Diesel Generator Room 8'

x x

4

13. Cable Spreading Room 26' x

x 17 4

x 15 14 Circulating Water Pt:5 cuse A.

Service Water Pures 8'

X 15.

G03 Diesel Generator Room 28' x

M*

3 16.

G04 Dieset Generator Room 28' x

x*

3

17. G03 Vital Switchgear Room 28' x*

2 18.

G04 vitat Switchgear Room 28' x*

2 19.

G03 Fuel oft Day Tank Room 28' x

M*

1

20. G04 Fuet all Day Tank Room 28' x

M*

1

• Diesel Generator Building fire hose stations are located in Mechanical Equipnent Room.

Unit 1 - Amendment No. 118,152 Unit 2 - Amendment No. 121,156

~..-

T 3.

The proper operation of Emergency Lighting, including the automatic transfer switch for DC lights, will be demonstrated during each reactor shutdown for a major fuel reloading.

4.

Each diesel generator shall be given inspections following the manufacturer's recommendations for this class of stand-by service.

5.

Operability of the diesel fuel oil system shall be verified monthly.

6.

A diesel fuel oil testing program shall be maintained to test both new fuel oil upon receipt and fuel oil stored in the fuel oil storage tanks which supply the emergency diesel generators on a quarterly frequency in accordance with applicable ASTM standards.

The above tests will be considered satisfactory if all applicable equipment operates as designed.

B.

Safety-Related Station Batteries These surveillance specifications are applicable to alt four safety-related station batteries: DOS, D06, DIOS, and D106; and the safety-related station swing battery D305.

1.

Every month the voltage of each cell (to the nearest 0.05 volt), the specific gravity and temperature of a pilot cell in each battery and each battery voltage shall be measured and recorded.

2.

Every 3 months the specific gravity, the height of electrolyte, and the amount of water added, for each cell, and the temperature of every fifth cell, shall be measured and recorded.

3.

At each time data is recorded, new data shall be compared with old to detect signs of abuse or deterioration.

4.

Each Safety-Related Station Battery shall be demonstrated OPERABLE:

a.

At least once per 18 months (SERVICE TEST) by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status all of the actual or simulated emergency loads for the design duty cycle.

b.

At least once per 60 months (PERFORMANCE TEST) by verifying that the

]

battery capacity is at least 80% of the manufacturer's rating. This performance discharge test may be performed in lieu of the battery service test.

Unit 1-AmendmentNo.(7tg}IA 15.4.6-2 Unit 2 - Amendment No. 2 h3 39 1A1, 145,132,1$6 i

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