Text

Issue 56 to AOP-I, Discussion of Fire
	ML20058N107
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/10/1990
From:	Fuller C; PUBLIC SERVICE CO. OF COLORADO
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	AOP-I-I-56, P-90249, NUDOCS 9008130227
	Download: ML20058N107 (19)
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Public Service'-

=g-Denver, CO 10201 0840 16805 WCR 19 1/2, Platteville, Colorado 80651 i

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August 10, 1990 Fort St. Vrain i

Unit No. I r

P-90249 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop P1-37 Washington, D.C.

20555 l

DOCKET NO:

. 50-267

SUBJECT:

ABNORMAL OPERATING PROCEDURE DISTRIBUTION Gentlemen:

We are-transmitting herein the following:

Issue'56 of AOP-I Two copies of this procedure have also been transmitted to Region IV, Emergency Response Coordinator, in accordance with 10CFR50.54(q)

~(Reference P-90250).

In accordance with 10CFR50.54(q), we have determined that the changes in this issue do not decrease the effectiveness of the Fort St. Vrain Emergency Plans and the plans, as changed, continue to meet the i

intent of 10CFR50.47(b) and 10CFR50 Appendix E.

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Public FORT ST. VRAIN NUCLEAR GENERATING STATION StrVlCO' PusuC senvoca COMPANY OF COLORAM 08/01/90

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ABNORMAL OPERATING PROCEDURES ISSUE

, EFFECTIVE NO.

SUBJECT NUMBER DATE INTRO Abnormal Operating Procedures Introduction 55 04-19-90 A

Voisture In-Leakage 57 04-19-90 B

Roactor Scram 57 04-19-90 B-2 0FLETED 01-09-88 C

oop Shutdown 57-Last 03-28-90 0-1 Single Circulator Trip 55 04-19-90 a

D-2 Three Circulator Trips 54-Last 03-21-90 1

E Abnormal Reactor Pcwer Change 56-Last 03-28-90 V

F-1 Main Turbine Energencies 58-Last 03-28-90 l

F-2 Low Condenser Vacuum Turbine Trip 55-Last 03-28-90 i

F-3 Loss of Outside Power and Turbine Trip 55-Last 03-28-90 F-4 Loss of Outside Power and Turbine-Trip with Failure of One Diesel Generator Set to Start 55-Last 03-28-90 G

Loss of Active Core Cooling 56-Last 03-28-90 H-1 Abnormal Radioactive Liquid Waste From Plant 57 04-19-90 H-2 Abnormal Radioactive Gas Release From Plant 57 04-25-90 H-3 High Activity in the Plant 57 04-19-90

.l I Discussion of Fire 56 08-01-90 J

DELETED 05-1A-82 y

K-1 Environmental Disturbances - Earthquake 59 04-19-90 K-2 Environmental Disturbances - Tornado 56 04-19-90 FORM tol372 22 3643 l

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1 AOP-I Issue 56

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O TITLE:'

OISCUSSION OF FIRE RESPONSISLE l

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PybllC FORT ST, VRAIN NUCLEAR GENERATING STATION l

08/01/90

$9TVIC9' PUBUC 85RV6CE COMPANY OF COLORADO ABNORMAL OPERATING PROCEDURES ISSUE

, EFFECTIVE NO.

SUBJECT NUMBER DATE INTRO Abnormal Operating Procedures Introduction 55 04~19-90 A

Moisture In-Leakage 57 04-19-90 B

Reactor Scram 57 04-19-90 B-2 DELETED 01-09-88 C

Loop Shutdown 57-Last 03-28-90 0-1 Single Circulator Trip 55 04-19-90 0-2 Three Circulator Trips 54-Last C-21-90 E

Abnormal Reactor Power Change 56-Last 03-28-90 F-1 Main Turbine Emergencies 58-Last 03-28-90 F-2 Low Condenser Vacuum Turbine Trip 55-Last 03-28-90 F-3 Loss of Outside Power and Turbine Trip 55-Last 03-28-90 F-4 Loss of Outside Power and Turbine-Trip with Failure of One Diesel Generator Set to Start 55-Last 03-28-90 G

Loss of Active Core Cooling 56-Last 03-28-90 H-1 Abnormal Radioactive liquid Waste-From Plant 57 04-19

H-2 Abnormal Radioactive Gas Release From Plant 57 04-25-90 H-3 High Activity in the Plant 57 04-19-90 lI Discussion of Fire 56 08-01-90 J

DELETED 05-14-82

.K-1 Environmental Disturbances - Earthquake 59 04-19-90 K-2 Environmental Disturbances - Tornado 56 04-19-90 FORM (D)372 22 3643 a

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Page 2 of 2 OPubllC' FORT ST. VRAlh' NUCLEAR GENERATING STATION

$$tVICG' F'JeuC esRVice COMPANY OF COLORADO 08/01/90 9r ABNORML OPERATING PROCEDURES ISSUE

. EFFECTIVE NO.

SUBJECT NUMBER DATE L

Loss of an Instrument Air Header 57 04-19-90 f

M Loss of Hydraulic Power 56-Last 03-21-90 N

Loss of an Instrument Bus 56 04-19-90 P

Loss of a D.C. Bus 17 04*19-90 Q

Steam Leak cr inadvertent Lifting of Steam Relief Vaive 57-Last 04-25-90 R

Loss of Access to Control Room 54 C6-30-89 S

Loss of HVAC to 480 Volt Switchgear Room 54-Last 03-28-90 CLASS Event and Emergency Classification Overview 7

07-26-89 I

L O

FORM (D)372 22 3M3

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l Public FORT ST VRAIN NUCLEAR GENERATING STATION SOfVICO' Pueuc sanvoca comSPANY OF c0LORADO O

TITLE:'

DISCUS $10N OF FIRE RESPONSIBLE $ ?

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FORM 101372 22 3842

AOP-t I

tssue 56 Pege 2 or 7 Ill L1R1 SYMPTOM-ACisOes MATRIX i

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Page 3 or 7 (1)

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l AOP-! -

Issue 56 age 7 of 7' O$9fVICS*

PubllC FORT ST. VRAIN NUCLEAR GENERATING STATION Pusuc seemca comPAssy OF COLORADO O

l 3.0 COMMITMENTS j

s

/

l The step (s) and section(s) listed below may not be deleted

)

l without issuance of comparable controls. The procedure itself, i

l if initiated as a result of commitment corrective action, may l

not be deleted without issuance of comparable controls.

i l

3.1-Step 2.11 of A0P APP I was added in response to Commitment l-Log #CL2184S.

i l

3.2. Step 2.20 of AOP APP I was added in response to Commitment-Log #CL-18578.

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l i

O FORM (D)372 22 3M3

~

l AOP APP I Issue 56 t

Page I of 9 i

O $9fVlC9'-

Public roRT sT. VRAIN NUCLEAR GENERATING STATION PUBUC SSRVICE COROPANY OF COLORADO INTRODUCTION Firt mei nave devastating effects on the ability of the PPS and the l

operator to maintain the plant in a safe condition. Fire in an instrument cabinet, relay cabinet, or load center can have equally as devastating.an effect. The primary problem is the destruction of, instruments and control cables, controllers, interacting instrumentation and load centers. The probability that a localized fire can disable important safety functions is minimized by physical separation of cables and components in the general plant area. Most important cables physically converge to the Control Room through the Auxiliary Electric Equipment Room with power being distributed from

_J the 480 Volt Switchgear Room. For this reason, fire in the Control Room or Auxiliary Electric Equipment Room or 480 Volt Switchgear Room is potentially more threatening to safety than it would be in tha general plant area.

DISCUSSION OF SYMPTOMS 1.1 XC-45153P Pyr-A-Larm Panel Zone 1-19 1

a)

XC-45153 Zone 1 Control Room Alarm The Control Room has six fire detectors in only one zone which feeds to the Pyr-A-Larm Fire Detection i

System. These detectors provide for alarm only and no automatic Halon actions. Halon activation for the Control Room must be manually initiated.

b)

XC-45153 Zones 2. 3, and 4 Auxiliary Electric Room.

The Auxiliary Equipment Room has three fire detectors in each of two zones (in addition to one HVAC exhaust duct detector, that feeds a separate zone), which feed to the Pyr-A-Larm Fire Ditection System. The room is cross-zoned so that automatic initiation of Halon into the Auxiliary Equipment Room will only take place if both zones detect fire.

c)

XC-45153 Zones 5 and 6 480V Room The 480V Room has three fire detectors in each of two zones (zones 5 and 6) which feed to the Pyr-A-Larm Fire Detection System. The room is cross-zoned so that automatic actuation of Halon into the room will only take place if a detector in each of the 2 zones detects fire.

O I

FOAM tDI372 22 3M3 rm 9 4w

g lj

'AOP APP I

._ o 1 -

Issue 56 '

f pghllg mRT ST. VRAIN NUCLEAR GENERATING STATION "9'

$9fVlCO' Pueuc esavoce coasPANv_ or COLORADO O

d)

XC-45153 Zones 7. 8. 9. and 10 J-Wall s

Twelve detectors in the reactor building provide fire detection ability in the cable tray area north of the J Wall between level 4756' to 4881'. These provide alarm only at XC-45153.

e)

XC-45153 Zones 11 and 12_G-Wall Four detectors provide fire detection ability in the cable tray area south of the 480V and Auxiliary Electric rooms. These detectors provide alarm signals only at XC-45153 in the Control Room, f)

XC-45153 Zones 13. 14. and 15 Reactor Building HVAC Eleven detectors provide fire detection ability in various air handlers and duct work in the HVAC system. They provido alarm only at XC-45153 in the Control Room. Th3se alarms could be orought up as smoke gets into the HVAC system.

I l

g)

KC-45153 Zone 17 TSC Vent System A dry pipe deluge system protects the Technical Support Center' charcoal filter system. The fire detection system provides alarm only, and deluge system must be manually activated using HS-7922.

l h)

' XC-45153 Zone 18 Acknowledge Locker Room (RM 104)

Fire panels (XC-45391 and XC-45316)

The GAMEWELL (XC-45391) and KIDDIE (XC-45316) fire protection systems protect the Reactor and Turbine building. Refer to S0P 45-01 for location and alarm resetting instructions. The KIDDIE fire protection system provides for halon actuation in Butiding 10, all other actions for both panels are altrms only.

l i)

XC-45153 Zone 19 Control Room Ceiling Fire A fire detection system was installed above false ceiling in Control Room to provide early warning of a fire. The fire detection system provides alarm only.

FORM (D)372 22 3M3

AOP APP 1

~

L

-l Issue 56 Pghll3 FORT ST. VRAIN NUCLEAR GENERATING STATION

'9'

$9 Nice

Puouc senveos comePAmy or coLonApo 1.2' 9FP 1A Lube Res. Fire I-06H. 4-4 The feedpumps are protected by a wet pipe system with thermally actuated spray nozzles.

1.3 BFP IC Lube Res. Fire 1-06H. 5-4 The feedpumps are protected by a wet pipe system with thermally actuated spray nozzles.

1.4

& d Power Supply Units Fire I-06H 5-3 A wet pipe system protects the hydraulic power units. The two loops are fed from different risers of the 45 system.

There is no loop identification in the fire alarm circui try.

1.5 4e Cire Turntable Res, Fire 1-06H. 4 2 A wet pipe system protects the circulator turntable'.

Thermally actuated spray nozzles are located above and below the turntable.

1.6 4160/480V XFMR 1, 2. 3 Sudden Press. I-061 3-3 The sudden pressure relays on 4160/480 Volt Transformers 1, 2, and 3 have alarm capability only. Send operator to investigate.

1.7 480V L.C. Transform Fire I-061 3-4 The firewater deluge system for 480 Volt load Center Transformers are common on all three transformers. Send operator to investigate for fire.

1.8 Fire Induced 10FC A major fire could result in an interruption of forced j.

cooling.

1.9 Turbine Lube Oil Res. Room Fire 1-06H, 4-5 An Automatic Deluge (Dry Pipe) type system protects the turbine lube oil reservoir room. High temperature switches in the room actuate the deluge system.

Fog type spray nozzles are arranged to completely blanket the oil tank. Actuation of the deluge system also causes the alarm.

1 omoim.nt

'-l AOP APP I Issue 56

'9'

&Public FORT ST. VRAIN NUCLEAR GENERATING STA?lON c,

WF Service

pueue aanvies coespan or cos.ORADO 1.10 Turbine tube Oil Storage Room Fire I-06H, 3-5 An automatic deluge (dry pipe) type system protects the turbine lube oil storage room. High temperature switches in the room actuate the deluge system. Fog type spray nozzles are arranged to completely blanket the oil tanks.

Actuation of the deluge system also causes the alarm.

1.11 Reactor Plant Exhaust Filter Fire 1-06H. 4-7 A deluge (Dry Pipe) type system protects the reactor plant exnaust filters. The primary purpose of the deluge system is to extin uish or prevent the ignition of the charcoal i

beds. 200 F temperature switches in the filter units actuate the deluge system and the alarm. The particular filter burning must be determined by local Joservation, as the alarm is common to all three filters.

1.12 Hydrogen Seal Oil Unit Fire I-06H. 3-4 The hydrogen seal oil unit is protected by a wet pipe system with thermally actuated nozzles.

1.13 Aux Boiler Room Fire 1-06H. 3-3 A wet pipe system with thermal actuated spray nozzles protect she aux botier room. The alarm is actuated on flow in the fire water piping into the room.

1.14 Standby Gen IA Room Fire I-06H, 1-4 In the event of fire in either diesel generator room, the C0: system has the capability of total flooding of either or both rooms. The total flooding can be actuated manually or automatically by the two heat-actuated tripping devices in each room above each of the diesel engines.

There are three CO: discharge nozzles in each room which discharge at a rate of 200 lb/ min to fill the 8500 cu. ft, free room volume to a 0.062 lb.cu.f t, daign C0 concentration. A horn sounds when 00 is about to be discharged into a diesel generator room. A signal from the CO: control system closes pneumatically operated fire dampers in the ventilation supply ducts to each room and in the return ducts to each room.

O I

FORM 101:72 22 300

l AOP APP 1 h

Issue 56 I'

FORT ST. VRAIN NUCLEAR CENERATING STATION "9'

OPublic

$9fVICO' Puauc senvece conspAmy or coe.onADO 1.15 Standby Gen IB Acom Fire I-06H. 2-4 l

In the event of fire in either diesel generator room, the CO: system has the capability of total flooding of either or both rooms. The total flooding can be actuated '

manually or automatically by the two beat-actuated tripping devices in each room above each of the diesel engines.

There are three CO discharge nozzles in each room which discharge at a rate of 200 lb/ min to fill the 8500 cu. ft.

free room volume to a 0.062 lb.cu.ft. design C0, concentration. A horn sounds when CO: is about to be discharged into a diesel generator room. A sigr.al fron.

the T control system closes pneumatically-optrated firt dam;-rs in the ventilation supply ducts to each room anu in the return ducts to each room.

1.16 Reserve Aux Transformer Fire 1-06H. 2-5 Individual automatic water deluge systems serve to protect the main power. transformer, the unit auxiliary transformer, the reserve auxiliary transformer, turbine lube oil storage rum, and turbine lube oil reservoir room. The automatic actuation of any deluge valve simultaneously sounds an clarm near the fire hazard area and in the control room, actuates a red flashing light mounted on or near the associateo deluge valve, and automatically starts both fire water pumps. In addition to each of the above systems being automatically operated, two manual control stations are provided for each system:

one located v.ar the firk hazard area, and one located in the control room.

The reserve auxiliary transformer fire protection system is automatically actuated by any one of four devices:

ite i

" sudden pressure" relay, its rate-of-temperature-rise detectors, operation of its differential auxiliary trip relay, or its neutral ground overcurrent trip relay.

O FORM (D)372 22 3M3

n' 1.

AOP APP 1 Issue 56 hPublic FORT m'. VRAIN NUCLEAR GENERATING STATION "I'

WGF Service *-

Pusue esavses coasPAM OF COLORADO Main Power ar.d UAT Fire I-MH 1-$

1.17 s

Individual automatic water deluge systems serve to protect the main power transformer, the Unit Auxiliary Transformer, the Reserve Auxiliary Transformer, turbine lube oil storage room, and turbine lube oil reservoir.

room. The automatic actuation of any deluge n1ve simultaneously: sounds an alarm near the fire hazard area in the Control Room, actuates a red flashing light inc nted on or near the associated delvge valve, and automatically starts both fire water pumps. In addition to each of the above systems being automatically operated, two manual control stations are provided for each system: one located near the fire hazard area,and one located in the control room, The " common" main transformer and the Unit Auxiliary Transformer deluge systems are botn automatically actuated by any one of five devices: the associated transformer

" sudden pressure" relay, the transformer differential trip relay, the tran.*former neutral ground overcurrent trip relay, the operation of the generator and mtin transformer differential trip relay, or by the associated rate-of-temperature-rise detectors of each tran.smer.

The main transformer and Unit Auxiliary Transformer deluge O

system tripping devices are interlocked so that when one deluge system is actuated it automatically actuates the deluge system of the other system.

1.18 Report of Fire or Smoke.

Fire or smoke reported by site personnel.

1 e

O 101372 22 3843

l AOP APP I

!ssue 56 OI 9 FORT ST. VRAIN NUCLEAR GENERATING STATION "9'

/

Public

' $9fVICO' Pusuc sanvoca COMPANY OF COLORADO DISCUSSION OF OPERATOR ACTION j

2.1 Terminate defueling activities.

l Notify Fuel Deck to terminate defueling activities and I

close all openings to PCRV.

2.2 Dispatch operator to investigate.

4 I

This is done tv verify actual fire if other personnel have not already reported it.

2.3 If fire confirmed, sound fire alarm and announce location Sound emergency fire alarm on 1-09 for approximately 5 seconds. Announce location and type of fire and sound alarm for approximately 30 seconds. These actions alert site personnel tc p*oceed to their emergency stations and y

summons the fire brigade to the scene of the fire, in accurdance with Administrative Procedure G-5, Personnel

=

Emergency Response.

N_0TE : If either the Access Control Bay roof and/or the Reactor Building roof hose stations are required, Immediately initiate a manual firewater pump start. This action will supply these stations as they are located above the firewater storage tank.

2.4 Establish reauired communications.

This provides a link with personnel at the fire scene for continuing assessment of fire and plant status.

2.5 If needed, call for outsioe assistance.

F E-'

This will provide extra assistance as required. Outside assistance is prelided by the Platteville Volunteer Fi-e Department (refer to Outside Assistance in RERP phor"s lists in the RERP Implementing Procedures).

l 2.6 Proceed to OPOP III.D for recovery from 10FC.

1 The OPOP will identify the steps needed to restore forced I ll cooling.

A 2.7 If the fire "ay affe t, or is affecting, safe l

operation,ter.ninate def ueling activities.

m Fire in, or affecting, the plant centrol panel, instrument cabinets or load centers nay have potentially devastat'ng i

effects on the continued safe defueling activities.

9 FORM (D) 372 -22 3H3

(

l A0P APP I 4

Issue 56

'9'

&Public FORT ST. VRAIN NUCLEAR GENERATING STATION W Service

PUBUC SERWCE COMPANY OF COLORADO O

2.8 Ensure fire water pump start.

This insures that a continuous supply of fire water will be available for firefighting and other possibie plant uses.

2.9 Ensure CAS reports personnel accountability.

Initiate search.if necessary.

This will insure that all personnel are safe and accounted for or whether a search for missing persons needs to be started.

2.10 Ensure discharge of the halon system if halon protected.

This will insure that the fire extinguishing agent (Halon 1

1301) is in the room to extinguish the fire.

2.11

1. - 3.1*#* If, fire involves a Five Train, ensure other Fire Train is protected.

If a fire involves a Fire Train, ensure Fire Brigade Leader provides instructions to Fire Brigade to protect I

redundant Fire Train

_fer to ACM Procedure 50P 48-01.

l 2.12 [f,necessary, ref System 48 provides an alternate means of cooling the j

reactor in the event of a major fite in congested cable l

areas.

i

)

2.13 If_'_ ire cannot be manually extinguished - manually l

discharge the halon system.

l l

This provides the opportunity for Contrul Room personnel h

to decide if Halon actuation is needed. Manual fire j

fighting may bring tre fire under control.

l 1

l 2.14 Operators in the Contro', Room don fresh air masks.

{

This must be done for both smoke contamination and Halon.

)

The masks must be put on before the Halon is manually actuated.

l 2.15 Ensure HVAC isolation.

L The HVAC of affected rooms of the three room complex will isolate automatically, on the actuation of the Halon system, or manually. This assures that an adequate Halen l

l concentration (3% to 5%) can be maintained in the room.

000r opening and closing into the affected room should be

[

9-1imited.

1 1

FORMIDIJ72 22 3843 l

1 l

w AOP APP I A_

1.I fa Issue 56'.

Page.9;of 9-Public FORT ST. VRAIN NUCLEAR GENERATING ST TION I

h

$9fVICO' Pusuc sanvece comPAmr or COLORADO ci l'

l 2.16' If'the' Control Room becomes uninhabitable, evacuate per l

AOP-R.

These actions prepare the plant for. maintaining shutdown conditions. Plant control systems should function I

normally to maintain cooldown.

If they do not, sufficient l

instrumentation is provided at the I-49 panel of the 480 l

Volt Switchgear Room to allow adequate local control to l

maintain decay heat removal, l

l 2.17 Put the unaffected' filteri into service. Isolate the-

-affected filter.

Two 50% capacity filters must be in service. The affected filter should be removed from service to ensure that the s

filters in service are able to fulfill their design function. Local observation must be used to determine the affected filter.

l 2.18 -Ensure operability of the other diesel generator-set.

'If one of the diesel generator sets is affected by fire, i

~

l the other set must be proven operable.

l.

2.19 Ensure emergency dietels start and load if 480V feed is lost.

i If the essential 480V busses lose-their supply, the diesel should start and load automatically, i

[-

2.20

1. - 3.2*#*

Swap suction of breathing air compressors.

In the event of fire or smoke in the area of breathing air compressors, swap suction to TSC per A0P 45-03, r

4 O

1 FORM (01772 22 3M3

.. ~

,. -

ML20058N107

Text

SUBJECT:

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