ML20052E313
| ML20052E313 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/20/1982 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20052E302 | List: |
| References | |
| PROC-820420-01, NUDOCS 8205100344 | |
| Download: ML20052E313 (27) | |
Text
- _ _ _ _
L'IP 300 EMERGENCY MEASURES 300-1 Initial Notifications and GSEP Responses (Primary Responsibility
' Station Director)
Rev. 3 1/82 300-C1 Niicleaf AccidenFReforting Systen Form
~
(Primary Responsibility - Station Director)
Rev..2 5/81 300-2 On-Going Emergency Communications (Primary Responsibility - Station l
Director)
Rev.1 3/81 I
i 300-3 Assembly and Evacuation of Personnel.
(Primary Responsibility - Operations Director)
Rev. 2 h/82 300-4 Emergency Dose Limits and Radiological Controls for Rescue and Recovery Operations (Primary Responsibility - Rad / Chem Director)
Rev. 0 7/80 300-5 Emergency Treatment of Injured Personnel (Primary Responsibility - Operations Director)
Rev..1 10/80 300-6 Survey of Injured Personnel (Primary Responsibility - Rad / Chem Director)
Rev. 0 7/80
- 300-7 Personnel Decontamination (Medical -
Decontamination Area) (Primary Responsibility
- Rad / Chem Director)
Rev. 0 7/80 300-8 Post-Accident Sampling of Primary Containment Atmosphere (Primary Responsibility - Rad / Chem Director)
Rev. 1 10/80 300-9 Post-Accident Sampling of Reactor Coolant (Primary Responsibility - Rad / Chem Director)
Rev. 2 1 0/81 300-10 Post-Accident Sampling and Release Rate Detennination of Radiciodines and Particulates (Primary Responsibility - Rad / Chem Director)
Rev.1 10/80 300-11 Post-Accident Noble Gas Release Rate Detennination
- 10/80 (Primary Re:ponsibility - Rad / Chem Directc;-)
Rev. 1 300-12 Initiation of Environmental Monitoring Activities by the Rad./ Chem. Director (Primary Responsibility - Rad./ Chem. Director)
Rev. 0 7/80 300-13 Rad./ Chem. Technicians Actions at Hospital j
(Primary Responsibility - Rad./ Chem. Director)
Rev. 0 7/80 i
I I
APR201982 8205100344 820504 i
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300 EMERGENCY MEASURES (Cont'd) 300-14 Estimation of Off-site Dose from an Unplanned e
Release of Radioactive Effluents j
(Primary Responsibility - Rad./ Chem. Director)
Rev. 0 7/80 300-15 Deployment of the Eberline S#i-2 Stabilized Assay
'i Meter (Primary Responsibility - Rad./ Chem.
- 1 Director)
Rev.1 3/61 d
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APR2 01982 o
t
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EP!P 300-3 Revision 2 ASSEMBLY AND EVACUATION OF PERSONNEL (Primary Responsibility - Operations Director)
A.
SCOPE This procedure describes local area evacuation, Assembly Areas, the use of the assembly siren and methods for evacuating.
B.
POLICY AND METHODS NOTE During an emergency situation, an assembly and evacuation of non-essential personnel should be considered by the Station Directer l
whenever:
1)
It is detennined that projected doses should be avoided by a relocation of personnel; or 2)
A Site or General Emergency is declared; or 3)
Other dangers exist that present a threat to the safety of on-site personnel as detennined by the Station Director.
1.
Evacuation of local areas of the plant.:
NOTE To correct an audibility problem encountered in evacuation of per-sonnel from high-noise areas, flashing evacuation lights have been installed in all three Diesel Generator Rooms.
a.
Evacuation of specific areas within or around the plant may be ordered by the Shift Engineer or the Station Director when it is felt that existing or developing conditions may result in a potential hazard to the health or safety of individuals in the area. These conditions include, but are not limited to:
(1) Sudden increase in dose rate due to radioactive j
source.
(2) Sudden increase in concentrations of airborne radioactivity due to off gas, steam leak or pro-cess line open.
APPRos/ED 1 of 9 g *20'82.
0.0.S.R.
EPIP 300-3 Revision 2 (3) Fires, explosions or release of toxic chemicals that endanger personnel health or safety.
(4) Radiation criticality alarms in the Unit 2 or Unit 3 Reactor Building, 517' eley., 613' elev. or the Unit 1 New Fuel Vault.
(5) Any other event where evacuation is deemed necessary by the Station Director or his designated alternate.
b.
Once evacuation of the area is deemed required, notify the affected individuals by station P.A. system, local alann or dispatching an individual to remove personnel.
c.
Initiate steps for corrective action. This may be ini-tieting the fire brigade, isolating equipment from ser-vice or coordinating with Radiation Protection to re-move the radioactive source.
2.
Assembly.
NOTE Notify local agencies, i.e.,
Will County Sheriff and Grundy County Sheriff prior to or as soon as practicable when using the plant siren.
The purpose of the Assembly Areas shown on the attached Fig-ure 1 is to assemble personnel in well-shielded areas for protection, against direct radiation hazards produced by emer-gency conditions. Conditions such as loss of water from spent fuel pools, filling the sphere with steam and noble gases or a Loss of Coolant Accident would produce direct radiation hazards of such magnitude to be immediately dan-gerous to personnel.
In case of fire in an Assembly Area, consideration must be given to using alternate assembly locations such as the Main-tenance Shop. If an alternate Assembly Area is to be used, repeated PA announcements to that affect should be made.
Personnel assigned to take charge of each Assembly Area are as follows:
J Assembly Area 1 - Master Mechanic, Master Electrician or a designated alternate.
Assembly Area 2 - Security guard dispatched by the Security Shift Supervisor.
APPROVED 2 of 9 62
.u.0.S.R-l
EPIP 300-3 Revision 2 Assembly Area 3 - Security guard dispatched by the Security Shift Supervisor.
Assembly Area 4 - Training Supervisor or an alternate from the Training Staff.
NOTE Elevated concentrations of air-borne radioactive materials, such as experienced during off-gas sys-tem detonations, are not immedi-ately dangerous to personnel. Thus, the assembly area siren should not be used for airborne conditions unless they are accompanied by a condition that would produce a direct radiation hazard.
a.
Whenever the need for assembly is identified, a Nucle-ar Station Operator will initiate the assembly siren (2 minute continuous blast).
b.
Personnel inside the security fence will report to Assembly Area 1, 2 or 3 (as described below), which-ever is closest:
(1) Assembly Area 1 is the corridor between the Unit 2 and Unit 3 Turbine Bailding Trackways; (2) Assembly Area 2 is the Maintenance Warehouse lo-cated at the west security fence; (3) Assembly Area 3 is the area directly east of the Chenical Cleaning Building located at the eastern edge of the site.
NOTE Nonnal clothing removal procedures shall be waived. Personnel wear-ing one layer of protective cloth-ing shall remove only gloves and protective footwear when exiting from the radiation zone. Person-nel wearing two layers of pro-tective clothing, as required in the canals or other highly con-l taminated areas, shall remove l
gloves, protective footwear and the outer layer of protective footwear and the outer layer of APPROVED APR 20'82
~
3 of 9 D.O.S.R.
EPIP 300-3 Revision 2 protective clothing. Hand and shoe counts and required person-nel surveys should be amitted.
Personnel exiting from radiation zones wearing protective clothing during an assemb'; should make every reasonable ei fort to avoid contaminating equipment, walls, floors and other personnel.
c.
Operations Depsrtment personnel that are on shift, whose nonnal station is in either the Control Room or the Shift Engineers' office, shall assemble in the Control Room. Other Operations Depart 2nent personnel shall as-semble in the Operational Support Center (OSC), which is located in the Rad./ Chem. Foreman's office.
d.
Rad./ Chem. Technicians and Rad./ Chem. Supervision will obtain Radiation Detection Instruments and assemble in the OSC.
e.
Fuel Handling and Fuel Handling Supervision will take the following actions:
(1) If no local (Fuel Handling Area) High Radiation Alann is sounded:
(a)
If fuel is not in the process of being trans-ferred, they will immediately report to the i
nearest Assembly Area.
(b)
If fuel is in the process of being transferred with a crane, move the fuel element to the nearest empty fuel vault, fuel pool or fuel cask location as applicable; renove the crane hook from the element and immediately report to the nearest Assembly Area.
(c) If fuel is in the process of being transferred with the fuel granple, whether in the spent fuel pool or the Reactor, move the fuel ele-ment to the nearest enpty fuel pool or re-actor location. Set and release the element from the grapple and immediately report to the nearest Assembly Area.
(2) If a local (Fuel Handling Area) High Radiation Alann is sounded and this high radiation condition is the cause of the assembly siren sounding, they will immediately report to the nearest Assembly APPRO G N
4 of 9 u.0.S.R-I
EPIP 300-3 Revision 2 Area using shielded corridors for protection from radiation.
f.
Station Directors shall report to the Technical Support Center (TSC).
g.
Personnel outside the security fence will report to Assembly Area 4 which is the cafeteria on the first floor of the Administration Center.
h.
The Station Security Director has the responsibility for the accountability of all personnel within the pro-tected area boundary. At the initiation of the assembly siren, the ranking Security Shift Supervisor on site will proceed to the Main Assembly Area east-end to es-tablish the accountability of personnel reporting to the Main Assembly Area. Additional guards are dis-patched to the remaining Assembly Areas. These guards establish communications with the Station Security Di-rector (Security Shift Supervisor during off hours) for purposes of accountability. The Security Shift Super-visor will establish contact with the Station Security Director (Shift Engineer during off hours). During "nomal working hours", the Master Elec./ Mechanic will tabulate by department and individual Foreman's group all accountability. of personnel at the Assembly Area and relay that infomation to the Security Shift Super-visor. (Personnel not accounted for will be traced via Security, logs, patrols and camputer). During other than
" normal working hours" (8:00 to 4:30 Monday - Friday),
the Security Shift Supervisor will tabulate personnel accountability.
Security mobile patrols will direct personnel in the Protected Area to designated Assembly Areas and can assist in the location of unaccounted personnel.
Security guards are also available (if necessary) to locate missing persons. The ranking Security Shift Supervisor will then notify, prior to the 30 minute
" mark" (30 minutes after siren initiation), the Station Security Director on accountability status.
Accountability for the Control Room, OSC and TSC per-sonnel will be handled by the Station Security Direc-tor from the TSC, working with the Operations Director and the Rad./ Chem. Director.
Attached is a sample of the Assembly Checklist that is used to document department accountability.
APPROVED APR 20'82 5
D.O.S.R.
EPIP 300-3 Revision 2 1.
Personnel will remain in the Assembly Area until the "ALL CLEAR" is sounded. At the first opportunity af ter the "ALL CLEAR", personal contamination checks should l
be made and the worker should return to his work as-signment. Personnel wearing protective clothing wil!
be responsible for notifying Radiation Protection of-i the path they took from their work area to the Assembly L
Area.
When the "ALL CLEAR" is sounded, Fuel Handling will con-tact Radiation Protection, assure that the high radiation condition has been teminated, return to work and ver-ify fuel element identification before completing the fuel moves which were in progress.
l 3.
Site Evacuation.
NOTE The Site Evacuation section of this procedure presumes an assembly has already been effected.
a.
The Station Director has the authority to evacuate site personnel. The Operation, Technical, Security and Rad./ Chem. Directors should be consulted before evac-uation takes place. The following are examples of con-ditions that have the potential to cause a site evac-uation:
(1) Site Emergency (GSEP 5.4).
(2) General Emergency (GSEP 5.5.).
(3) Natural Disasters (tornados, fires, etc.) that endanger on-site personnel health cr safety.
(4) Any event deemed by the Station Director to re-quire an evacuation.
b.
Personnel essential in controlling the emergency should be assigned to the Control Room, the TSC or the OSC.
c.
Additional support to accomplish the evacuation (trans-portation, bioassay equipment and additional personnel) may be obtained by coordinating with the Command Center Director or the Recovery Manager.
g d.
If evacuation is due to radiological hazards, have the Rad./ Chem. Director dispatch Radiation Protection per-sonnel to detemine the lowect dose pathway to evac-uate personnel. There are Ne main evacuation path-APPROVED 6 of 9 g 20T2.
D.O.S.R.
_~
EPIP 300-3 Revision 2 ways available (see Figure 1).
(1) South - via the main entrance or the security gate.
(2) West - out the west end of the site via the Unit 3 i
Turbine Building, if possible.
e.
Consult the Rad./ Chem. Director and determine if in-dividuals need to assemble off site for monitoring or bioassay tests. Off-site Assembly Areas include the GSEP Trailer Area, the G.E. Fuel Reprocessing Plant, 1
LaSalle Station and/or Braidwood Station.
NOTE If off-site assembly is detennined to be necessary, consult with the Station Security Director and con-sider blocking entrances and exits to parking lots to prohibit per-sonnel fram leaving without Rad-iation Protection clearance.
f.
Determine which work groups or individuals are non-essential and should leave the site.
g.
Appoint individuals to direct and lead the site evac.
uation. If the evacuation is due to radiation, Rad-iation Protection personnel should be assigned to help direct the evacuation to verify the lowest dose path-way is followed and a survey of personnel is accom-plished at the Assembly Area as required.
C.
REFERENCES i
None.
l APPROVED E
7 of 9 D.O.S.R..
EPIP 300-3 Revision 2 ASSEMBLY CHECKLIST DEPARTMENT ACCOUNTABILITY ALL ACCOUNTED FOR UNACCOUNTED BADGES 1.
Mechanical Maint.
2.
Electrical Maint.
l 3.
Instrument Maint.
4.
Office Clerical 5.
Administration 6.
Fuel Handlers 7.
Station Men - Janitors 8.
Tech. Staff 9.
Quality Control
- 10. Quality Assurance
.1.
Operating
- 12. Rad. Dept.
- 13. Radwasta
- 14. Security
- 15. Training
- 16. Storeroam
- 17. Station Const. (Contractors)
- 18. 0AD
- 19. Substation Const, i
- 20. Visitors APPe0 @
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I FIGURE I D U 300-3
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i EPIP
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200 - Emergency Conditi...
i 200-T1 Classification of GSEP Conditions j
(Primary Responsibility - Station Director)
Rev. 3 ' 3/82 200-T2 Table of I-131 Equivalents For Tha Principal j
Iodine Isotopes On A Reactor Core Rev. 0 7/80 i
200-1 Declaration of GSEP Condition For Gaseous j
and Liquid Effluent Releases (Primary i
Responsibility - Operations Director)
Rev. 0 7/80 l
l 200-2 Classification of an Incident Involving Hazardous Material (Primary Responsibility -
l Station Director)
Rev. 0 7/80 1
200-3 Criticality Accident in a Special fluclear Material Area (Primary Responsibility -
Operations Director)
Rev. 0 7/80 200-4 Fire Fighting (Primary Responsibility - Operations Director)
Rev. 1 9/80 200-5 Security Threat (Primary Responsibility - Operations Director)
-Rev. 0 7/80 200-6 Corrective Actions Following An Oil Spill (Primary Responsibility - Operations Director)
Rev. 1 1 2/81 200-7 Operation During Tornado or Sustained Wind Conditions (Primary Responsibility - Operations Director)
Rev.1 1/82 200-8 Operation DJring Earthquake Conditions (Primary Responsibility - Operations Director)
Rev. 0 7/80 200-9 Dresden Dam Failure Rev. 0 7/80 (Primary Responsibility - Operations Director) 200-10 Probable Maximum Flood of Unit 1 (Primary Responsibility - Operations Director)
Rev. 0 7/80 200-11 Probable Maximum Flood of Unit 2 and 3 (Primary Responsibility - Operations Director)
Rev. O S/80 200-12 Area High Radiation (Primary Responsibility - Operations Director)
Rev. 0 7/80 200-13 High Airborne Activity
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(Primary Responsibility - Operations Director)
Rev. 0 7/80 l
APR 2 01982
l.
r EPIP
?
200 - Emergency Conditions (cont'd)
~
lj 200-14 High Radioactive Surface Contamination (Primary Responsibility - Operations Director)
Rev. 0 7/80 11 200-15 Emergency Procedure for Obstruction Lights
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(Primary Responsibility - Operations Director)
Rev. 0 9/80 t
f 200-16 IMUSED N,13GER_...,,
200-17 UNUSED NUMBER 200-18 UNUSED NUMBER 200-19 Unit 1 Control Room Evacuation (Primary Responsibility - Operations Director)
Rev. O 9/80 200-20 Control Room Evacuation / Safe Shutdown (Primary Responsibility - Operations Director)
Rev. 1 h/82 I
m t
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I s
APR 2 01982 i
l
EPIP 200-20 Revision 1 CONTROL ROOM EVACUATION / SAFE SHUTDOWN (Primary Responsibility - Operations Director)
I A.
PURPOSE The intent of this procedure is to detail the method for bringing the Reactor to and maintaining the Reactor in a Hot Shutdown con-di tion. The procedure assumes evacuation of the Control Roan or a loss of control capability fran the Control Room. Neither the debilitating of renote control capability nor the evacuation ini-tiation event are postulated to occur simultaneously with other accidents, events or phenomena, such as a design-basis accident or a loss of off-site power. Credit is assumed for reactor trip and verification of control rod insertion in the Control Room, even for an event requiring evacuation.
B.
REFERENCES 1.
Fire Protection Safe Shutdown Analysis, Dresden Station, Units 2 and 3, June, 1978.
2.
Fire Protection Safe Shutdown Analysis, Supplement 1. Cold Shutdown Analysis, Dresden Station, Units 2 and 3, January, 1980.
C.
PREREOUISITES 1.
Keys for High Radiation Areas.
2.
Radios for communications.
3.
Protective clothing and mask for entering the Isolation Con-denser Valve Room, if necessary.
D.
PRECAUTIONS None.
E.
LIMITATIONS AND ACTIONS None.
F.
PROCEDURE 1.
Before leaving the Control Room and upon orders fran the Shift Supervisor:
a.
MANUALLY SCRAM the Reactor.
b.
Leave the Mode Switch in RUN so that the Reactor will isolate on less than 850 psig in RUN.
I APPROVED APR 20'82 1 of 14 D.O.S.R.
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~
EPIP 200-20 Revision 1 c.
TRIP the Control Rod Drive (CRD) Pumps.
d.
TRIP the Turbine.
2.
The Shift Engineer will take his log and report to the Tech-nical Support Center to act as Station Director. He will:
a.
Make initial Generating Station Emergency Plan notifi-cations.
b.
Initiate a damage control party to combat the problem in the Control Room and to assess damage, c.
Dispatch an Operator to the Cribhouse to verify that fire system pressure is nomal and that the diesel-driven Fire Pump has started, if required.
3.
The Unit Shift Supervisor will pass out attachments from this procedure and will dispatch personnel as follows:
a.
The Unit Nuclear Station Operators (NSO's) to the Re-actor Building Second Floor (Instrument Racks 2202-5 and -6) with a full copy of this procedure.
b.
An additional Operator with Attachment 7 to the Reactor Building Second Floor / Isolation Condenser Areas or Con-densate Transfer Pump Areas as needed.
c.
An additional Operator with Attachment 8 to the CRD Pump Areas when needed, d.
An Equipment Operator or NSO with Attachments 3, 4, 5 and 6, if local start of the Diesel Generator and local operation of feed breakers becomes necessary to provide continuity of power sources.
4.
The Shift Supervisor shall establish the Reactor Building Second Floor as the control center for the remainder of this procedure.
5.
OPEN manual Isolation Valves for isolation condenser gauge glass (Reactor Building Fourth Floor). MONITOR shell side water level for indication of decreasing water level.
NOTE If nomal water level is present, water level will be out of sight high. Consider steaming without fill until level indication can be verified in the sight glass.
j This should take =20-30 minutes. APPROVED APR 20%2 2 of 14 0.0.S.R.
EPIP 200-20 Revision 1 6.
If Isolation Condenser Vent Valves A0-1301-17 and -20 have not closed, CLOSE the Air Supply Valve to the Vent Valves or CLOSE manual Isolation Valve 1301-16 (Reactor Building Fourth Floor).
7.
OPEN and THROTTLE Isolation Condenser Outboard Condensate Return Valve MO-1301-3 to control cooldown. Refer to At-tachment i for a table of Saturation Pressure versus Satura-tion Temperature.
8.
MONITOR reactor vessel water level and pressure by monitoring Instrumentation on Instrument Racks 2202-5 or -6 (Reactor Building Second Floor).
9.
Initiate fill of the Isolation Condenser by opening Contam-inated Demineralized Water Supply Valve M0-1301-10 and op-erating the Condensate Transfer Pumps as necessary.
NOTE Clean demineralized water or fire system water may be used if avail-able.
10.
The Shift Supervisor should verify isolation condenser oper-ation by:
a.
Observing local Flow Indicators dPIS 1349-A and B or dPIS 1350-A and B on the Reactor Building First Floor, or by, b.
Dispatching someone to observe steam venting fram the shell side of the Isolation Condenser (south side of the Reactor Building).
c.
If the Isolation Condenser is not operating or has iso-lated, refer to Attachment 2.
11.
THROTTLE Contaminated Demineralized Water Supply Valve M0-1301-10 or locally START and STOP a Condensate Transfer Ptsnp (Attachment 7) to maintain isolation condenser water level within the indicating range of the isolation condenser gauge glass.
12.
Locally START and STOP a CRD Pump ( Attachment 8) to maintain reactor water level between +10 inches and +40 inches.
I NOTE Reactor Feed Ptsnps should have added water until tripped at +55 inches. The CRD Ptsnp need not gg APR 2012 3 ' 4 0.0.S.R.
EPIP 200-20 Revision 1 be started until reactor water level is below +40 inches but should be started before level reaches +10 inches.
13.
Continue to cool down, depressurize and maintain reactor water level with the Isolation Condenser and the CRD Pumps.
14 When the Control Room is again available, re-establish con-trol in the Control Room and proceed to Cold Shutdown with nomal shutdown procedures.
G.
CHECKl.ISTS hone.
H.
TECHNICAL SPECIFICATIONS REFERENCES None.
e 9
' APPROVED e 2052 D.O.S.R.
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i EPIP 200-20 Revision 1 ATTACHMENT 1 C00LD0WN TABLE Saturation Pressure Saturation Temperature 1000 psic 546' F 950 psig 540' F 900 psig 533* F 850 psig 527' F 835 psig 525' F 800 psig 520" F 750 psig 513' F 700 psig 505' F 665 psig 500* F 650 psig 498* F 600 psig 489* F 550 psig 479a y 525 psig 475' F 500 psig 470" F 450 psig 459' F 408 psig 450* F (1 hr) 400 psig 448" F 350 psig 435* F 311 psig 425' F 300 psic 423* F 250 psig 404' F 232 psig 400* F 200 psig 392" F 169 psig 375' F 150 psig 366" F 120 psig 350* F (2hr) 100 psic 338" F 81 psi 9 325' F 52 psig 300" F 50 psig 296" F 30 psig 275' F 25 psig 254" F 14 psig 250' F (3hr) 4 psig 225" F APPROVED l
APR 20'82 D.O.S.R.
5 of 14
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EPIP 200-20 Revision 1 ATTACHMENT 2 ISOLATION CONDENSER NOT OPERATING OR ISOLATED 1.
Control center personnel will observe the isolation condenser steaming operation from outside the Reactor Building. Should the Isolation Condense,r not be initiated or stop after initiation, as evidenced by steam exiting the vent pipe, action must be taken to place it in service.
2.
VERIFY that Isolation Condenser Outboard Valves MO-2(3)-1301-2 and
-3 OPEN by visually checking valve position (Isolation Condenser Pipeway 2nd and 3rd elevation). If the valves are closed, RACK OUT the feed breakers and MANUALLY OPEN the valves after verifying no isolation condenser line breaks have occurred.
3.
Should the Isolation Condenser still not be operational, it must be assumed that the Isolation Condenser System isolated on high flow. Should this be the case, it will be necessary to lift leads and install jumpers at the feed breakers to allow the valves to be opened.
a.
Locate the feed breakers for Isolation Condenser Inboard Valves MO-2(3)-1301-1 and -4 at conpartments J3 and J4 of MCC 28-1 (conpartnents H1 and H2 of MCC 38-1).
CAUTION Once the lead from tenninal 8A is lifted and the Isolation Condenser Inboard Valves opened, Auto Iso-lation is defeated.
b.
Lift the lead at tenninal 8A in the breaker comprtment to de-energize CLOSE coil, [ Prints 12E2507(12E3507),12E2507A (12E3507A),12E2674E(12E36740)].
CAUTION The appropriate Isolation Condenser Inboard Valve should open immedi-ately upon jumpering tenninals 1 and 3A.
c.
Jumper tenninal 1 to 3A in the breaker canpartment to energize OPEN coil.
4.
After the Isolation Condenser Inboard and Outboard Valves are opened it may be necessary to open manual Isolation Condenser Vent Valves 2(3)-1301-14 and -15 to vent any noncondensible gases from the Isolation Condenser. CLOSE the Vent Valves after a few min-utes of venting.
APPROVED 6 of 14 APR 20'82 u.0.S.R.
m.
EPIP 200-20 Revision 1 ATTACHMENT 2 (Cont'd.)
5.
After all attempts to initiate the Isolation Condenser fram out-side the Control Room have failed, it may be necessary to enter the Control Room with supplied air if conditions pennit.
1 i
i APPROVED en 20112 0.0.S.R.
7 of 14 4
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t EPIP 200-20 Revision 1 ATTACHMENT 3 LOCAL CONTROL OF DIESEL GENERATOR BREAKER TO BUS 1.
VERIFY that all feed breakers to the associated bus are OPEN.
2.
Verify that all ammeters for feed breakers indicate zero amps.
3.
OPEN the Safe Shutdown Control Room Disconnect Switches at the diesel generator breaker cubicle.
4.
START the Diesel Generator per Attachment 4 5.
Verify that the Diesel Generator is at speed and voltage.
6.
Plug the safe shutdown pushbutton station cable into the safe shutdown receptacle on the diesel generator breaker cubicle.
7.
CLOSE the diesel generator breaker to bus.
8.
Check diesel generator voltage and frequency at the Diesel Generator Metering and Relay Panel.
9.
OBSERVE diesel generator voltage and frequency as equip-ment on the bus is started.
- 10. OBSERVE diesel generator load restrictions as the diesel engine is loaded.
.f
' APPROVED APR 2012 f
8 of 14 D.O.S.R.
1
EPIP 200-20 Revision 1 ATTACHMENT 4 (LOCAL MANUAL START) 0F DIESEL GENERATOR NOTE If power is lost to Bus 23-1(33-1) or Bus 24-1(34-1), the Energency Diesel Generator should auto start and its output breaker should auto close to its associated bus.
CAUTION Engine Start Selector Switch at the Engine Control Panel must be in the AUTO position in order for the diesel generator field to flash.
1.
VERIFY that all feed breakers to the associated bus are OPEN.
2.
VERIFY that the Engine Start Selector Switch at the Engine Con-trol Panel is in the AUTO position.
3.
At the diesel engine governor, verify that the governor speed droop is set to 5.
4.
START the diesel engine by momentarily holding the Auto-Start Re-lay (ASR) at the associated 4Ky bus.
NOTE If the ASR does not start the diesel engine, PRESS the local start pushbutton on the Engine Control Panel.
5.
VERIFY that the diesel generator room vent fan STARTS.
6.
VERIFY that the Diesal Generator Cooling Water Pump STARTS.
7 VERIFY that the Diesel Generator Lube Oil Circulating Pump STOPS.
8.
Bring the Diesel Generator up to speed with the governor control switch located at the Engine Control Panel.
9.
Check diesel generator voltage and frequency at the Diesel Gener-ator Metering and Relay Panel.
- 10. Notify the Diesel Generator Breaker Operator that the Diesel Gen-erator is ready for loading.
' APPROVED APR 2012 9 of 14 0.0.S.R.
EPIP 200-20 Revision 1 ATTACHMENT 4 (Cont'd.)
- 11. OBSERVE diesel generator voltage and frequency as the diesel gen-erator breaker is closed and as equipment on the bus is started.
- 12. OBSERVE diesel generator load restrictions as the diesel engine is loaded. Use KW meter.
- 13. MONITOR diesel oil day tank level, water flow and engine tenper-a ture.
l
'APPRO@
gm20S2 10 of 14 0.0.s.R.
EPIP 200-20 Revision 1 ATTACHMENT 5 LOCAL CONTROL OF FEED BREAKERS TO AUXILIARY TRANSFORMERS AND BUSES 28(38)/29(39) 1.
Ensure that the bus to be energized is dead.
2.
Bus tie breaker 28(38)/29(39) OPEN.
3.
Voltage restored to 4Kv Bus 23-1(33-1)/24-1(34-1).
4.
To protect against a loss of local control caused by fire induced cable faults or equipment malfunction, OPEN the Safe Shutdown Con-trol Room Disconnect Switches at 23-1(33-1)/24-1(34-1) bus cubicle.
5.
Plug the safe shutdown pushbutton station cable into the safe shut-down receptacle on Bus 28(38)/29(39) feed at Bus 23-1(33-1)/24-1 (34-1).
6.
Check that voltage is on Bus 23-1(33-1)/24-1(34-1).
7.
CLOSE the feed breaker to Transfonner 28(38)/29(39) at Bus 23-1 (33-1/24-1(34-1).
8.
OPEN the Safe Shutdown Control Room Disconnect Switches at 28(38)/
29(39) bus cubicle.
9.
Plug in the safe shutdown pushbutton station cable into the safe shutdown receptacle at 28(38)/29(39) bus cubicle.
- 10. OPEN all nonessential feed breakers on Bus 28(38)/29(39).
- 11. CLOSE the feed breaker from Bus 23-1(33-1)/24-1(34-1) to Bus 28 (38)/29(39) at Bus 28(38)/29(39).
I t
' APPROVED AR 20 M 11 of 14 0.0.S.R.
EPIP 200-20 Revision 1 ATTACHMENT 6 LOCAL CONTROL OF BUS TIE BREAKERS (DEAD BUS ONLY)
(24 to 24-1 at Bus 24, 34 to 34-1 at Bus 34, 23 to 23-1 at Bus 23, 33 to 33-1 at Bus 33, 24 to 24-1 at Bus 24-1, 34 to 34-1 at Bus 34-1, 23 to 23-1 at Bus 23-1, and 33 to 33-1 at Bus 33-1.)
1.
CHECK that all feed breakers to the bus to be energized are in the OPEN position.
2.
Prior to closing the feed breakers, OPEN the Safe Shutdown Control Roam Disconnect Switches at the diesel generator breaker cubicle.
3.
Plug in the safe shutdown pushbutton station cable into the safe shutdown receptacle of the feed breaker to be closed.
4 CLOSE the bus tie breakers.
APPROVED R 20'82 12 of 14 U.0.S.R.
~
)
EPIP 200-20 Revision 1 ATTACHMENT 7 LOCAL CONTROL OF CONDENSATE TRANSFER PUMPS 1.
To disconnect renote control circuit from local control circuit pull Safe Shutdown Control Room Disconnect Fuses listed below:
Condensate Transfer Pump 2A MCC 28-2 (Turbine Bldg. by Hydrogen Seal Oil Unit) Compt. 05 Fuse Condensate Transfer Pump 28 MCC 29-2 (Turbine Bldg. Ground Floor -
East of Service Air Compressor) Compt. A4 Fuse Condensate Transfer Pump 3A MCC 38-2 (Turbine Bldg. by Hydrogen Seal Oil Unit) Compt. D3 Fuse Condensate Transfer Pump 38 MCC 39-2 (Turbine Bldg. by Standby Gas Treatment System) Compt. A5 Fuse 2.
START or STOP the Condensate Transfer Pumps using local pushbuttons.
APPROVED APR 2012 13 of 14 u.0.S.R.
EPIP 200-20 Revision 1 ATTACHMENT 8 LOCAL CONTROL OF CRD PUMPS 1.
To protect against a loss of local control caused by fire induced cable faults or equipment malfunctions, OPEN the Safe Shutdown Control Room Disconnect Switches at the bus cubicle.
2.
Verify that the Turbine Building Closed Cooling Water Systen is in service.
3.
Verify that the CRD Pump has a minimum flow path.
4.
Verify that the desired suction filter is in service.
i 5.
OPEN the Suction Filter Vent Valve and VENT the filter housing.
CLOSE the valve when vented.
6.
OPEN Vent Valve 301-13A/B to vent CR0 pump casing, then CLOSE the valve.
7.
Verify that CR0 pump and motor oil levels are proper and recheck following pump start.
8.
CLOSE CRD Pump Discharge Valve 301-2A/B.
9.
CLOSE CRD Charging Header Valve 301-25.
- 10. OBSERVE pump suction pressure-(Local Panel 301-2A/B to be 10 to 20psig).
- 11. START the CRD Pump at the local control station.
- 12. THROTTLE CRD Pump Discharge Valve 301-2A/B to prevent ptsnp run-out to control pump amps.
If necessary to control pump amps, OPEN CRD Charging Header Valve 301-25.
- 13. Verify CRD pump steady state current is less than 34 amps.
l' APPRO G APR 20'82 14 of 14 G:lNAL.)
0.0.SA I
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