ML17207A453

From kanterella
Jump to navigation Jump to search
Forwards Fire Protection Info Re Preliminary Schedule Mod, Fire Pump Controller Evaluation & Cable Area Evaluation in Response to NRC 790817 Ltr
ML17207A453
Person / Time
Site: Saint Lucie NextEra Energy icon.png
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 DOCKET FACIL:50-335 St, Lucie Plant< Unit ii Florida Power 8 l ight Co. 05000335 AUTH, NAME AUTHOR AFFILIATION UHRIGiR ~ ED Florida Power E Light Co.

REC IP ~ NAME RECIPIENT AFFILIATION REIDE R ~ N ~ Operating Reactors Branch

SUBJECT:

For wards fire protection info re preliminary schedule modi fire pump controller evaluation 8, cable area evaluation in response to NRC 790S17 ltd DISTRIBUTION CODE: A0060 COPIES RECEIVED:LTR PENCL 2g, SIZE!

TITLE: Fire Protection Information (After Issuance of OP. L'ic,)

I' N OT E. 0 f n II

~

+ wwp\w&w&~~~~~~w&%1%~~~w~~~No w~ww&ot&ww&oawoowwoo'ptwwwwslww&w&ww&w&p wpowwolw&st&~~w RKC IP IENT COPIES RECIPIENT COPIES IO CODF/NAME LTTR ENCL IO CODE/NAME LTTR ENCL ACTION: 05 BC INTERNAL: ~

09 REG FI~'

2 1

2 02 NRC PDR ii TA/EDO 1

1 1

1

'12 AUXIL SYS BR 2 2 14 PLANT'YS BR 5 5 19 NAMBACH 1 1 20 MURANAKAiR 1 1 OELO 1 0 EXTERNAL: 03 LPO" 1 1 0 ll NS IC 1 1 22 ACRS lb 16 OCT is>>79 Jk TOTAL NUMBER OF COPIES REQUIRED: LTTR 37 ENCL 36

I I

I V

i C

BOX 629100, MIAMI, FL 33162 ygllgg~

tv~~uwX FLORIDA POWER 4 LIGHT COMPANY 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

c ATTACHMENT A PRELIMINARYB .MODI F I CATION SCHEDULE ST..LUCIE UNIT 1 FIRE PROTECTION FPL's Item Engineering NRC NRC Proposed Design Submittal Approval Implementation

~d ~di dd 3.1 ~Fi 3.1.1 Completed 3.1. 2 Completed 3.1. 3 April 1980 Oct, 1980 3.1.4 Dec. 1979 Jan. 1980 Feb. 1980 Oct. 1980 3.2 Fire Protection Water Pi in S stem 3.2.1 Dec. 1979 3.2.2 Completed, 3.2.3 April 1980 Oct, 1980 3.2.4 'Dec. 1979 3.2.5 Completed

3. 3 Foam Equi,pment Dec. 1979 3.4 Portable Smoke Ejectors Completed

'.5 Air Breathing Dec. 1979 Equipment

'.6 Fire Door Evaluation **Completed 3.7 Ventilation Duct **Completed Penetrations 3.8 Control Room 3.8.1 Completed 3.8.2 Dec. 1979 3.8.3 Jan. 1980 Oct. 1980 3.8.4 Dec, 1979 Oct. 1980 3.8. 5 **Completed

3. 3 ~ddi 3 di March 1980 April 1980 May 1980 Dec. 1981 Room

FPL's Engineering NRC NRC . Proposed Design Submittal Approval Implementation Item Com letion Date Date * ~Ri BB 1 3.10 Switch ear Rooms 3.10.1 Completed 3.10. 2 Completed 1.11'B Jan. 1980 Oct. 1980 Ventilation 3.12 Reactor Auxiliar

~B'Id 3.12.1 Completed 3.12. 2 Completed 3.12. 3 Completed 3.12. 4 Dec. 1979 3.12. 5 April 1980 Oct. 1980 3.12.6 Completed 3.12. 7 Feb. 1980 March 1980 April 1980 Oct. 1980 3.12.8 Feb. 1980 Oct. 1980 3.12.9 Dec. 1979 3.13 Reactor Bldg 3.13.1 Completed

3. 1'3. 2 April 1980 Dec. 1981 3.13. 3 May 1980 June 1980 July 1980 Dec. 1981 3.14 Diesel Generator Bld .

and Fuel Oil Stora e Tanks 3.14.1 Completed 3.14. 2 April 1980 Oct. 1980 3.14. 3 April 1980 Oct. 1980

3. 14. 4 May 1980 Oct. 1980 3.14. 5 April 1980 May 1980 June 1980 Dec. 1981 3.14. 6 April 1980 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.

~ ~

(

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

~

' ~

(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)

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 will not result in depriving fire water to safety-related areas.

3.2.4 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.

.3.2.5 H drant Hose Valves (4.3.1.3)

A 2

'ose 1/2-inch gated hydrant hose valve gill be provided in each house.

3.3 Foam E ui ment. (4.3.1.6)(5.14.5)

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.

3.4 Portable Smoke E ectoxs (4.4.1)

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.

3.5 Air Sreathin E ui ment {4.4.3)

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

~ ~

~

+3.6 Fire Door Evaluation (4.9.1)

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

+3 7 Duct Penetrations (4.9.2)

The ventilation duct penetrations of barriers enclosing safety related systems are to be"reevaluated. I ire or smoke dampers will be provided at locations where the evaluation shows that potential effects due to an unmitigated fire could affect safe shutdown.

3.8 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)

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

3.8.4 Fire Door (4.9.1)(5.1.6)(5.6:6)

A 'one hour fire rated self closing door will be provided at the entrance to the corridor serving the kitchen/office area.

3.8.5 . 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->)

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.

3.10 Switch ear,Rooms (43 Foot Elevation) (5.3) 3.10.1 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)

The polyurethane insulation on the piping in the switchgear room will be covered with a fire retardant material.

3.11 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)

The ordinary glass windows in the stairway fire doors will be replaced with wire glass or fire rated doors will be provided.

3.12.2 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.

3.12.3 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 3.12.4 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.

~ ~

~

~

3.12-5 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).

3.12.6 Flammable Gas Pi in Identification (5.8.6)

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

auxiliary'uilding

  • 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)

Hetal tool lockers will be provided within the containment for the storage of combustible materials left inside the containment building.

3.13.2 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 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.

3.14 Diesel Generator Buildin and Fuel Oil Stora e Tanks {5.14) 3.1 4. 1 Curbs (5.14.6)

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.

'.14.2 Fire Door (4.9.1)(5.14.6)

The dooz opening between the diesel generator rooms will be provided w3. th a three hour fire rated door.

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.

I <

~

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.

~ ~

1) 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 As is standard with all plant controll'ers, purchased under unit contract stipulating including controllers, the controllers were compliance with this standard and satisfactory purchased separate from the pumps and drivers.

performance of the entire unit when installed." 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 PSL-1 Existing System 7-1.1 General ..

"7-1.1.1 All controll ers shall be specifically Since the controllers for both fire pumps listed for electric motor driven fire pump were purchased to nuclear grade Class IE servi ce. " requirements the equipment is certainly acceptable for fire pump service.

(a) Any controller selected shall have a short Please note that Table 7-4.2.9 does not exist.

circui,t. rating at least equal to the available Using Table 7-4.2.10, the recommended circuit short circuit current for the circuit in which it breaks interrupting rating is 22,000 amperes is used. symmetrical based on a 1500KYA transformer at a secondary voltage of 480 volts. The (b) Short circuit current at the controller shall existing circuit breaker meets these requirements.

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.)

7-1.1.2 All controllers shall be completely Because the. circuit breakers are a part of the assembled, .wired, and tested by the manufacturer nuclear grade Class IE load centers, the before shipment from the factory. breakers were purchased, manufactured and tested to Class IE quality assurance requirements. There-t fore, we believe a better product was obtained than if purchased as industrial grade.

7-2 Loca tion,

  • 7-2.1 Controllers shall be located as close as The fire pumps'ircuit breakers and control is practical to the motors they control and shall circuAry are located in the Reactor Auxiliary

~

be within sight of the motors. Building (RAB), a reinforced concrete structure, and are a part of safety-related load centers 7-2.2 Controllers shall be so located or so which meet 7-2.2. To ensure the integrity and protected that they will not be injured by water protection of the power supply, it is located in escaping from pumps or pump connections. Current the RAB, The fire pumps are located adjacent to carrying parts of controllers shall be not less their water supply for obvious reasons. Therefore, than 12 inches (305 mm) above the floor level. 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 PSL'1-. Existing System..

7-3 Construction 7-3.1 Equipmenl. All equipment shall be suitable As previously stated, the circuit breakers and for use in locations subject to a moderate degree control circuitry are located in a reinforced of moisture such as a damp basement. concrete building which precludes a "damp basement" and "falling drops of water." The 7-3.2 f1ounting. All equipment shall be mounted above are in a seismically qualified steel cabinet in a substantial manner on a single noncombustible which is attached to the concrete floor.

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, 7-3.4.3 Bus bars and other wiring elements of the Equipment meets these requirements as a minimum.

controller shall be designed on a continuous duty basis.

7-3e5 Protection of Auxiliary Circuits. Circuits Circuitry must be protected against overcurrent which are depended upon for proper operation of 'the to prevent damage and the possibility of fire.

controller shall oot have overcurrent protective If power is lost to the pump, the control room devices connected in them. 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 PSL-1 Existing System 7-3.6 .External Operation. All switching equipment The circuit breakers can be manually operated for manual use in connecting or disconnecting, or externally to the cubicle.

starting or stopping the motor shall he externally operable as defined in NFPA 70, National. Electric Code (see Appendix C).

7-3,7 Wiring Diagrams and Instructions. -A wiring diagram is not provided inside the controller enclosure. If wiring'evisions are 7-3.7.1 A wiring diagram shall be provided and perma- necessary, plant personnel experienced with this nently attached to the inside of the controller equipment have necessary drawings available. All enclosure. terminals and cables (except for manufacturer's cables) are plainly marked. It should be noted 7-3.7.2 All the field wiring terminals shall be that both operations and maintenance activities plainly marked to correspond with the wiring at a nuclear plant, on equipment powered from diagram furnished. 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 Hameplates for ratings of equipment are provided switch and circuit breaker shall be marked to plainly yhere necessary, Instruction manuals are not indicate the name of the manufacturer, hjs designated required for operation of the breaker because

  • . identifying number and the electric rating in volts, 'perations personnel are knowledgeable in the horsepower, amperes, frequency, phases, etc., qs may electrical and manual operation of the breaker.

a' be appropriate. The markings shall be so located 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,

NFPA-20 Requirements. PSL-1 Existing System 7-4 Cotgponents 7-4.1 Isolating Means. The isolating means shall See circuit breaker section (7-4.2.)

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.

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 The design philosophy at PSL-1 for motors greater motor branch circuit shall be protected by a suitable than 100hp, whether nuclear safety-related or non-magnetic trip-type circuit breaker, connected . safety related, .was to utilize stored energy circuit directly to the load side of the isolating means and breakers versus magnetic type motor starters. In conforming with the following requirements: this design, the stored energy circuit breaker re-places the need for an isolating means and motor Exception: The circuit breaker for a limited service starter. The fire pump breakers are fed from a controller need not be a magnetic trip type. (See safety related load center and are capable of be~

7-7.2.) 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 PSL-I Existing System 7-4.2.1 No other overcurrent protective devices The existing;circuit breakers meet sections shall be in the motor circuit on the load side of 7-4;2.1 through 7-4.2,6 . The'ire 'pump's full the circuit breaker LSee 6-3.4 for rating and 'load current is 275 amperes versus the breaker's setting of overcurrent devices in the circuit on continuous rating of 600 amperes.

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.

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

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

circuit setting relationship. The breaker is set to between a minimum of 8 and 20 seconds for locked trip~

rotor conditions.

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.

NAPA-20 Requirements PSL-1 Existing System 7-4.2.8 The overcurrent sensing elements of the The overcurrent sensing elements are of the circuit breaker shall be of the nonthermal type. nonthermal type.

Exception: Ambient temperature compensated thermal elements may be used.

  • 7-4.2.9 The interrupting rating of the circuit Using NFPA-20 Table 7-4.2.10, the recommended breaker shall be equal to or greater than the circuit breaker interrupting rating is 22,000 available shortcircuit current for the circuit amperes based on a 1500KVA transformer at a in which it is used. When the available short-circuit secondary voltage of 480 volts. The existing current at the line terminals of the controller circuit breaker is rated for 22,000 amperes exceeds the interrupting rating of the largest symmetrical. This exceeds the available short available breaker, the circuit breaker used shall be circuit current.

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.)

NFPA-20 Requirements PSL-1 Existing System C.

7-4.3 Motor Starter See reply to section 7-4.2.

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 Indicating lights are a part of the breaker pilot lamp (6w or 7w, 115-'l25 volt, candelabra base) cubicle to inform personnel that either the shall be connected to a pair of power supply breaker is open or closed, and therefore that conductors directly on the line side of the motor control power is available. Meters are availab'le starter (load side of the circuit breaker) to on the Load Center to inform personnel that indicate that the circuit breaker and test link power is available.

are closed and that power is available at the controller for starting. The lamp shall be accessible for replacement.

NFPA-20 Requi rements pSL-1 Existing System 7-4.5 Alarm and Signal Devices Remote from Audible and visual alarms are provided via the Controller. When the pump room is not constantly annunciator system in the control room to indicate attended, audible or visual alarms powered by a if the fire pumps are running or the local control source, not exceeding 125 volts, shall be pro- switch is in the stop position. Power for these voided at a point of constant attendance. These items is provided from the safety-related power alarms shall indicate the following: supplies of 125 vdc. Loss of power to the breaker is detected immediately by bus under (a) Controller has operated into a motor voltage relays and alarmed in the control room.

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.

  • (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. Alarm contacts for indication of pump running is Controllers shall be equipped with contacts (open or obtained from the motor's breaker.

closed) to operate circuits for the conditions covered in 7-4.5.

7-5 Starting and Control.

  • 7-.5.1 Automatic and Nonautomatic.

7-5.1.1 An automatic controller shall be operable The fire pump installation meets the requirements also as a nonautomatic controller. 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 PSL-1 Existing System 7-5.2 Automatic Controller.

  • 7-5.2.1 Water Pressure Control.. In the controller The shut-.off head on the fire pumps is a maximum circuit there shall be provided a pressure-actuated of 150 psi. System pressures in excess of this switch having independent high and low calibrated shut-off head are not expected. The maximum adjustments, and responsive to water pressure in pressure to which the pressure switches may be the fire protection system. The pressure sensing exposed without harmful effect to set point element of the switch shall be capable of withstanding repeatabi lity is 250 psi. Therefore, the a momentary surge pressure of 400 psi (27.6 bars) with- requirement of section 7-5.2.1 is met.

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.)

I

~

(a) Each controller for multiple pump installations. There are two pressure sensing elements (for the shall have its own individual pressure sensing line. 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 The pressure switch for the transformer deluge pump supplies special water control equipment (deluge system uses a normally closed contact for low it valves, dry pipe valves, etc.) and is desired to pressure.

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.

NFPA-20 Requirements PSL-I Existing Systems "7-5.2.3 Manual Electric Control at Remote Station. The controllers (circuit breakers) are located When additional control stations for causing with the safety related load centers which have nonautomatic continuous operation of the pumping the capability of starting/stopping the fire unit, independent of the pressure-actuated switch, pumps. Adjacent to each fire pump is a local are provided at locations remote from the control station with the capability of starting, controller, such stations shall not be operable stopping and engaging the automatic circuitry to stop the motor." 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 The fire water system is designed to and ha's Parallel. The controller for each unit of multiple operated with both pumps starting at the sam'e pump units shall incorporate a sequential timing time. Therefore, we see no advantage to starting device to prevent any one motor from starting the pumps sequentially. A disadvantage would be simultaneously with any other motor.. If water slower pressure recovery time. Also, the nuclear requirements call for more than one pumping unit facility has more power supplies available than to operate, the units shall start at intervals of most industrial/commercial facilities and both five to ten seconds. Failure of a leading motor normaI and emergency power supplies are totally to start shall not prevent subsequent pumping units separated for the two pumps so simultaneous from starting." starting presents no electrical loading problems.

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

NFPA-20 Requirements PSL-1 Existing System "7-5.2.5 External Circuits Connected to Controllers. As stated previously, the circuit breaker Mith pumping units operatin'g singly or in parallel, is a stored energy type of controller. If the control circuits leaving or entering the fire control power is lost while the pump is pump controller shall be so arranged that breakage, operating, the breaker will remain closed disconnecting, shorting of the wires or loss of thereby supplying power to the motor. The power to these circuits may cause continuous breaker can also be operate d manually if running of the fire pump but shall not prevent control power is lost.

the controller(s) from starting the fire pump(s) due to causes other than these external circuits."

7-5.3 Nonautomatic Controller.

"7-5.3.1 Manual Electric Control at Controller. The existing system meets these nequirements.

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.

7-5.3.2 Manual Mechanical Control at Controller.

(a) The controller shall be equipped with a handle Tje stored energy circuit breaker is provided or lever which operates to close the motor-circuit with a manual spring charging/breaker closing switching mechanism mechanically. This handle or handle whi ch in one continuous downward pull of lever shall provide for nonautomatic continuous the handle, the two closing, springs are charged running operation of the motor(s) independent of any electric control circuits, magnets or equivalent and near the end of the stroke are discharged to fast close the circuit breaker. If the

~

devices, and independent of the pressure-activated handle is released prior to the discharging of control switch. Means shall be incorporated for the springs, the handle will return to its mechanically latching or holding of the handle or lever initial position.

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.

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 The existing system meets these requirements.

of controller enclosure which, in the case of automatic controllers, shall return the controller to full automatic position.

2, Automatic shutdown after automatic start After the fire pumps are started, they must (optional)--if controller is set up for automatic be manually shut down, 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.

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 The raceway ppovided for control and power plant{s) and the pump room shall be of such number, to the pump/motors'ontrollers and motor so arranged and so located that there will be small termination points are designed with the chance of an interruption of service to the motor(s), requirements of 6-3.1 in mind. The same due to accident to the lines. philosophy is utilized for safety-related cables.

6-3.2 Pump Room Miring. All wiring in the pump The existing system meets the requirements room shall be in rigid metal conduit, electrical of Section 6-3.2.

metallic tubing or liquid-tight flexible metal conduit.

6-3.3 Capacity of Lines.

6-3.3,1 Each line between the power supply circuits The existing system meets these requirements at utility plants, substations or plant load as a minimum.

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.)

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 PSL-1 Existing System "6-3.3.3 The voltage at the motor shall not The existing system meets the requirements drop more than five percent below the of sections 6-3.3.3 and 6-3.3.4 as a minimum.

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.

~

"6-3.4.1 When power supply protective devices The existing system meets the requirements of (fuses or circuit breakers) are installed in the sections 6-3.4.1 and 6-3.4.2.

'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."

"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).]

~

~

=

p ~, ' ~

P TTACHt1ENT C =

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 o f 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 A

~ +

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.