L-79-280, Forwards Fire Protection Info Re Preliminary Schedule Mod, Fire Pump Controller Evaluation & Cable Area Evaluation in Response to NRC

Forwards Fire Protection Info Re Preliminary Schedule Mod, Fire Pump Controller Evaluation & Cable Area Evaluation in Response to NRC

ML17207A453
Person / Time
Site:	Saint Lucie
Issue date:	10/03/1979
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Reid R Office of Nuclear Reactor Regulation
References
L-79-280, NUDOCS 7910100095
Download: ML17207A453 (33)

Text

I REGULATORY FORMATION DISTRIBUTION SY M (RIDS)

ACCESSION NBR:7910100095 DOC,OATEN'9/10/03 NOTARIZED:

NO FACIL:50-335 St, Lucie Plant<

Unit ii Florida Power 8

l ight Co.

AUTH,NAME AUTHOR AFFILIATION UHRIGiR ~ ED Florida Power E Light Co.

REC IP ~ NAME RECIPIENT AFFILIATION REIDE R ~ N ~

Operating Reactors Branch DOCKET 05000335

SUBJECT:

For wards fire protection info re preliminary fire pump controller evaluation 8, cable area response to NRC 790S17 ltd DISTRIBUTION CODE:

A0060 COPIES RECEIVED:LTR PENCL TITLE: Fire Protection Information (After schedule modi evaluation in SIZE!

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BOX 629100, MIAMI,FL 33162 ygllgg~

tv~~uwX FLORIDA POWER 4 LIGHTCOMPANY October 3, 1979 L-79-280 Office of Nuclear Reactor Regulation Attention:

Mr. R.

W. Reid, Chief Operating Reactors Branch ¹4 Division of Operating Reactors U.

S. Nuclear Regulatory Commission Washington, D.

C.

20555

Dear Mr. Reid:

Re:

St. Lucie Unit 1

Docket No. 50-335 Fire Protection The following information is submitted in response to your letter of August 17, 1979, which forwarded Amendment 33 to Facility Operating License DPR-67:

Attachment A - Preliminary Modification Schedule Attachment B - Fire Pump Controller Evaluation Attachment C - Cable Area Evaluation Please refer to FPL letter L-79-235 of August 24, 1979 for a discussion of ventilation system design.

This letter contains information responsive to your request for an evaluation of duct penetrations of barriers enclosing safety related systems.

Very truly yours, Robert E. Uhrig Vice President Advanced Systems 5 Technology REU/MAS/cph Attachments cc:

Mr. James P. O'Reilly, Region II Harold Reis, Esquire

~ g~0y 008 9 PEOPLE... SERVING PEOPLE

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ATTACHMENT A PRELIMINARYB.MODIFICATION SCHEDULE ST..LUCIE UNIT 1

FIRE PROTECTION Item 3.1

~Fi Engineering NRC Design Submittal

~d FPL's NRC Proposed Approval Implementation

~di dd 3.1.1 3.1. 2 3.1. 3 3.1.4 April 1980 Dec.

1979 Jan.

1980 Feb.

1980 Completed Completed

Oct, 1980 Oct.

1980 3.2 Fire Protection Water Pi in S stem 3.2.1 3.2.2 3.2.3 3.2.4 3.2.5 April 1980 Dec.

1979 Completed,

Oct, 1980

'Dec.

1979 Completed

'.5

'.6 Air Breathing Equipment Fire Door Evaluation 3.7 Ventilation Duct Penetrations 3.8 Control Room 3.8.1 3.8.2 3.8.3 3.8.4 3.8. 5

3. 3 Foam Equi,pment 3.4 Portable Smoke Ejectors Jan.

1980

Dec, 1979 Dec.

1979 Completed Dec.

1979

• • Completed

• • Completed Completed Dec.

1979 Oct.

1980 Oct.

1980

• • Completed

3. 3

~ddi 3

di Room March 1980 April 1980 May 1980 Dec.

1981

Item 3.10

• Switch ear Rooms 3.10.1 3.10. 2 1.11'B Ventilation Engineering Design Com letion Date Jan.

1980 NRC Submittal Date

• FPL's NRC Proposed Approval Implementation

~Ri BB 1

Completed Completed Oct.

1980 3.12 Reactor Auxiliar

~B'Id 3.12.1 3.12. 2 3.12. 3 3.12. 4 3.12. 5 3.12.6 3.12. 7 3.12.8 3.12.9 April 1980 Feb.

1980 Feb.

1980 March 1980 April 1980 Completed Completed Completed Dec.

1979 Oct.

1980 Completed Oct.

1980 Oct.

1980 Dec.

1979 3.13 Reactor Bldg 3.13.1

3. 1'3. 2 3.13. 3 April 1980 May 1980 Completed Dec.

1981 June 1980 July 1980 Dec.

1981 3.14 Diesel Generator Bld.

and Fuel Oil Stora e

Tanks 3.14.1 3.14. 2 3.14. 3

3. 14. 4 3.14. 5 3.14. 6 April 1980 April 1980 May 1980 April 1980 April 1980 May 1980 June 1980 Completed Oct.

1980 Oct.

1980 Oct.

1980 Dec.

1981 Oct.

1980 3.'15 Yard Area Oct.

1980

• Refer to items marked with an asterisk in Section 3.0 (copy attached) of the NRC Safety Evaluation for Amendment 33 to the St. Lucie Unit 1 Operating License.

• • Refer to FPL letter L-79-235 dated August 24, 1979.

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Please note that there are four December, 1981 dates on the preliminary schedule.

Due to the large scope of these

items, our limited resources in light of other regulatory requirements, and procurement considerations, we are unable to schedule the necessary design effort to support the Spring-1980 refueling.

Since St.

Lucie Unit 1, Cycle 4

is tentatively planned as an 18-month cycle, the Fall-1981 refueling becomes the next available outage during which the fire protection modifications can be completed..

This is the basis for the December,'981 schedule dates.

3.0

SUMMARY

OF MODIFICATIONS The licensee plans to make certain plant modifications to improve the fire protection program as.a result of both his and the staff's evaluations.

The proposed modifications are summarized below.

The sections of this report, which discuss the modifications are

'oted in parenthesis following each item.

The licensee vill provide a schedule for all mocb.ficationc.

Certain items listed below are marked with an asterisk (*) to indicate that the NRC staff will require additional information in the form of design details, test results, or acceptance criteria to assure that the design is acceptable prior to implementation of these modifications.

The balance of other modifications has been described in an acceptable level of detail.

Guard Posts (4.3.1.2)

Guard posts vill be provided to protect the fire pumps and ancillary equipment from vehicular damage.

Yalve Position Identification (4.3.1.2)

Heans will be provided for visual indication of the position of the, valves controlling flow from the fire pumps.

Fire Suction Pi in (4.3.1.1)(4.3.$.2)

Capability will be provided to permit the fire pumps to take suction from either of the water storage tanks.

rade Existin Fire P s (4.3.1.2)

The existing fire pump installation vill be upgraded as follows:

(1)

The existing two electric motor driven pumps will be modified to be capable to automatically operate upon loss of offsite power.and to start upon drop of pressure in the distribution system; except under engineered safety features actuation signal (ESFAS) conditions.

(2)

A pressure switch arranged to start pump upon drop of pressure in the fire protection water system will be provided near the discharge piping from each fire pump.

3-1

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(3)

The stop devices for the fire pumps located in the control room will be removed..

3.2 Fire Protection Hater Pi in S stem (4.3.1.3) 3.2.1 drant and PIV Guard Posts (4.3.1.3)

Guard posts will be provided to protect hydrant and control valve indicator posts which are subject to vehicular damage.

3.2.2 H drant Protection {4.3.1.3)

A means will be provided to protect the fire hydrant located in the construction area for Unit 2 from mechanical damage.

3.2.3 Isolation Valves (4.3.1.3) 3.2.4

.3.2.5 A post indicator valve will be provided between fire hydrants 9

and 10 to preclude the potential that shutting a portion of the fire loop to service a hydrant willnot result in depriving fire water to safety-related areas.

Additional H drant (4.3.1.3)(5.14.6)

A charged 2-1/2-inch hose outlet will be provided at the security wall between the auxiliary building and diesel generator building until such time as the security wall has been removed.

H drant Hose Valves (4.3.1.3)

A 2 1/2-inch gated hydrant hose valve gill be provided in each

'ose house.

3.3 Foam E ui ment. (4.3.1.6)(5.14.5) 3.4 Two portable foam eductors sized for connection to 1 1/2-inch fixe hose and at least SO gallons of foam concentrate will be provided.

Portable Smoke E ectoxs (4.4.1) 3.5 Two fire service portable smoke ejector's of the explosion proof type with a capacity of 5000 cfm oi greater will be provided for fire brigade use.

Air Sreathin E ui ment {4.4.3)

A cascade type system to xefill air breathing cylinders will be provided.

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+3.6 Fire Door Evaluation (4.9.1)

+3 7 An ev'aluation will be made of the fire rating of all doors in barriers separating fire areas and fire zones.

Based on this study, existing doors in fire barriers vill be upgraded where necessary to meet the fire rating of the barrier or the highest fire loading on either side of the barrier.'entilation Duct Penetrations (4.9.2) 3.8 The ventilation duct penetrations of barriers enclosing safety related systems are to be"reevaluated.

Iire or smoke dampers will be provided at locations where the evaluation shows that potential effects due to an unmitigated fire could affect safe shutdown.

Control Room (5.1) 3.8.1 Fire Extin uisher (4.3.3)(5.1.6)

Two 2 1/2 gallon pressurized water fire extinguishers will be provided for the control room.

3.8.2 Records Stora e (5.1.6)

The drawings and records within the control room will be stored in enclosed metal cabinets which will be located away from safety related equipment.

3.8.3 Smoke Detectors

.(4.2) (5.1.6) 3.8.4 Automatic smoke detectors will be provided within the standup control panels (RTG 'Boards) in the control room.

Fire Door (4.9.1)(5.1.6)(5.6:6) 3.8.5 A 'one hour fire rated self closing door will be provided at the entrance to the corridor serving the kitchen/office area.

. P~D (5..6)t5.6.6)

FPL wL11 provide an evaluation of the need for fire rated dampers in the duct I area between the control room and the mechanical equipment room.

3-3

~*3 9 Cable S readin Room "Fire Barrier (4.11){5.2.6){5.3->)

3.10 3.10.1 A 1-1/2-hour rated fire barrier will be provided for the wall opening separating the cable spreading zoom from the "Train B) switchgear room.

Switch ear,Rooms (43 Foot Elevation) (5.3)

Stora e Cabinets (5.3.6)

Enclosed metal cabinets will be provided for the storage of com-bustible records in the "Train B" switchgear room.

3.10.2 Pol rethane Pi e Insulation {5.3.6) 3.11 The polyurethane insulation on the piping in the switchgear room will be covered with a fire retardant material.

Batte Room Ventilation (5.5.6)

The weighted damper in the exhaust duct of each battery room will

<be -removed to help eliminate the possibility of hydrogen accumula-tions within the rooms.

3.12 Reactor Auxilia Buildin 3.12.1 Fire Door Re airs {4.9.1)(5.6.6) 3.12.2 3.12.3 3.12.4 The ordinary glass windows in the stairway fire doors will be replaced with wire glass or fire rated doors will be provided.

Ladders to Cable Tra Areas (4.12)(5.8.6)

Fixed ladders for access to the cable trays in the areas above

'Fire 'Zones 43 and 44 will be provided.

Pol rethane Pi e Insulation {5.6.6)

The polyurethane insulation on the piping in the control room mechanical equipment room {Fire Zone 71) will be covered with a fire retardant material.

I Cable Loft Conduit (5.8.6)

The conduit in the cable loft above Fire Zones 43, 44 and 54 will be pXugged with an approved fire retardant material where cables enter the open end of the conduit.

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3.12-5 3.12.6 Iaund

/Decontamination Area Fire Door (4.9.1)(5.8.6).

A 1"1/2-hour fire rated door and frame will be provided for the wall opening between laundry/decontamination area (Fire Zone 43) and the corridor (Fire Zone 55).

Flammable Gas Pi in Identification (5.8.6)

The flammable gas supply piping within the reactor auxiliary'uilding will be identified by color coding or lettered. markers.

• 3.12.-7 Smoke Detectors (4.2)(5.8.6)(5.9.6)

Automatic smoke detectors connected to the fire alarm system in the control room will be provided for the following areas:

(1)

Iow pressure safety injection pumps (2)

High pressure safety injection pumps (3)

Containment spray pumps 3.12.8 Drummin Station Fire Barrier (4.9.1) (5.8.6)

A three-hour fire rated door end frame will be provided in the wall separating the drumming station (Fire Zone 51) from the corridor (Fire Zone 55).

3.12.9 Anti-C Clothin Dis osal Containers (5.9.6)

I The anti-C protective clothing disposaI containers in the corridor of the auxiliary building (Fire Zone 36) will be provided with covers.

3.13 Reactor Buildin (5.11) 3.13.1 Tool Iockers (5.11.6) 3.13.2 Hetal tool lockers will be provided within the containment for the storage of combustible materials left inside the containment building.

Reactor Coolant P

Fire Detectors (4.2)(5.11.6)

Automatic fire detectors connected to the alarm system'n the control room will be provided above each reactor coolant pump.

3>>5

+3s13.3 3.14 Reactor Coolant'ump Oil Collection S stem (5.11.6)

Action on the provision of an oil collection system foz the reactor coolant pumps has been deferred pending final resolution of an EPRX study, "Evaluation and Test of Improved Fire Resistant Fluid Lubricants foz Mater Reactor

Coolant, Pump Hotors.

Xf a suitable lubricant is not found, a fire suppression system or a suitable oil collection system will be provided.

Diesel Generator Buildin and Fuel Oil Stora e Tanks {5.14) 3.1 4.

1 Curbs (5.14.6)

'.14.2 Curbs will be provided at the doorway between the two generators rooms and at the manholes adjacent to the diesel generator building to prevent migrating oil from entering these areas.

Fire Door (4.9.1)(5.14.6)

The dooz opening between the diesel generator rooms will be provided th a three hour fire rated door.

w3.

3.14.3 Oil Vent Lines (5.14.6)

The vent lines for the diesel generator skid tanks will be relocated to vent outside the diesel generator rooms.

3.14.4 Earl Marnin Detectors (5.14.6)

A portion. of the existing fire detector in each diesel generator room will be replaced with early warning type detectors.

-3.14.5 Automatic S rinkler S stem (4.3.1.5)(5.14.6)

An automatic fire suppression system will be provided in each diesel generator room.

Tank Dikes (5.14.6)

The pipe holes in the dike surrounding the diesel fuel oil storage tanks adjacent to the diesel generator building will be sealed to insure that, in the event of a tank rupture, the contents of the fuel tanks will be contained within the diked area.

Yard Area (5.13.6) {5.15.6)

(1)

Curbs will'e provided for manholes in the yard area con-taining shutdown related cables which would be affected by migrating oil.

{2)

Curbs will also be.provided between the circulating water pumps and intake water pumps at the service water intake structure to prevent oil, in the event of a circulating water pump oil release, from endangering the intake water pumps which are required for safe shutdown.

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1 ATTACHMENT B Fire Pum Controller Evaluation h

.A detailed analysis has been performed of NFPA-20 (1978) requirements for fire pump electric drive controllers versus the existing system at St. Lucie Unit l.

A comparison.matrix is attached.

Me have concluded that the existing system is preferable to the sys'em required by a strict interpretation of NFPA-20 because the existing system was desi gned and purchased under the philosophy developed for nuclear safety related systems

.and equipment.

The potential for system degradation exists if a strict int'erpretation of NFPA-20, rather than the intent of NFPA-20, is applied to our installation.

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Comparison between NFPA-20 1978 requirements foW Fire Pump Electric Drive Controllers and PSL-1 Existing System NFPA-,20 Requirements PSL-1 Existing System Please note the following:

"1-8 Definitions.

1-8,1 Controllers.

1-8.1.1 Controller means the cabinet, motor starter, circuit breaker and disconnect switch, and other control devices for the control of electric motors and internal combustion engine driven pumps.

1-8.1.2 Isolating t<eans is a switch intended for isolating an electric circuit from its source of power.

1-8.1.3 Disconnecting Means is a device, group of devices, or other means (such as a circuit breaker or disconnecting switches) whereby the conductors of a circuit can be disconnected from their source of supply."

"1-5 Unit Purchase.

1-5. 1 The pump, driver, and controller shall be purchased under unit contract stipulating compliance with this standard and satisfactory performance of the entire unit when installed."

As is standard with all plant controll'ers, including controllers, the controllers were purchased separate from the pumps and drivers.

The fire pump controllers were purchased to nuclear grade Class IE control requirements.'he testing and quality control requirements for Class IE equipment are much mor' stringent than NFPA-20 requirements.

NFPA-20 Requirements 7-1.1 General..

"7-1.1.1 All controll ers shall be specifically listed for electric motor driven fire pump servi ce. "

PSL-1 Existing System Since the controllers for both fire pumps were purchased to nuclear grade Class IE requirements the equipment is certainly acceptable for fire pump service.

(a)

Any controller selected shall have a short circui,t. rating at least equal to the available short circuit current for the circuit in which it is used.

(b)

Short circuit current at the controller shall be determined by using Table 7-4.2.9 when the installation meets the criteria established in the notes to the table.

Otherwise a short circuit study must be made to establish the available short-circuit current at the controller in accordance with IEEE 141, Electric Power Distribution for Industrial Plants or IEEE 241, Electric Systems for Commercial Buildings.

(See Appendix C.)

Please note that Table 7-4.2.9 does not exist.

Using Table 7-4.2.10, the recommended circuit breaks interrupting rating is 22,000 amperes symmetrical based on a 1500KYA transformer at a secondary voltage of 480 volts.

The existing circuit breaker meets these requirements.

7-1.1.2 All controllers shall be completely assembled,

.wired, and tested by the manufacturer before shipment from the factory.

Because the. circuit breakers are a part of the nuclear grade Class IE load centers, the breakers were purchased, manufactured and tested to Class IE quality assurance requirements.

There-

fore, we believe a better product was obtained t than if purchased as industrial grade.

7-2

Location,

• 7-2.1 Controllers shall be located as close as is practical to the motors they control and shall

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be within sight of the motors.

7-2.2 Controllers shall be so located or so protected that they will not be injured by water escaping from pumps or pump connections.

Current carrying parts of controllers shall be not less than 12 inches (305 mm) above the floor level.

The fire pumps'ircuit breakers and control circuAry are located in the Reactor Auxiliary Building (RAB), a reinforced concrete structure, and are a part of safety-related load centers which meet 7-2.2.

To ensure the integrity and protection of the power supply, it is located in the

RAB, The fire pumps are located adjacent to their water supply for obvious reasons.

Therefore, it is not feasible to meet 7-2.1.

However

.g.

local control station wit/ start/stop capa6iiities for each pump exists at tne pump.

HFPA-20 Requirements 7-3 Construction PSL'1-. Existing System..

7-3.1 Equipmenl.

All equipment shall be suitable for use in locations subject to a moderate degree of moisture such as a

damp basement.

7-3.2 f1ounting.

All equipment shall be mounted in a substantial manner on a single noncombustible supporting structure.

7-3.3 Enclosure.

The structure or panel shall be, securely mounted in an enlosure(s) vIhich will protect the equipment against mechanical,.injury and falling drops of water striking the enclosure from the downward vertical, As previously stated, the circuit breakers and control circuitry are located in a reinforced concrete building which precludes a

"damp basement" and "falling drops of water."

The above are in a seismically qualified steel cabinet which is attached to the concrete floor.

7-3.4.3 Bus bars and other wiring elements of the controller shall be designed on a continuous duty basis.

Equipment meets these requirements as a minimum.

7-3e5 Protection of Auxiliary Circuits.

Circuits which are depended upon for proper operation of 'the controller shall oot have overcurrent protective devices connected in them.

Circuitry must be protected against overcurrent to prevent damage and the possibility of fire.

If power is lost to the pump, the control room is -immediately notified by bus undervoltage relays.

Control power is not required to maintain operation of the pumps.

However, if control powe'r is lost, the breakers have the capability of being manually closed or tripped.

Due to the total separation (electrical and physical) loss of one pump due to actuation of overcurrent devices will not affect operability of the other pump.

Since HFPA-20 does not require redundant pumps or any continuous manning of facilities an argument does exist fo'r running the only pump to destruction in the hope that the fire will be put out before pump

failure, This is not true for a redundant pump installation.

Additionally, removal of over current protection from the fire pumps would require they be removed from the emergency (diesel generator supplied) busses due to nuclear safety concerns.

This would eliminate the fire water system in the event of a loss of off site power

NFPA-20 Requirements 7-3.6.External Operation.

All switching equipment for manual use in connecting or disconnecting, or starting or stopping the motor shall he externally operable as defined in NFPA 70, National. Electric Code (see Appendix C).

PSL-1 Existing System The circuit breakers can be manually operated externally to the cubicle.

7-3,7 Wiring Diagrams and Instructions.

7-3.7.1 A wiring diagram shall be provided and perma-nently attached to the inside of the controller enclosure.

7-3.7.2 All the field wiring terminals shall be plainly marked to correspond with the wiring diagram furnished.

-A wiring diagram is not provided inside the controller enclosure.

If wiring'evisions are necessary, plant personnel experienced with this equipment have necessary drawings available.

All terminals and cables (except for manufacturer's cables) are plainly marked.

It should be noted that both operations and maintenance activities at a nuclear plant, on equipment powered from safety related (Class IE) busses, is quite

-,strictly controlled by the existing NRC mandated gC/gA program:

This is not true for most of the:

facilities covered by NFPA-20.

7-3.8

Marking, Each motor control device and ea,ch switch and circuit breaker shall be marked to plainly indicate the name of the manufacturer, hjs designated identifying number and the electric rating in volts, horsepower,

amperes, frequency,

phases, etc.,

qs may be appropriate.

The markings shall be so located a'

to be visible after installation.

• 7-3.9 Instructions.

Complete instructions covering the operation of the controller shall be provided and conspicuously mounted. on the controller, Hameplates for ratings of equipment are provided yhere necessary, Instruction manuals are not required for operation of the breaker because

'perations personnel are knowledgeable in the electrical and manual operation of the breaker.

NFPA-20 Requirements.

7-4 Cotgponents 7-4.1 Isolating Means.

The isolating means shall be a manually operable motor circuit switch or a molded case switch, either having a horsepower rating equal to the motor horsepower.

Exception l.

A molded case switch having an ampere rating of not less than 115 percent of the motor full load current, and also suitable for inter-rupting the motor locked rotor current shall be permitted.

Exception 2.

This isolating means is not required on limited service controllers.

PSL-1 Existing System See circuit breaker section (7-4.2.)

7-4.1.1 The isolating means shall be externally operable (see 7-3.6).

7-4.1.2 The ampere rating of the isolating means shall be at least 115 percent of the nameplate current rating of the motor.

"7-4.2 Circuit Breaker (Disconnecting Means).

The motor branch circuit shall be protected by a suitable magnetic trip-type circuit breaker, connected directly to the load side of the isolating means and conforming with the following requirements:

Exception:

The circuit breaker for a limited service controller need not be a magnetic trip type.

(See 7-7.2.)

The design philosophy at PSL-1 for motors greater than 100hp, whether nuclear safety-related or non-

. safety related,

.was to utilize stored energy circuit breakers versus magnetic type motor starters.

In this design, the stored energy circuit breaker re-places the need for an isolating means and motor starter.

The fire pump breakers are fed from a safety related load center and are capable of be~

loaded onto the emergency diesel generators.

'The fire pump motors'ircuit breakers were purchased to nuclear grade Class IE requirements and provide for locked rotor and instantaneous short circuit protection in accordnace with NFPA-20.

These breakers

. open and close via stored energy, thus once closed, the breakers will remain closed upon loss of control power.

This design is more reliable than the magnetic starter recommended by NFPA-20 since once control power is lost, power to the motor is also lost In addition, the circuit breaker has the capability of being manually opened or closed, thereby increasing system reliability.

NFPA-20 Requirements 7-4.2.1 No other overcurrent protective devices shall be in the motor circuit on the load side of the circuit breaker LSee 6-3.4 for rating and setting of overcurrent devices in the circuit on the line side of the circuit breaker.

See NFPA 70, National Electrical

Code, Sections 430-37 and 240-20(a) for the number of overcurrent units required for circuit protection devices (see Appendix C).]

~ I 7-4.2.2 The circuit breaker shall have one pole for each ungrounded branch circuit conductor.

7-4.2.3 The circuit breaker shall be externally operable.

7-4.2.4 The circuit breaker shall trip free of the handle.

PSL-I Existing System The existing;circuit breakers meet sections 7-4;2.1 through 7-4.2,6.

The'ire 'pump's full

'load current is 275 amperes versus the breaker's continuous rating of 600 amperes.

7-4.2.5 The circuit breaker rating shall be not less than 115 percent of the rated full load current load of the motor.

7-4.2.6 The circuit. breaker shall permit normal starting of the motor without tripping.

7-4.2.7 The circuit breaker shall provide locked rotor and instantaneous short circuit protection.

(a)

For a squirrel cage induction motor, the circuit breaker shall be:

l.

Of the time delay type having a tripping time between 8 and 20 seconds at locked rotor current (this is approximately 600 percent of rated full load current for a squirrel cage induction motor).

2.

Calibrated in amperes up to and set at 300 per-cent of the motor full load current.

The circuit breaker provides for locked rotor and instantaneous short circuit protection and various other valves depending upon the time-current trip~

setting relationship.

The breaker is set to trip~

between a minimum of 8 and 20 seconds for locked rotor conditions.

NAPA-20 Requirements 7-4.2.8 The overcurrent sensing elements of the circuit breaker shall be of the nonthermal type.

Exception:

Ambient temperature compensated thermal elements may be used.

PSL-1 Existing System The overcurrent sensing elements are of the nonthermal type.

• 7-4.2.9 The interrupting rating of the circuit breaker shall be equal to or greater than the available shortcircuit current for the circuit in which it is used.

When the available short-circuit current at the line terminals of the controller exceeds the interrupting rating of the largest available breaker, the circuit breaker used shall be protected with current limiting fuses (bolted type Class J or L) coordinated with the circuit breaker so that the short-circuit currents within the circuit breaker'ating are interrupted by the circuit breaker only.

These fuses shall hold locked rotor current of the motor continuously [for further detail see ANSI C37.27 (see Appendix C).]

Coordinated in this sense means that the character-istics of 7-4.2.7 shall be provided by the. circuit breaker alone, and the fuse shall not permit peak let-

- through current in excess of 2.3 times the 240 volt rms symmetrical interrupting rating of the circuit-breaker.

The crossover point of the fuse curve shall be to the left of the intersection of the interrupting rating of the circuit breaker on the instantaneou's trip clearing time curve of the circuit breaker.

The current limiting fuses shall be mounted in the controller panel and connected between the isolating means and the circuit breaker (See Fig. A-7-4.2.9. )

7-4.2.10 The circuit breaker interrupting rating shall be selected by using Table 7-4.2.10 when the install-ation meets the criteria established in the notes to the Table.

Otherwise, a short-circuit study must be made to establish the available short-circuit current at the controller in accordance with IEEE 141, Electric Power Distribution for Industrial Plants or IEEE 241, Electric Systems for Commercial Buildings.

(See Appendix C.)

Using NFPA-20 Table 7-4.2.10, the recommended circuit breaker interrupting rating is 22,000 amperes based on a 1500KVA transformer at a

secondary voltage of 480 volts.

The existing circuit breaker is rated for 22,000 amperes symmetrical.

This exceeds the available short circuit current.

NFPA-20 Requirements 7-4.3 Motor Starter PSL-1 Existing System See reply to section 7-4.2.

C.

7-4.3.1 The motor shall be of the magnetic type with a contact in each ungrounded conductor.

7-4.3.2 For electrical operation of reduced voltage

starters, timed automatic acceleration of the motor shall be provided.

The period of motor acceleration shall not exceed 10 seconds.

7-4.3.3 Starting resistors shall be designed to permit one five second starting operation in each 80 seconds for a period of not less than one hour..

7-4.3.4 The operating coil for the main contactor shall be supplied directly from the main power voltage and not through a transformer (for controllers of 600 volts or less).

• 7-4;4 Alarm and Signal Devices on Controller.

A pilot lamp (6w or 7w, 115-'l25 volt, candelabra base) shall be connected to a pair of power supply conductors directly on the line side of the motor starter (load side of the circuit breaker) to indicate that the circuit breaker and test link are closed and that power is available at the controller for starting.

The lamp shall be accessible for replacement.

Indicating lights are a part of the breaker cubicle to inform personnel that either the breaker is open or closed, and therefore that control power is available.

Meters are availab'le on the Load Center to inform personnel that power is available.

NFPA-20 Requi rements 7-4.5 Alarm and Signal Devices Remote from Controller.

When the pump room is not constantly

attended, audible or visual alarms powered by a

source, not exceeding 125 volts, shall be pro-voided at a point of constant attendance.

These alarms shall indicate the following:

(a)

Controller has operated into a motor running condition.

This alarm circuit shall be energized by a separate reliable supervised power source, or from the pump motor power, reduced to not more than 125 volts.

pSL-1 Existing System Audible and visual alarms are provided via the annunciator system in the control room to indicate if the fire pumps are running or the local control switch is in the stop position.

Power for these items is provided from the safety-related power supplies of 125 vdc.

Loss of power to the breaker is detected immediately by bus under voltage relays and alarmed in the control room.

• (b) Loss of line power on line side of motor starter, in any phase.

This alarm circuit shall be energized by a separate reliable supervised power source.

7-4.6 Controller Alarm Contacts for Remote Indication.

Controllers shall be equipped with contacts (open or closed) to operate circuits for the conditions covered in 7-4.5.

Alarm contacts for indication of pump running is obtained from the motor's breaker.

7-5 Starting and Control.

• 7-.5.1 Automatic and Nonautomatic.

7-5.1.1 An automatic controller shall be operable also as a nonautomatic controller.

The fire pump installation meets the requirements of sections 7-5.1.1 and 7-5.1.2.

7-5; 1.2 A nonautomatic controller shall be actuated by manually initiated electrical means and by manually initiated mechanical means.

HFPA-20 Requirements 7-5.2 Automatic Controller.

PSL-1 Existing System

• 7-5.2.1 Water Pressure Control.. In the controller circuit there shall be provided a pressure-actuated switch having independent high and low calibrated adjustments, and responsive to water pressure in the fire protection system.

The pressure sensing element of the switch shall be capable of withstanding a momentary surge pressure of 400 psi (27.6 bars) with-out losing its accuracy.

Suitable provision shall be made for relieving pressure to the pressure-actuated switch, to test the operation of the controller and the pumping uni t.

(See Fig. A-7-5.2.1.)

(a)

Each controller for multiple pump installations.

shall have its own individual pressure sensing line.

The shut-.off head on the fire pumps is a maximum of 150 psi.

System pressures in excess of this shut-off head are not expected.

The maximum pressure to which the pressure switches may be exposed without harmful effect to set point repeatabi lity is 250 psi.

Therefore, the requirement of section 7-5.2.1 is met.

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I There are two pressure sensing elements (for the transformer deluge system and plant fire header) which detect low pressure and start the fire pumps.

Both controllers (pressure switches) have their own pressure sensing line and provisions are made for relieving pressure for purposes of testing both pressure switches.

7-5.2.2 Fire Protection Equipment Control.

When the pump supplies special water control equipment (deluge valves, dry pipe valves, etc.)

and it is desired to start the motor before the pressure-actuated switch(es) would do so, the controller shall be equipped to start the motor upon operation of the fire protect'ion equipment.

This equipment shall be a relay of the drop-out type.

The relay shall be actuated from a normally closed contact on the fire protection equipment.

The pressure switch for the transformer deluge system uses a normally closed contact for low pressure.

NFPA-20 Requirements "7-5.2.3 Manual Electric Control at Remote Station.

When additional control stations for causing nonautomatic continuous operation of the pumping unit, independent of the pressure-actuated

switch, are provided at locations remote from the controller, such stations shall not be operable to stop the motor."

PSL-I Existing Systems The controllers (circuit breakers) are located with the safety related load centers which have the capability of starting/stopping the fire pumps.

Adjacent to each fire pump is a local control station with the capability of starting, stopping and engaging the automatic circuitry of the fire pumps.

The existing system also has a control switch in the control room with the capability of stopping or engaging the automatic circuitry of the fire pumps.

If either switch, local or control room, is placed in the stop position, annunciation is provide in the control room.

The use of a stop switchMn the control room is the same philosophy utilized for safety-related equipment.

"7-5.2.4 Sequence Starting of Pumps Operating in Parallel.

The controller for each unit of multiple pump units shall incorporate a sequential timing device to prevent any one motor from starting simultaneously with any other motor.. If water requirements call for more than one pumping unit to operate, the units shall start at intervals of five to ten seconds.

Failure of a leading motor to start shall not prevent subsequent pumping units from starting."

The fire water system is designed to and ha's operated with both pumps starting at the sam'e time.

Therefore, we see no advantage to starting the pumps sequentially.

A disadvantage would be slower pressure recovery time.

Also, the nuclear facility has more power supplies available than most industrial/commercial facilities and both normaI and emergency power supplies are totally separated for the two pumps so simultaneous starting presents no electrical loading problems.

Failure of either'pump to start will not affec starting of the other pump.

NFPA-20 Requirements "7-5.2.5 External Circuits Connected to Controllers.

Mith pumping units operatin'g singly or in parallel, the control circuits leaving or entering the fire pump controller shall be so arranged that breakage, disconnecting, shorting of the wires or loss of power to these circuits may cause continuous running of the fire pump but shall not prevent the controller(s) from starting the fire pump(s) due to causes other than these external circuits."

PSL-1 Existing System As stated previously, the circuit breaker is a stored energy type of controller. If control power is lost while the pump is operating, the breaker will remain closed thereby supplying power to the motor.

The breaker can also be operate d manually if control power is lost.

7-5.3 Nonautomatic Controller.

"7-5.3.1 Manual Electric Control at Controller.

There shall be a manually operated switch on the control panel so arranged that when the motor is started manu'ally, its operation cannot be affected by the pressure-actuated switch.

The arrangement shall also provide that the unit will remain in operation until manually shut down.

The existing system meets these nequirements.

7-5.3.2 Manual Mechanical Control at Controller.

(a)

The controller shall be equipped with a handle or lever which operates to close the motor-circuit switching mechanism mechanically.

This handle or lever shall provide for nonautomatic continuous running operation of the motor(s) independent of any electric control circuits, magnets or equivalent

devices, and independent of the pressure-activated control switch.

Means shall be incorporated for mechanically latching or holding of the handle or lever for manual operation in the actuated position.

The mechanical latching shall not be automatic, but at the option of the operator.

(b)

The handle or lever shall be arranged to move in one direction only from "off" to final position.

(c)

The motor starter shall return automatically to the "off" positi on in case the operator releases the starter handle in any but the full running position.

Tje stored energy circuit breaker is provided with a manual spring charging/breaker closing handle whi ch in one continuous downward pull of the handle, the two closing, springs are charged and near the end of the stroke are discharged ~

to fast close the circuit breaker.

If the handle is released prior to the discharging of the springs, the handle will return to its initial position.

NFPA-20 Requirements PSL-1 Existing System 7-5.4 Methods of Stopping.

Shutdown shall be accomplished by the following methods:

1.

Manual operation of reset pushbutton on outside of controller enclosure which, in the case of automatic controllers, shall return the controller to full automatic position.

The existing system meets these requirements.

2, Automatic shutdown after automatic start (optional)--if controller is set up for automatic shutdown after starting causes have returned to

normal, a running period timer set for at least one minute running time for each ten horsepower of motor rating (but which need not exceed seven minutes) shall be used.

After the fire pumps are started, they must be manually shut down,

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r NFPA-20 Requirements PSL-1 Existing System In addition to your request for information pertaining to the el'ectrical'ontrollers, FPKL believes that the following information will be of interest to the NRC Staff Review Team.

• 6-3 Power Supply Lines.

• 6-3.1 Type of Lines.

The lines between the power plant{s) and the pump room shall be of such number, so arranged and so located that there will be small chance of an interruption of service to the motor(s),

due to accident to the lines.

6-3.2 Pump Room Miring. All wiring in the pump room shall be in rigid metal conduit, electrical metallic tubing or liquid-tight flexible metal conduit.

The raceway ppovided for control and power to the pump/motors'ontrollers and motor termination points are designed with the requirements of 6-3.1 in mind.

The same philosophy is utilized for safety-related cables.

The existing system meets the requirements of Section 6-3.2.

6-3.3 Capacity of Lines.

6-3.3,1 Each line between the power supply circuits at utility plants, substations or plant load distribution centers and ahead of fire pimp feeder circuits shall be sized in accordance with NFPA 70, National Electrical Code, Article 430, Part 8, Motor Circuit Conductors; Section 230-2, Exception 1; Section 230-44 and Section 230-82, Exception 5,

(See Appendix C.)

The existing system meets these requirements as a minimum.

6-3.3.2 Each line installed in the fire pump feeder The cable used in'power and control circuitry circuit shall be sized at 125 percent of the sum of the was purchased to nuclear grade Class 1E full load current(s) of the fire pump and jockey pump requirements.

The cables ahead of and,in the motor(s) plus the current of the necessary associated fire pump feeder circuits are conservatively fire pump installation electrical accessories.

[See sized to meet or exceed NFPA-20 requirements.

NFPA 70, National Electrical Code, Section 230-90(a),

For example, the power feed between the circuit Exception 5 (see Appendix C).]

breaker and the motor is sized approximately 505 greater than required by NFPA-20.

The fire pump feeder circuit conductors shall be physically routed outside of the building(s), excluding the switch room (when involved) and the pump room.

When the fire pump feeder conductors must be routed through buildings, they shall be buried or protected with two inches (51 mm) of concrete or equivalent in order to be judged "outside of the building" according to NFPA 70, the National Electrical Code, Article 230-44.

{See Appendix C.)

NFPA-20 Requirements "6-3.3.3 The voltage at the motor shall not drop more than five percent below the voltage rating of the motors when the pumps are being driven at rated output, pressure, and

speed, and when the lines between power station(s) and motors are carrying their peak loads."

"6-3.3.4 Where squirrel-cage motors are used, the capacity of the generating station(s),

the connecting lines, and the transformers shall be ample to keep the voltage from dropping more than 15 percent below normal voltage under motor starting conditions."

6-3.4 Power Supply Protective Oevices.

PSL-1 Existing System The existing system meets the requirements of sections 6-3.3.3 and 6-3.3.4 as a minimum.

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"6-3.4.1 When power supply protective devices (fuses or circuit breakers) are installed in the

'ower supply circuits at utility plants, substations, or plant load distrubtion centers ahead of the fire pump feeder circuits, such devices shall not open at the sum; of the locked rotor currents of the fire pump motor(s) and the maximum plant load currents."

The existing system meets the requirements of sections 6-3.4.1 and 6-3.4.2.

"6-3.4.2 When power supply protective devices

.(fuses or ci.rcuit breakers) are installed in the fire pump feeder circuit, such devices shall not open at the sum of the locked rotor currents of the fire pump motor(s) and the necessary associated fire pump installation electrical accessory currents."

I See also NFPA 70, the National Electrical

Code, Section 230-90(a),

Exception 5.

(See Appendix C).]

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P TTACHt1ENT C

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Cable Area Evaluation Please refer to the fire protection eval'uation provided by Florida Power 5 Light Company (FL) letter L-77-102 dated March 31, 1977.

On pages 8 through 100 of Section '8.4.1.19 (Cable Loft; Areas 43, 44', and 54)

FP L discusses the results of a detailed evaluation of the safety considerations associated with a design basis fire.

Table 7-9 is a compilation of shutdown related cable functions by fire area, and areas 43, 44, and 54 are specifically addressed on pages 7-43 through 7-49.

In addition, detailed discussions of this and many other fire protection subjects were held with members of a

NRC fire protection review team at the St. Lucie site over the period December 4 through December 10, 1978.

FPL has'concluded that the information described above is responsive to the August 17, 1979 request for cable area information (cover letter to Amendment 33 to License P R-67).

However, if further information is desired, F L personnel will be available to di"scuss this subject during an 'upcoming meeting with the NRC staff scheduled for October 15-16, 1979 at the St. Lucie site.

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