ML20083P486
| ML20083P486 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/26/1984 |
| From: | PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML16341C133 | List: |
| References | |
| PROC-840326-01, NUDOCS 8404200027 | |
| Download: ML20083P486 (268) | |
Text
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PGandE Letter No.: DCL-84-118 l
ATTACHENT 1 Updates Included In This Submittal l
DIABLO CANYON EMERGENCY PLAN
) IMPLEMENTING PROCEDURES Volume 3A l
EP OP-3A, Revision 5 EP OP-8, Revision 8 EP OP-13. Revision 3 EP OP-25 Rev'ision 2 EP M-1, Revision 11 EP R-1, Revision 11 EP R-7, Revision 4 Volume 38 EP EF-5, Revision 4 EP RB-2, On-The-Spot Change CORPORATE EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURES CERP 2.2, Revision 1
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- I PGandE Letter No.: DCL-84-118 ATTACHMENT 2 Location of Proprietary / Privacy Information
- Procedure:
2-1, pages 2,11 and 16 of 16; Attachment " Safety, Health, and Claims Personnel to be Contacted for l
Reporting of Injuries at Diablo Canyon" - pages 1 and 2 of 2.
R-7, pages 9 and 10 of 10.
M-1, pages 1-3 of 5; Attachment " Company Panel of Physicians, Ambulances and Hospitals" - pages 1 l and 2 of 2; Attachment " Panel of Physicians, Ambulances and Hospitals, Coast Valleys Division" -
pages 2.1-2.6 of 6; Attachment " Safety. Health and Claims Personnel to be Contacted for Reporting of Injuries at Diablo Canyon" - pages 1
! and 2 of 2; Attachment 10 - Appendix Z - page 1 of 1.
EF-5, page 11 of 38; pages 26, 27, 28, 29, 30, 31 and 32 of 38; Attachment " Emergency Facility Phone Numbers" - page 1 of 1; Attachment " Technical
- Support Center Check List" - pages 2 and 3 of 3; Attachment -
" Emergency Operating Facility Equipment Function i
Checklist" - pages 1-3 of 3.
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CURRENT E!!ERGENCY PLAN DFLEMENTING PROCEDURES TABLE OF CONTENTS Yolume 3A TITLE REY OP-0 Reactor Trip With Safety Injection 5 OP-1 Loss of Coolant Accident 7 OP-2 Loss of Secondary Coolant 2 OP-3A Steam Gen Tube Failure 5 -
OP-3B Minor Steam Gen Tube Failure 1 OP-4A Loss of Electrical Power 1 OP-4B Loss of All AC Power 0 OP-5 Reactor Trip Without Safety Injection 5 CP-6 Emergency Boration 6 OP-7 Loss of Condenser Vacuum 2 OP-8 Control Room Inaccessibility 8 OP-9 Loss of Reactor Coolant Pump 4 OP-10 Loss of Auxiliary Salt Water 2 OP-11 Loss of Component Cooling Water 3
. OP-12 Malfunction of Auto Reactor Control System i s OP-12A Failure of a Control Bk to Move in Auto 2 OP-12B Cont Withdrawl of a Control Rod Bank 3 OP-12C Cont Insertion of a Control Rod Bank 2 OP-12D Control Rod Pos Indication Sys tialfunc 3 OP-12E Control Rod Misalignment 2 OP-12F Dropped Control Rod 2 4
OP-13 Malfunction of Reactor Press Control System 3 OP-14 High Activity in Reactor Coolant 2 CP-15 Loss of Feedwater 4 CP-16 Nuclear Instrumentation Malfunctions 3 OP-17 italfunction of RHR System 2 OP-18A Loss of Charging 0 OP-188 Loss of Normal Letdown 0 CP-19 Malfunction of Reactor Makeup Control 2 OP-20 Excessive Reactor Coolant System Leakage 2
,o 03/26/84 0502d/0005K b
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2-TITLE Rg OP-21 Loss of A Coolant Loop RTD 2 OP-22 Emergency Shutdown 1 OP-23 Natural Circulation of Reactor Coolant 3 CP-24 Loss of Containment Integrity 1 a OP-25 Tank Ruptures 2 4 OP-25 Excessive Feedwater Flow 1 j OP-27 Irradiated Fuel Damage 1
- OP-28 Startup of an Inactive Reactive Coolant Loop 1 i
OP-29 Excessive Load Increase 1 OP-30. Inadvertent Load Fuel Assly Improper Pos 1 OP-31 System Under Frequency 1 OP-32 Rod Ejection 1 OP-33 Loss of Instrument Air 1 i '
CP-34 Generator Trip - Full Load Rejection 1 OP-35 Loss of Vital or Non-Vital Instr AC Sys 1 OP-36 Turbine Trip 1 OP-37 Loss of Protection System Channel 1 OP-38 Anticipated Transient Without Trip (ATWT) 5 OP-39 RCP Locked Rotor Accident 1 OP-40 Accidental Depressurization of MS System I i OP-41 Hydrogen " Explosion" Inside Containment 1 GP-44 Gaseous Voids in the RCS 2
.< R-1 Per Injury (Rad Related) And/0r Overexp 11 R-2 Re1 of Airborne Radioactive Materials 4 i 4 R-3 Rei of Radioactive Liquids 3 R-4 High Radiation (In Plant) 3 R-5 Radioactive Liquid Spill 3 R-6 Radiological Fire 6 4
R-7 Offsite Transportation Accidents 4 ti-1 Employee Injury of Illness (Nonradiological) 11 ti-2 Nonemployee Injury or Illness (Third Party) 9 M-3 Chlorine Release 5 4 ti-4 Earthquake 7 11- 5 Tsunami Warning 5
. M-6 Nonradiological Fire 8 M-7 011 Spill ISO and Clean Up Procedure 6 '
2 M-8 Containment Emergency Personnel Hatch 0 M-9 Hazardous Waste Management Contingency Plan 1
- G-1 Emergency Classification and Emergency Plan
- Activation 3 1 G-2 Establishment of the On-Site Emergency i
Organization 3 G-3 Notificatio.n of Off-Site Organizations 2
- G-4 Personnel Accountability and Assembly 3
- G-5 Evacuation of Nonessential Site Personnel 0 03/26/84
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3 C- E G Pacific Gas and Electric Company NUMBER EP OP-3A REVISION 5 CEPARTMENT OF NUCLEAR PLANT CPERATICNS DATE 2/8/84 OIABLO CANYCN PCWER PLANT UNIT NC(S) 1 AND 2 PAGE 1 0F 23 EMERGENCY PROCEDURE IMPORTANT h TITLE. STEAM GENERATOR TUBE RUPTURE TO APPACVED: Y PLANT M ER DATE
- SCOPE This procedu.*e covers the operating steps to be taken in the event of a steam generator tube rupture. It is assumed that reactor trip and safety injection actuations have occurred. The operator should have already perfor ned Emergency Operating Procedure OP-0, " Reactor Trip with Safety Injection". This procedure and changes thereto requires t PSRC review.
SYMPTOMS (See OP-0 symptoms)
AUTOMATIC ACTIONS (SeeOP-0AutomaticActions)
OBJECTIVES
- 1. To minimize the release of radioactive material by identifying and isolating the faulted steam generator and by reducing reactor coolant system pressure below the steam generator valve setting (1065 psig).
- 2. To estawlish the capability to supply feedwater to all steam generators and to isolate feedwater to the faulted steam generator.
- 3. To maintain the ability to remove the necessary residual heat from the reactor through the intact steam generators via the steam dump valves to the condenser or the atmosphere.
4 To maintain the reactor coolant system in a subcooled state during the recovery.
- 5. To prevent overflooding of the faulty steam generator.
IM EDIATE OPERATOR ACTIONS (See OP-0 Innediate Operator Actions)
SUBSEQUENT OPERATOR ACTIONS 0C0C03 II 9
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OtAat.o CANYON PCWER PLANT UNIT NC(S) 1 AND 2 REVISION 5 DATE 2/8/84 PAGE 2 0F 23 ma STEAM GENERATOR TUBE RUPTURE t
ACTIONS COMMENTS
- 1. Sound the site emergency alarm.
- 2. Contact Chemistry & Radiation 2. The steam generator samples Department to sample containment are essential for subsequent atmosphere and all steam generators recovery actions, for abnormal radiation.
- 3. Identify the faulted steam generator 3. While attempting to identify by one of the following methods, and isolate the faulted 1 steam generator, continue with this procedure up to step 17. I
- a. Observe steam generator water levels.
The faulted steam generator should .
experience an unexpected rise in level. If required, momentarily reduce auxiliary feedwater flow to the steam generators and attempt to identify the faulted steam generator by level indications.
- b. Reset Containment Isolation Phase A, Train A and Train B.
- 1) If a high blowdown radiation signal is NOT present, open or check open the inside containment SG blowdown isolation valves and open the sample valves FCV 250, 248, 246 and 244 one at a time to identify the faulted steam generator. Allow time between opening to allow sample flow to contact the radiation element. The steam generator blowdown with high radiation identifies the faulted steam generator.
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NUMBER EP OP-3A ciAsto cANYCN PCWER Pt. ANT UNIT NC(S) 1 AND 2 REVISION 5 DATE 2/8/84 PAGE 3 0F 23
- 7gtg STEAM GENERATOR TUBE RUPTURE ACTIONS COMMENTS
- 2) If high ractation level on steam generator blewdown liquid monitor has isolated steam generator blowdown and blowdown samples, detennine the faulted steam generator -
as folicws. First, check open or open the IC bicwdown isolation valves, then cut in the S/G blowdown Hi Rad switch on VB-3 to overrice the high radiation trip signal and open FCV's 250, 248, 246 and 244 steam generators 1 through 4 blowdown sample valves, '
one at a time as necessary to compare radiation levels on each.
The SG with the high radiation in the sample is the faulted SG.
- 3) From the steam generator samples, identify the faulted Steam Generator by observation of abnormally high radiation in any one steam generator.
4 When the faulted steam generator has been positively identified, ISOLATE THE FAULTED STEAM GENERATOR.
- a. Stop all AFW flow to the faulted a. Monitor the water level steam generator. in the faulted steam generato' throughout this procedure.
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NUMSER EP OP-3A DIAsto cANvCN PCwtR PLANT UNIT NO(S: 1 A;,9 ', REVISICN 5 DATE 2/8/84 PAGE 4 0F 23 rira STEAM GENERATCR TLBE RUPTURE ,
I ACTIONS COMENTS
- b. Close or verify closed, the b. The steam generator safety following valves associated valves on the faulted steam with the faulted steam generator may lift during generator. 053). this operation.
Main Steam Isolation Valve, Main Steam Isolation Valve Bypass Valve, IC and OC Blowdown Valve, Blowdown Sample Valve, 10% Atmospheric Relief Valve.
- 5. If the main steam isolation valves or the main steam isolation valve bypass valve on the faulted steam generator will not close, then close the main steam isolation valves and bypass valves on ALL nenfaulted steam generators ana verify tne nonfaulted steam generators 10% atmospheric relief valves maintaining steam generator.
pressure approximately 1035 psig.
- 6. Verify closed and place in manual the 101 atmospheric relief valve on th'e faulted steam generator.
- 7. If steam generator No. 2 is the 7. This will tenninate the faulted steam generator, close the activity release from the aux, feedwater pump steam supply .
faulted steam generator FCV 37. If steam generator No. 3 via the steam driven aux.
is the faulted steam generator, feed pump.
close FCV 38.
- 8. Verify all pressurizer PORV's are 8. Verify by position lights closed, and discharge line temperature indication. -
Verify by lit position lights that power is available to the pressurizer power operated relief va}ve backup isolation valves.
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otAsi.o cANycN PCwtA Pt. ANT t.Ntf Not$1 1 ANp ', NUMBER EP OP-3A REVIS!CN 5 OATE 2/8/84 PAGE 5 0F 23 TiTa STEAM GENERATOR TUBE RUPTURE ACTIONS CONNENTS
- 9. Monitor the core exit thermccouple 9. Indications of inadequate temperature for indications of core cooling are given in inacequate core cooling. If Appendix C of this procedure, indications of inadquate core cooling exist, perform Appendix C of this procedure.
- 10. If RCS wide range pressure continues 10. NOTE: The conditions for to decay below 1220 psig or is stopping RCP must be belew 1220 psig and stable, continuously monitored through step 18.
- a. Again verify a minimum of one ena ming pump delivering flow and one $1 puro delivering flow to .
the RCS,
! b. THEN. STOP all four reactor coolant Es . Maintain seal water flow to tne KPseals by manually adjusting the reciprocating charging pump speed or FCV 128.
- c. Close the Centrifugal Charging c. NOTE: If the W.R. RCS pump recirculation valves pressure is increased (8105 and 8106) above 2000 psig, reopen valves 8105 and 8106 to prevent pump damage.
- d. If component cooling water to the RCP's is isolated due to a containment Phase 8 isolation, stop all RCP's within 5 1 minutes and maintain seal flow as above.
- 11. If the faulted steam generator was 11. If the faulted steam isolated by closure of its M51V generator has been (per step 4 of this procedure) identified, do not dump perform steps a. A b. below. steam from the faulted If it was isolated as per step steam generator. Maintain
- 5. go to step 12. containrent Phase A ,
Isolation until necessary to reset for system operations.
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- M SER EP 09 3A OIASLO CANYCN PCvvem PLANT UN87 NC45) 1 AND 2 REY!SION 5 OATE 2/8/84 PAGE 6 CF 23 rir a STEAN GENERATCR TUSS RUPTURE ACTIONS COMMENTS
- a. If the condenser is available, open or verify open the nonfaulted steam generators main steam isolation valves and establish steam dug to the i condenser. Transfer the steam dump control to the pressure control mode and verify set .'
pressure at N0 load pressure.
- b. If the concenser is not available, verify the 10% atmospheric relief valves hoiding steam pressure below the safety valve setpotnt.
- 12. Ver'fy or establisn power on the 480 12. This power, plus the volt vital buses. F, G and H. normal and backup bottled air supply, will assure power sources available for at least one PZR PORV, steam generator PORY's and charging and letdown flowpaths. If loss of offsite power occurs, the letdown path will be to -
the PRT via the relief valve downstream of the orifice valves, g3, Verify RCS T,,9 is at or approaching i
no load under the influence of condenser or atmospheric relief valves from the nonfaulted steam generators.
Adjust steam dump if required to achieve T,,j,,4, 14 Maintain maximum AFW flow until 14 Observe the water levels the steam generator water levels closely for unexplained are in the narrow range. When changes in one steam the SG water levels approach 331 generator which may identify M. verify automatic steam the faulted steam generator, generator level control.
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- NUMBER EP CP-3A OiAsto CANYCN PCWER PLANT UN67 Nots) 1 AND 2 REY!5 ION 5 OATE 2/8/84 PAGE 7 0F 23 t vira STEAM GE.NERATOR TUBE RUPTURE ACTIONS CCWENTS
- 15. Monitor the condensate storage 15. If tne CST.lo lo level alam tanz and upon reaching approximately occurs, the operator has los level, perfom a. or b. below. approximately 25 minutes to perfom Steps a. or D.
- a. Verify a level in the raw water storage reservoirl then open FCV-436 and FCV-437 (Reservoir s6pply to AFW pumps). Allow the AR pumps to run during the transfer. Monitor the AFW flew closely. If AFW flow is lost, t-1p all 3 AFW pumps until the transfer is complete, then restart the pumps.
- b. If the raw water storage reservoir is not available, go to Appendix
, A (AFW Puer Suction Supply from Fire Water Tank Procedure). Allow the AN pumps to run during the transfer. Monitor the AFW flow closely. If AFW flow is lost, trip all 3 AFW pumps until the transfer is complete, then restart the pumps.
- 16. If the RC3 pressure is above the 16. CAUT!CNt1)lftheRC$ pressure shutoff head of the RHR pumps, falls below the shutoff head of the RHR pumps, restart the pumps to deliver water to RESET SAFETY INJECTION the RC5 and stop both RHR pumps.
. CAUT!0N2) Automatic retnitiation of safety injection will not occur after this step since the reactor trip breakers are open. If the operator has indication that an St is required af ter this step, he must initiata it manually.
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NUf48ER EP OP-3A otA84.0 CANYCN *Cwem PLANT UNif Nots) 1 AND 2 REVISION $
DATE 2/8/84 PAGE 8 0F 23 riv a STEAM GENERATOR TtBE RUPTURE
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ACTIONS CCPNENTS
- 16. (Cont)
CAUT!0N:3)!f loss of offsite power occurs after resetting safety injection, it will be necessary to load the safeguards equipment onto the vital buses manually.
If safety injection is reinttiated manually after the loss of offsite power, the vital buses will automatically sequentially load the safeguard equipment.
If loss of offsite pcwer occurs, go to Appendix 8 (BlackoutWithSIEmerp.
Loading of Vital Busess.
- 17. 00 NOT pe0CEED OEYCN0 THIS STEP t UhT t, Tht FAVl,T(Q STEAM GENERATGR [5 10(NTLFi[p AND I 5OL.AT E R.
- 18. Begin a ,R,g1,d,cooldown d of the RCS to 500 degrees F using only the nonfaulted steam generators.
- a. If the faulted steam generator was isolated oy closure of the main steam isolation valves associated with the nonfaulted steam generators, dump steam only from the nonfaulted steam generators through the los atmospheric relief valves.
- If isolated per step 4, use step
- b. or c. below.
- b. Use the condenser steam dumps if b. This is the preferred the condenser is available. Go method. When P 12 is to steam pressure control mode if reached, select Iypass not already in this mode. Interlock on the Steam l
Place tne steam pressure controller Du g Interlock 5 elector In MNUAL and increase the demand switches to pennit the l
as necessary cooldown. '
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ciasto c48ves mwam %T Unit Noisi 1 A.NO 2 h(l3 fen lP M OATE 2/8/84 PAGE 9 0F 23
' $ TEAM GENERATCR TUBE RUPTURE riv a ACTIONS COMMENTS
- c. If the condenser is not available, use the los
! atmospnerte relief valves from the nonfaulted steam generators.
- 19. Continue to monitor containment conditions, if containment sump level rises abnormally or if a containment sample (if available) indicates hi activity in containment, go to OP gn 1 for further accident recovery.
- 20. Af ter the RCS has been cooled to 500 20. During subsequent controlled degrees F, if required, depressurize RCS depressurization, the the RCS to the value equal to the criteria for tripping RCP's faulted steam generator pressure. on low pressure no lenger If pressurizer level has been off applies.
l scale low, the level will probably
, return during tais operation.
Maintain minimum 35 degrees F l subcooling during this operation.
- 4. If RCP's are in service, use pressurizer spray to reduce RC5 pressure.
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- b. If nonnal spray is not available. b. UT It may take 2 3 open n pressurizer Power Operated minutes for PORV Rette alve (PORV) to reduce RCS discharge line
, pressure. Verify closure of the temperature tp start valve by observing position decreasing indication and discharge line .
temperature decreasing, and if required, close the backup isolation valve. .
OC0003 91
NUMBER EP OP-3A ciAsi.o cANYCN PCWER Pt. ANT UN67 NCtSi 1 AND 2 REVISICN 5
- DATE 2/8/84 PAGE 10 0F 23 ritu STENT GENERATOR TUBE RUPTURE ACTIONS COMMENTS
- 21. As RCS pressuri:e decreases, due to PIR spray er the PIR PORY being open, monitor PZR level and stop the cepressuri:ation when:
- a. PZR level exceeds 851,
- b. OR RCS pressure decreases to the p7 essure of the faulted steam generator.
Verify closure of the PORV by position indication and discharge line temperature. Verify closure of the spray valve by position indication.
- 22. Continue to monitor RCS pressure and pressurizer water level,
- a. If pressurizer level continues a. Monitor PRT conditions to rise or is stable with and relief Ifne temperatures continued RCS pressure to detect a possible stuck decreasing after the open valve. Close the depressur124 tion is terminated, appropriate PORY isolation suspect leakage from the valve if leakage is suspected, pressurizer steam space. If this condition persists and the PRT rupture disc is ruptured go to OP-1, " Loss of Coolant Accident". ,
- b. If the pressurizer level continues to rise with risino RCS pressure, AND PRT conditions are stable, the St TTow is ' greater than the tube rupture flow.
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ciAsto cANycN pews uT UNat Netsi NUMBER EP OP-3A 1 AND 2 REVIS;CN 5 CATE 2/8/84 PAGE 11 0F 23 I
titu STEAM GENERATOR TUBE RUPTURE ACitCNS COMMENTS
- c. 00 NOT continue in this procecure untti the conditions of b. sbove are observed. .
- 23. When RCS pressure has increased by 200 psig af ter the termination of the depressurization,
- 4. AND Pressurizer water level is greater than 22%
! b. AND indicated subccoling from the 1 l nonfaulted steam generator loops I is greater than 35 degrees F l
- c. THEN allow one centrifugal charging When the charging and $1 pumps .
puso to operate for normal charging are shutdown the RCS pressure and RCP seals and shutdown the should decrease to the value remaining charging, and $1 pumps of the faulted steam generator .
while maintaining operable safety injection flowpaths.
24 Establish normal charging. 24 Continue monitoring PZR level. If PZR level cannot
- a. Reset containment Phase A be maintained above 22%,
isolation if required. or indicated subcooling from the nonfaulted steam
- b. Check open or open normal generator loops cannot be charging valve 3146. maintained greater than 35 degrees F, manually
- c. Check closed or close charging reinitiate $1 and return to to aus. spray valve 8145 and step 20 and continue, alt, spray bypass valve 8148 and alternate charging valve 8147.
- d. Open charging line isolation valves 8107 and 8108.
- e. Close the BIT inlet and outlet valves 8803A and 8 and 8801A and B.
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NUMBER EP OP-3A c Aato cANYCN POWER PUNT UNIT NCW 1 AND 2 REVISION 5 DATE 2/8/84 PAGE 12 0F 23 7:Ta STEAM GENERATOR TUBE RUPTURE ACTIONS COMENTS
- f. Adjust HCV-142 and FCV-128 or reciprocal charging pump speed to achieve RCP seal flow and charging flow as required to maintain pressurizer level greater than 227..
I g. Open RCP seal .eturn valves, 8100 and 8112. Check seal ficw normal.
- 25. Establish normal letdown.
- a. Check open or open letdown valves LCV-459 and 460.
- b. Open letdown isolation valve 8152.
- c. Ocen one 75 gpm letdown orifice valve.
- d. Verify PCV-135 opening by observing letdown flow.
- a. Adjust VCT makeup blend to the cold Xe free concentration,
- b. Open VCT outlet valves LCV-112Bac,
- c. Close RWST to charging pump suction valves 8805 A&B.
- d. Verify divert valve LCV-112A in AUTO.
- 27. Reestablish the use of the pressurizer heaters to control pressure. If .
reoutred, transfer the pressurizer -
backup heaters groups 2 and 3 to the .
Vital 480 volt buses G4H.
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DIABLc cANycN PCWER PUNT UNIT Nots) NUMBER EP OP-3A 1 AND 2 REVISION 5 OATE 2/B/84 PAGE 13 0F 23
- rira STEAM GENERATOR TUBE RUPTURE ACTIONS CONNENTS
- 28. If possible, establish conditions 28. The icw pressure pump for starting No. I and No. 2 RCP's trip criteria no longer if the pumps have been shutdown, applies,
- a. When conoitions are established, a. Start both pumps to start both RCP's. deliver spray regardless of whether these pumps are associated with a faulted steam generator.
- 29. If No.1 and/or No. 2 RCP is 29. This step will reduce the running, shutdown No. 3 and primary heat load.
and No. 4 RCP's.
- 30. With the plant in a stabilized condition, determine if the condenser will be available to receive steam dump during the subsequent cooldown.
- a. If the condenser is available, a. Failure to perform steps perform steps 31, 32 and 33 31, 32 and 33 SIMULTANEOUSLY. simultaneousiy may result in a loss of PZR level control .
- b. If the condenser is not b. Consult the Vol. 9 curves available, notify the to determ'ine how long the Chemistry and Radiation plant can remain at hot Protection Department that standb/ before proceeding a controlled activity release to cold shutdown.
will be occuring. If time permits, verify that all faulted steam generator samples have been taken, then perform steps 31, 32, and 33 SIMULTANEOUSLY.
- 31. Begin a controlled cooldown of the RCS using steam dump from the NONFAULTED steam generators only. Verify as steam dump.begins that AFW system is maintaining l ALL steam generator levels in automatic.
OCC003 131 O
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i ciAsto cANYCN PCWEA PLANT UNIT N0(S1 1 AND 2 hCN DATE 2/8/84 PAGE 14 0F 23 l rirty STEAM GENERATOR TUBE RUPTURE ACTIONS COMMENTS Place the LCV for the faulted steam generator in automatic and verify normal AFW response to the faulted steam generator existing level. If the faulted steam
~ generator level is low, verify feedwater flow to the steam generator; if level is high, h0 feedwater flow to the steam generator,
- a. Maintain an RCS cooldown rate of about 50 degrees F/HR.
- b. Use the condenser dump valves by reducing the pressure satpoint. If the condenser is not available, use
. the 10% atmospheric relief valves.
If the faulted steam generator was isolated as per step 5 of this procedure, use the 10% atmospheric relief valves.
- 32. Simultaneous with the cooldown, dump steam from the faulted steam generator to the condenser.
- a. Bleed steam to the condenser a. THIS !$ THE PREFERRED using the Main Steam Isolation METHOD.
Valve BYPASS VALVE.
- b. If the condenser is not available, b. THIS IS NOT THE PREFERREC use the 101 atmospheric steam METHOD.
relief valves.
- 33. Simultaneous with the faulted steam 33. This will minimize the mass generator pressure dscay, control RCS and the faulted steam RCS pressure approximately the generator. Stay within the same as the faulted steam limits on the Tech. Spec.
generator pressure. cooldown curves during this operation.
- a. Use PIR heaters and one of the following:
- b. Use normal PZR spray if possible OR
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DC0003 141
oiAeLo c4NvCN PCWEA PLANT UNIT NC(S)
NUMBER EP OP-3A 1 AND 2 REVISION 5 ,
l DATE 2/8/84 PAGE 15 0F 23 1
- rirts STEAM GENERATOR TU8E RUPTURE ACTIONS COMMENTS
- c. Use auxiliary spray if letdcwn is in service OR
- d. Use PZR PORY intermittently if required. If the PZR PORY is used, continuously monitor PRT pressure, temperature, and level and take appropriate actions to maintain PRT integrity. Verify PORY closure by position indication and PRT conditons. If a RCS leak to the PRT is identified, close the PORY 1 solation valve. ,
34 Determine the cold Xe Free Shutdown margin and borate if required to that concentration.
- 35. At approximately 800 psig RCS pressure close all 4 accumulator injection isolation valves. -
- 36. When the RCS hot leg temperatures 36. Do not collapse the PZR are reduced to less than 350 degrees bubble.
F and RCS pressure is less than 400 psig, place the RHR in service
- using Operating Procedure B-2.
(Residual Heat Removal System).
- 37. Continue the cooldown in this mode 37. Use Operating Procedure until the RCP is stopped, then .L-5 (Plant Cooldown From continue to control RCS and Minimum Load to Cold faulted steam generator pressures Shutdown) in conjunction until the RCS hot leg temperatures with this procedure during are below 200 degrees F, then the cooldown. Enter L-5 '
use auxiliary spray untti the at the point where RHR RCS pressure and faulted steam is to be put into service.
generator pressures equilibrate.
- 38. Continue operation of the RHR, letdown and charging as required.
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OtASLO CANYCN PCWER Pt ANT UNIT NC(s) 1 AND 2 ('h 'h fP OP-3A DATE 2/8/S4 PAGE 16 0F 23 Tm STEAM GENERATOR TUBE RUPTURE APPENDIX A AUXILIARY FEED PUMP SUCTICN SUPPLY FRCM FIRE WATER TANK The operator has 20 minutes to perform this operation after the lo lo level alann on the condensate storage tank and before the AFW pumps lose suction.
This provides sufficient time; however, the operator must not delay and must carry out the valve line up in order as written.
- If the AFW pumps are being supplied from the ' raw water reservoir and a seismic event occurs with resultant loss of AFW suction and auxiliary feedwater flow to the steam generators, the steam generators will boil dry in about 30 minutes. Under these conditions, it is especially important to expedite this procedure and reestablish AFW flow to the steam generators prior to the reactor losing its heat sink.
ACTIONS C0lHENTS Using the attacaed drawing, proceed
'to supply the AFW pumps suction from the fire water tank.
- 1. Close or verify closed MU-0-284 1. Closing these valves prevents and MU-0-286. . losing fire water out a possible break in the reservoir supply line. -
- 2. Close or check closed MU-1-298.
- 3. Close or check closed MU-0-325. ,
4 Close or check closed MU-0-427.
- 6. Notify the control room that the suction for the AFW pumps is now available from the fire water tank. ,
- 7. From the control room open FCV-436 and 437.
- 8. Proceed to tne auxiliary feedwater pumps and vent the pump casings if required to remove air.
I OCC003 161 ,
e0 g
v - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - ~ ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
I -!. o.
o n n Q Fire Water )
Tank U 5 q To M.U. b k o W Scaled TP.-0-4 rr o.3 g filters !] g T's Fire Open Valve h open n -@
a Pgs q := -.
Suction Open y g r} gy Close U MU-0-325 4; Close /\ A E a
~
Q - $
Mi ** E 284 Trom Raw Raw cjose Water5 ficashir/ MU 29# E >
Water Reservoir > . j i Mi-0-427 V g g
/\ -
~ 4 Close P S IR Package U 8 n H.U. Filter Bypass FCV-436 u yy Ppl-1 4 I l-297 Scaled Open U" Valve EEAM MZ3
?. '3 9
FCV-437 ,
Am 00*O Pp I-2 <
8
@ fire Water Tank to a o
Q" {**
AfW Ptmp Suction 1-3 open
~
' ^
oiAsto cAsvos newsm aw.T usit Nois) 1 AND 2 ON OATE 2/8/84 PAGE 18 0F 23 y,fte STEAM GENERATCR TUSE RUPTLRE ,
APPEN0!X B l St.ACx0VT WITH SAFETY !NJECT!0N EMERGENCY LCA0!NG 0F VITAL BUSES
- 1. If the vital buses lose voltage prior to resetting the safety injection
- signal, the vital buses will automatically load the vital equierent given below. Verify the equipmnt has been loaded by observing breaker lights on the control board. -
- 2. If the vital buses lose voltage dter thq safi'y injection signal has been reset, load or verify loadeb tne elair.nent given below cnto the vital buses u nually. Allow approximately 4 seconds between loading of eacn piece of eculpment onto a giver' vital bus. Load or verify that the CFCU's are running in t.ow Speed.
VITAL BUS VITAL BUS VITAL BUS F G H 0/G 1-3 O/G 1 2 D/G 1 1, MCC 1 F MCC 1-G fCC 1 H CC Pp 1 1 CC Pp 1 2 51 Pp 1-2
$! Pp 1 1 l
! CFCU 1 2 RHR Pp 1-1 RHR Pp 1-2 CFCU 1-1 . CFCU 1 3 CFCU 1 4 CCW Pp 1 1 CFCU 1 5 CCW Pp 1 3 ASW Pp 1 1 CCW Pp 1 2 AFW 5p 1 2 AFW Pp 1 1 ASW Pp 1 2
- 3. Lead the containment spray Pumps only if they were running prior to the blackout. .
VITAL SUS VITAL, SUS G H Cont Spray Pp 1-1 Cent Spray Pp 1 2 i
I CC0003 18!
- 6 s
ciasto cAsycs acwam ut usir scisi 1 AND 2
[SfCN DATE 2/8/84 .
PAGE 19 0F 03
, t STEAM GENERATOR TUSE RUPTURE titta APPEN0!X C CETERMINATION OF ADECUATE CCRE CCCLING This appendix provides the guidance to determine adequate core cooling if inadequate core cooling is suspected. Further, the instructions for regaining adequate core cooling is presented.
ACTION COMMENTS
- 1. Monitor the core exit thermocouple temperatures.
- a. If the P-250 is available go to step 2.
- b. If the P 250 is not
~~~ available go to step 3.
- 2. If 5 or more P 250 thermocouple ,
readings exceed 1200 degrees F, notify the Shift Foremen that inadquate core cooling exists and go to step 5.
If there are not 5 or more that onceed 1200 deg7ees F discontinue this appendix but continue to monitor the thermocouple readings.
- 3. Monitor the thermocouple readout on PAMS 3 and 4 If 5 or more thermo-couple readings escoed 1200'F notify the Shift Foremen that inadequate core cooling esists and go to step 5.
If there are no 5 or mor9 readings that onceed 16 'F discontinue this appendia but continue to monitor the thermoccuple readings.
l ""i t
e DC0003 191 e
4 90 9
I l
CIABLO CANYON PCWER PLANT UNIT NO(S) 1 AND 2 f0N
- l DATE 2/8/64
! PAGE 20 0F 23 STEAM GENERATOR TUBE RUPTURE 737 a .
-ACTION COMENTS
- 4. The Shift Foreman will verify if inadequate core cooling exists using the appropriate steps above. If inadequate core cooling exists the Shift Foreman will direct operations as follows:
- a. Declare a General Emergency.
Implement tne instructions given in Emergency Procedure G-1 regarding on and offsite protective actions.
- b. Attempt to establish SI flow to the RCS and AFW flow to the steam generators,
- c. Continue monitoring core outlet temperature to determine the effectiveness of the remaining actions.
- d. DEPRESSURIZE THE RCS by method 1 or 2 below.
- 1) Dump steam to the condenser 1)THISISTHEPREFERREDhETH00.
or atmosphere if the steam generator levels are in the narrow range and AFW flow is evident.
- 2) Verify the SIS or charging 2) Opening the PORV's will provide pumps are running and a drop in RCS pressure available to deliver water sufficient to allow tiie SI to the RCS flow required to cool the core.
THEN This method is to be used only if 1) (above) is ireffectiva.
Open the pressurizer PORV's. ,
...-' . s
, 4
\.
.y l .
OC0003 20I s ..
- w w .. 't
\re 13
" N otAeto CANycN PCWER PLANT UNIT NO(S) 1 AND 2 R S ON DATE 2/8/84 PAGE 21 0F 23
( rg.a STEM GENERATOR TUBE RUPTURE ACTIONS COMMENTS
- e. If no means of depressurization e. Attempt to establish CCW are available, or if the and seal water ficw to depressurization did not the pump; however, if result in decreasing core CCW and/or seal water exit thermocouple temperatures, flow cannot be established, proceed to start a RCP.
THEN The pump must be started to move coolant through the core.
START one RCP if possible.
If the RCP fails after starting, replace the lost RCP with any remaining RCP.
m l
l .
DC0003 21I !
1 l
1
i NUMBER EP OP-3A c Asi.o cANYCN PCWER PLANT UNIT NO(S) 1 AND 2 REVISION 5 -
DATE 2/8/84 4
PAGE 22 0F 23 2
RE STEAM GENERATOR TUBE RUPTURE i
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I DC0003 22I itCS TEMPERATURE (*F) .
G W D
,--.m=w--r--
N CIABLO CANYCN PCWER PLANT UNIT NO(S) 1 AND 2 R ON '
OATE 2/8/84 I PAGE 23 0F 23
( STEAM GENERATOR TUBE RUPTURE riTa APPENDIX Z D4ERGENCY PROCEDURE NOTIFICATION
- 1. When this emergency procedure has bean activated and upon direction from the Shift Foreman proceed as follows:
- a. Designate this event an Alert. Notify plant staff and response organizations required for Inis classification by Emergency Procedure G-2 " Establishment of On-Site Organization" and Emergency Procedure G-3 " Notification of Off-Site Organization" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation."
- b. Designate this event a Site Area Emergency if steam generator tube leakage coincides with a loss of off-site power indicated by Appendix B of this procedure and inability to restore power to the non-vital 12KV and 4K busses (D and E). Notify plant staff I- and response organizations required by EP G-2 and EP G-3 in accordance with EP G-1.
- c. In the event inadequate core cooling is verified per Appendix C, reclassify this event as a General Emergency. Notify plant staff and response organizations requireo by EP G-2 and EP G-3 in accordance with EP G-1.
m OC0003 23I l
. l l
.T_. 3st3 Pacific Gas and Electric C0mpany NUMBER EP OP-8 REVISION 8 1 CEPARTMENT CF NUCLEAA PLANT CPERATICNS DATE 2/3/54 l CIABLO CANYCN PCWER PLANT UNIT NC(S) 1 AND 2 PAGE 1 0F 56
\ '
}1 TITLE.
EMERGENCY OPERATING PROCEDURE CONTROL RCCM INACCESSISILITY IMPORTANT TO APDACVED- YS 'M b PLANTMANAGEA) DATE SCOPE These instructions are provided to cover those conditions prevailing when operation from the Control Rocm is no longer possible due to fire, smoke, heat, chlorine, high radioactivity or other occurrences which make the Control Room uninhabitable.
Secticn A TO MAINTAIN THE PLANT IN HOT STANDBY - pg. 4 Section B TO TAKE THE PLANT FROM HOT STANDBY TO COLD SHUTDOWN -
pg. 12 -
Appendix A TO RE-ESTABLISH LTON AFTER A LTDN ISOLATION - pg. 32
i Appendix B TO USE NORMAL PZR SPRAY VALVES - pg. 33 Appendix C ENERGIZING NON-VITAL 480V BUSSES WITH THE EMERGENCY DIESEL GENERATOR - pg. 34 Appendix D TO TAKE THE PLANT FROM HOT STANDBY TO COLD SHUTDOWN USING NATURAL CIRCULATION - pg. 40 Appendix E AUXILIARY FEED PUMPS SUCTION SUPPLY FROM FIRE WATER TANK - pg. 53 Appendix Z NOTIFICATION INSTRUCTIONS - pg. 56 This procedure and changes thereto requires PSRC review.
SYMPTOMS Possible Annunciator Alams:
- 1. HIGH RADIATION (PK 11-21)
- a. Rad Mon Cont Rm Area 1
- b. Process Monitor Hi-Rad l I .
DC0060 III
otABLC CANYCN PCWER PLANT UNIT NC(S) 1 AND E fV ON 8 DATE 2/3/84 PAGE 2 0F 56 TITLE - CONTROL RCCM INACCESSIBILITY
- 2. CONTROL ROCM VENT (PK 15-06)
- a. Cont Rm Chlorine & Rad Monitor
- 3. FIRE / SMOKE DETECTOR (PK 10-10)
CBJECTIVES
- 1. Establish stable Hot Standby conditions from the Hot Shutdown Panel.
- 2. To provide instructions to allow the plant to be taken to Cold Shutdcwn condition from Hot Standby from outside the Control Room if conditions require it.
AUTOMATIC ACTIONS
- 1. Possible transfer to Control Room ventilation to Mode 3 (high Chlorine) or Mode 4 (Pressurization).
- 2. Possible start of the Emergency Diesel Generators (if offsite power is lost).
ACTION / EXPECTED RESPCNSE RESPONSE NOT OBTAINED
!!HEDIATE ACTIONS
- 1. Manually TRIP the reactor 1. TRIP the Reactor locally BEFORE leaving the at the Reactor Trip Control Room. Breakers,
- a. Verify the Reactor Trip
- 1) All Control Rod
- Bottom Lights ON (DRPI) l l 2) Reactor Power NIS-0ECREASING
- 2. , Verify tripped or manually 2. TRIP the Turbine locally
.~ TRIP the Turbine BEFORE at the Governor Pedestal.
leaving the Control Room.
- a. Verify all four STOP a. Verify turbine STOP '
valves CLOSED on turbine valves CLOSED by EH panel. observing actual valve ;
position at the turbine. .
l l
OC0060 211 l .
45 e
( TITLE- CCNTRCL ROCM INACCESSIBILITY i
i ACTICN/EXPEuto RESKNSE ESENSE NOT CBTAINED
- 3. Proceed to the hot Shutdown Panel.
SUBSEQUENT ACTIONS
- 4. STOP any dilution in progress. 4. Manually operate valves locally as necessary.
S. If condenser vacuum decreasing consider:
- a. Restarting a circulating water pump OR
- b. Securing Air Ejectors on the inactive half of the
NOTE: Certain loads (ASW and CFCU) auto start on auto transfer to startup powe r. NormalJy these loads cannot be shutdown until AUTO transfer is RESET but if the DC control power is removed from the ASW pump breaker after the breaker is opened locally it can be shutdown. The CFCU breakers must be opened locally to shut them down.
NOTE: The follcwing list of equipment should have their Control Switches piaced in the position described below BEFORE transferring to local control to insure a SUMPLESS transfer:
- a. PZR HTR GRPS 12 and 14 to the NEUTRAL position,
- b. The in-service LTDN Orifice Isolation valve CVCS-8149 A, 8 or C to the OPEN position,
- c. The NOT in-service LTDN Orifice Isolation valve CVCS81I 49 A, B or C to the CLOSED position.
- d. Boric Acid Transfer Pumps 11 and 12 to Low Speed.
CAUTION: Transfer of Boric Acid Pumps and PZR HTRS to local control removes them from their AUTO control schemes.
t t
DC0060 3II eg -
- D'Asto cANYCN ACWEA PLANT UNIT NOISI i: UMBER EP OP-8 1 AND 2 REVISION 8 DATE 2/. 34 PAGE 4 CF 56 TITLE CONTROL ROOM INACCESSIBILITY .i
. ACTICN/ EXPECTED ESPCNSE ESPCME NOT CBTAINED A. TO MAINTAIN THE PLANT IN HOT STANOBY
- 1. The following equipment is available for transfer to local control if Manual .
control is desired:
- a. Boric acid transfer pump 11
- b. Containment fan coolers 11, 13 and 14.
- c. 8149A&C (letdown orifice valves).
- d. HCV 142
- e. FCV 128 l f. 10t steam dump valves.
- g. LCV 110, 111, 115 and 113.
- h. CCW pump 11 and 13 l 1. ASW pump 12
- k. Pzr. Heater group 14
- 1. AFW pump 13
- m. LCV 108
- n. LCV 109
- 2. The following equipment must have their control transfer cutout switch CUT IN prior to transferring to local control:
- a. Located inside the 480V
! Bus F AUX relay panel:
- 1. Containment fan cooler 12
- 2. 8149B (letdown orificevalve)
- These items must have their control transfer relays hand reset when transferring control back to Control Room (in addition to being in remote position on transfer switch).
i DC0060 4II e9
- ciAsto CANYCN PCWEA PUNT UNIT NC(S) 1 439 g REVISION 8 DATE 2/3/84 PAGE 5 0F 56 i TITLE. CONTROL ROOM INACCESSIBILITY ACTION /Entuto PESPCNSE RESPCNSEPOTCBTAINEd
- b. Located inside the 480V Bus G AUX relay panel:
- 2. MOV 8104 (Emerg.
Borate Valve)
- 3. LCV 106
'4 LCV 107
- 5. BA XFER pump 12
- 6. CONTAI M ENT fan cooler 15
- c. Located at 4 KV Bus G
/ ,
- 1. CCW pump 12 l 2. ASW pump 11
- 3. Cent. Chg. pump 12
- e. LOCATED INSIDE 480V Bus 130 cutout switch panel.
- PZR heater group 12
- 3. Trip the Main Feedwater Pump Turbines and ensure that they go on Turning Gear once zero speed is reached.
- These items must have their control transfer relays hand reset when transferring control back to Control Room (in addition to being in I remote position on transfer switen). '
1 i
DC0060 SII "O e p
. --, ,, .a , . . , , -
DIABLO CANYCN POWER PLANT UNIT NO(S) 1 AND 2 S CN DATE 2/3/84 I PAGE 6 0F 56 ints CONTROL ROOM INACCESSIBILITY 1
- ACTION /EXPE~iED RESKNSE RESKNSE NOT OBTAINED l
l 4. Ensure that the Bearing 011 4. If required contact the j Pump, HP Seal Oil Backup Pump Electrical Maintenance and the Bearing Lift Oil Department for starting loads l
Pumps are running; and that locally.
the Main Unit Turbine goes on Turning Gear once zero speed is reached.
- 5. Maintain the Reactor at Hot Standby condition by:
- a. Controlling narrow range a. Control Steam Generator Steam Generators in the NR level manually.
normal operating band (approximately 80% actual level W.R.) with the Auxiliary Feedwater controls in AUTO.
- 1) STOP turbine driven Auxiliary Feedwater Pump if not needed for level control, pg]E: Refer to Figure #5 for determining Actual vs Indicated Steam Generator Level (attempt to maintain and actual SG level of 78% - 85% on the Wide Range indicator.
.e j DC0060 6II
~
oiAsto OANYCN ACwEA PLANT UNIT NOTS) 1 AND 2 ON 8 DATE 2/3/84
( PACE 7 0F 56
' TITts. CONTROL RCCM INACCESSIBILITY l
l
- ACTICN/EXFEuto PESPCNSE RESPCNSE NOT CBTAINED
- b. Verify PZR level being b. START a Centrifugal maintained in AUTO by a Charging Pump at the Hot Charging Pump. Shutdown Panel.
- 1) .STOP the Reciprocating Charging Pump using the control switch at the 4160V Bkr.
- 2) Manually adjust charging flow to control PZR level and Seal Injection using HIC-128 and HIC-142,
- 3) Maintain PZR level
/
. >20% to insure
\ '
- '- against a LTDN Isolation.
- 4) If LTDN Isolation does occur, restore LTDN per Appendix A.
- c. Control RCS pressure at c. Transfer PZR HTR GRPS 12 2235 PSIG by use of the and 13 to the Emergency Backup HTRS as needed. Power Supply, 480V Vital Bkrs 52-1G-72, 52-1H-74 NOTE: PIR HTR GRPS 12 and 13 on Emergency Power Supply can ONLY be controlled (when outside the Control Room) by locally closing or opening their breakers for pressure control.
- d. Verify Steam Generator d. Control Steam Generator pressure is being - pressure at 1005 psig by maintained at Manually operating the approximately 1005 psig 10% Steam Dumps.
by use of the Condenser Steam Dump. This will be an automatic function unless vacuum is lost in the condenser.
i
, I DC0060 7II
ciAsto cANYCN PCWEA *LANT t.;Nii Nots) 1 AND 2 hff0N 8 DATE 2/3/84 PAGE 8 0F 56 TirUE- CChTROL R004 INACCESSIBILITY d ACTICN/EXFECTED FESPCNSE RESPCNSE B0T OBTAINED
- e. Calculate the SCM for Hot and Cold XE Free conditions.
- 6. Establish or verify communications bet > gen the Hot Shutdown Panel (x1431 Unit 1,x2432 Unit 2]I
- a. Technical Support Center:
Rx3199foroperatori T) Outside telephone ex-change
- 2) ERFDS for additional plant monitoring capa- -
bility,
- b. Dedicated Shutdown Panel
((x4355 Unit 1, x2246 Unit 22 as necessary.
- c. 480V xital switchgear area jl x1372 Unit 1, x2497 Unit 2)J 4 KV vital switchgear d.{Ix1747 Unit 1,x2404 x2778x2706 Unit 2))
a rea.
- 7. Maintain SDM using method a.
or b. below (method a. is the preferred mechod):
- a. OPEN Emergency Borate a. OPEN Manual Borate valve, valve, CVCS-8104 from the CVCS-8471 and shift Boric j Hot Shutocwn Panel. Acid Pump to fast speed.
l l
- 1) Verify Boric Acid 1) Boric Acid flow on FI-1138 at concentration may be Hot Shutdown Panel. determined by either:
I DC0060 8II me e
l 34eto CANYON PCWEA P'. ANT UNIT NO<Si 1 AND 2
[ h fP OF-8 DATE 2/3/84 PAGE 9 0F 56 l I TITLE I CONTROL RCOM INACCESSIBILITY
- ACTICN/E E CTED FESK NSE FESPCNSE NOT OBTAINED
- a. Observing the Baron concentra-tion monitor near the secondary Sample Panel 85 el (this monitor is only valid if letecwn is in service) OR
- b. By sampling tne RCS.
- b. Boration to Hot Xe Free Condition using the BIT.
- 1) CLOSE and verify locally 51-8870 A & B and 51-8911 (BAST to BIT Recirc valves) by
/ securicg air to the
'- valve operator at Mech Pn1 74
- 2) Manually OPEN MOV 8803 A or B.
- 3) Manually OPEN MOV S301 A or B.
- 4) Manually CLOSE HCV-142 to bypass maximum flow through BIT. -
E: Seal injection to RCPs still required or verify CCW to Rc7 thermal barriers heat ' exchangers.
- 5) Based on a BIT flow rate of 120 gem flush the BIT for 15 min.
- 6) If additional boron is required, swap
, charging pump suction to the RWST (open HOV 8805 A and B). -
DC0060 911
+
eg #
l
)
1 I
1 A;;0 2 P OP-8 ci4eto cANYCN PCwEm oLANT VNiT NC S) ,
OATE 2/3/24 PAGE 10 0F 56 TITLE CONTROL ROCM INACCESS!SILITY ACTICN/DETS FESFChSE FESPCNSE BCT CETAltE
- c. Keep the PIR HTRS energi:eo curing the boration.
- d. Use PZR spray to maintain d. Control Auxiliary FIR RCS pressure and permote Spray by CPENING RCS/PIR Boric Acid CVCS-8145 at the mixing. See Appendix 8 Dedicated Shutccwn for operation of Normal Panel.
PZR spray valves, t0TE: Table 5.7-1 of Section 5 of the Technical Specifications limits tne numcer of unneatec auxiliary spray cycles if the spray water terrperature and pressurizer water temperature differential is >320*F.
- e. Verify Baron .
Concentration and good mixing of baron in RCS by se=pling:
- 1) RCS Hot Leg
- 2) PZR licuid
- 3) LTDN line g: Satisfactory mixing of boron throughout the RCS shculd be accomplished after 3-4 RCS Lcep Samples which should take about I hour.
- 8. Place Emergency Diesel Generator control selector switch on excitation cubicle to LOCAL position.
- a. Verify the AUT0/ TEST selector switch on local panel in the AUTO position locally in each Diesel Generator room.
O l OC0060 10!!
l .
i
- l ... . .
i OuSLO CANYCN PCWEA P'. ANT UNIT NC($) 1 AND 2 h)fff0N 8 DATE 2/3/84 PAGE 11 0F 56 I- TITL2 CONTROL RCCM INACCESSIBILITY ACTICN/EGeCTED FESKNSE RESPCNSE NOT CBTAIED
- 9. Place SU FDR breaker transfer switches to LOCAL position on cubicles. ,
- 10. If there was a loss of 0FFSITE power the Emergency Diesel Generator should start autcmatically and assume the vital bus loads.
- a. Verify the Emergency a. START the Emergency Diesel Generators STARTED Diesel Generators locally Automatically and are and energize the 4KV supplying the 4KV vital vital buses. (Requi res buses, operator locally at bus to parallel). If the diesel generator output breaker does not close I
due to a fire induced fault at the Control Room, open the switchgear door with a dedicated wrench provided for this purpose, and follow the instructions posted on the inside of the door to mechanically close the b rea ker.
- 1) 4KV Bus F, G and H voltage indication at the Hot Shutdown Panel.
- b. Shutdown unnecessary equip. not needed for current plant status.
t 5
DC0060 11II
NUMBER EP 07-8 DIABLO CANYCN PCWEA ALANT VNIT NC(s) 1 AND 2 REVISION 6 OATE 2/3/84 PAGE 12 0F 56 7 TLE CONTROL ROCM INACCESSIBILITY
. ACTICN/EGECTED hESKNSE RESPJ4SE NOT CBTMdD
- c. Verify that equipment c. Restart equipment locally with controls located at if necessary. If the 4KV Hot Shutdown Panel have pump loads cannot be restarted af ter transfer started due to a fire of power to Emergency induced fault at the Diesel Generators. Control Room, open the switchgear with a dedicated wrench provided for this purpose, and follow the instructicns posted on the inside of the coor to mechanically close the breakers
- d. Transfer PZR HTR GRPS 12 and 13 to the Emergency Pcwer Supply, 480V Vital Bkrs 52-1G-72, 52-1H-74.
(Refer to OP A-4A).
NQTE: PZR HTR GRPS 12 and 13 on Emergency Power Supply can ONLY be controlled (when outside the Control Room) by locally closing and opening their emergency power breakers for pre;*ure control.
- 11. Maintain HOT STANOBY until Control Room access is restored and control has been returned to the Control Rocm.
[0]{: If Control Room access is not restored rapidly, a decision must be reacned on HOW LONG to remain in HOT STANCBY and when to start cooling down to COLD SHUTDOWN. The basis for this decision is CST inventory. Refer to Figures 18-1 and 2 in volume 9 of the plant manual for guidance in making this decision. The copies of these figures at the end of the procedure are for information only.
B. TO TAKE THE PLANT FROM HOT STANOBY TO COLD SHUTOOWN FROM OUTSIDE THE CONTROL ROOM-
- 1. Containment entry may be
. required to accomplish .
various evolutions in this procedure.
I 1
1 1
OC0060 1211 l
. I
- @ e e
' 6 CIA 8LO CANYCN POWER PLANT UNIT NQ($) 1 AND 2 R ON DATE 2/3/84 PAGE 13 0F 56 TirLE- CONTRCL ROCM INACCESSIBILITY ACTICN/E9ECTED ESKME ESKNSE NOT CBTAINED
- a. Notify the Rad / Chem Dept.
for assistance as necessary in the containment entry.
- 2. Notify the !&C Dept. for assistance to execute certain steps in the procedure.
- 3. Calculate the SOM for Cold XE Free Conditions if not previously calculated and borate as necessary,
- a. Refer to Section A Step 7 of the procedure for preferred method of Boration
, 4 Sample the RCS & PZR to l
ensure boron concentrations are equalized and adequate for. cold shutdown.
- 5. During the cooldown maintain RCS temperature and pressure within the operating bands of Figure 6 at the end of the procedu re.
- a. Remote readout of the boron analyzer is availabl~e at the secondary sample panel area 85' El. -
-- (this monitor is only ,
valid if letdown is in service).
t CC0060 13II .
4
OiAsw CANYCN PCWEA P1. ANT UNIT NC(S). 1 AND 2 h' g fPOP-6 OATE 2/3/84 PAGE 14 0F 56 tit d CONTROL ROCM INACCESSIBILITY I ACTION /EECTED RESPCNSE RESPCNSE NOT OBTAINED
- 7. De-enefgize all PZR HTRS,
- a. OPEN and RACK OUT 8krs.
- 1) Proportional Htrs (52-130-5)
- 2) Group 13 (52-13E-2)
- 3) Group 12 and 14 I
control switch to 0FF.
- 8. ' verify that all Control Rod 8. START all fans.
Drive Mechanism cooling fans *
,are in operation.
- a. If CROM cooling fans are NOT in operation due to loss of Non-vital power GO to Appendix C to Re-energize tne Non-Vital Buses.
CAUTION: Appendix c will not ce carried out without the approval of tne Plant Superintendent.
. b. If CROM cooling fans can not be operated continue with the procedure. This condition is significant during the Natural
! Circulaticn cooldown and i
shall be addressed in Appendix D.
1 OC0060 1411 S
- *O O
. NUMBER EP OP-8 OiAsto cANycN PCWEA PLANT UNIT No(s) 1 AND 2 REVISION 8 DATE 2/3/S4 PAGE 15 0F 56 I
nTLE CCNTR'L 0 ROCM INACCESSIBILITY ACTICN/EX.C9.ito FESKME RESKNSE NOT OBTAINED
- 9. START RCS cooldown.
- a. With force'd Reactor a. If in a Natural Coolant flow do NOT Circulation Mode GO TO exceed a 75'F/HR cooldown APPENDIX 0 for cooldown rate. A 50*F/HR cooldown instructions.
rate is reconinended.
- b. Slowly increase pres- b. If pressurizer level surizer level and maintain decreases to <22 STOP cool-pressuri:er level t 50%. down until pressuri:er level is recovered.
NOTE: During cooldown, actual PZR level can be determined by using Figure 4 at the end of the procedure. Indicated level at the Oedicated Shutdown Panel (LI-406).
CAUTION: When using the steam generator 10% dumps for cooldown, maintain steam generator pressures balanced to avoid an SI on steam generator differential pressure.
- c. To start the cooldown c. As an alternate means of SLCWLY increase the rate cooldown (if condenser of steam flow through the available) use handjack 10: Steam Dumps. on 40% steam dump valve.
- d. Verify Auxiliary d. Manually throttle Feedwater System is auxiliary feedwater flow, automatically as necessary.
maintaining Steam Generator Narrow Range level at 333.
- e. Monitor the Condensate Storage Tank.
- 1) If CST level is low, and condensate pumps are available restore CST level by pumping down the condenser e hotwell.,
0C0060 1511 4@ g a
- iAetc cANycN PCWEA ALANT UNIT NCiS) 1 AND 2 REVISION 8 OATE 2/3/84 PAGE 16 0F 56 TITLE CONTROL ROCM INACCESSIBILITY
/
' ACTICNS/EXF9~TED FESKNSE RESENSE NOT CBTAINED
- source.
- f. Reduce RCS pressure using f. If Auxiliary PZR Spray is PZR Spray, See Appendix B preferred OPEN CVCS 8145 for Using Normal PZR at the Oedicated Shutdown Spray. Panel.
NOTE: If it is desired to secure normal charging to the RCS, CLOSE C7CI-8146 by installing a pneumatic jumper around SV 200 in FM 45 in Containment. .
- g. Maintain sub-cooling margin >35*F as determined by the following:
- 1) STEAM TABLES
- 2) PI-406 RCS Wide Range Pressure (Oedicated Shutdown Panel.)
- 3) TI-406 RCS Wide Range Loop 1 Hot Leg Temperature (Oedicated Shutdown Panel.)
- 4) TSC(ERFDS)
- h. During Pressure Reduction OPEN additional orifices
~
as necessary to maintain desired letdowa flow.
OC0060 16II ,
e9 O
l l
l DIABLO CANYCN PCwEA *LANT UNIT Nois) 1 AND 2 R ON CATE 2/3/53 PAGE 17 0F 56
( TITLE- CONTROL ROCM INACCESSIBILITY ACTICNS/EGEutu PESKNSE PESPONSE NOT CBTAINED CAUTION: AUTO and Manual SI is NOT available with PY 1115 and PY 1418 0 FEN. Station an operator at these breakers in communication with the Hot Shutdcwn Panel. Deactivation is a violation of the Technical Specifica-tion and must be approved by a Senior Reactor Operator. This action re-quires inmediate notification of the NRC.
- 10. When RCS temperature has been reduced below 543*F (as indicated at the Oedicated Shutdown Panel) OPEN the folicwing instrument AC breakers to inhibit HI steam line flow and Lcw PZR .
pressure SI.
- a. PY 1115 Train A Output
. Cab.
- b. PY 1418 Train B Output Cab.
- 11. Reduce primary heat load by reducing the number of RCPs in service.
- a. As a minirnum RCP should remain No. 2 in service to provide Normal PZR Spray Control.
- b. TRIP the RCPs to be removed from service locally at the 12KV Bkr.
cubicle.
observed periodically l I
during cooldown.
i l
OCCC60 17I1 l
l NUMBER Ep OP-8
- DAsto CANycN PCWEA PLANT UNIT NO(S) 1 AND 2 REVISION 8 DATE 2/3/84 pAGE 18 0F 56 l TiTui CCNTROL ROCM INACCESSIBILITY g )
- AC~ICNS/EXH-utv ESPONFE RESF0NSE NOT OBTAIBS NOTE: Maintain <25'F AT between loops. The selectable C-id Leg or not Leg temperature of RCS loop 1 is directly indicated at the Oedicated Shutdown panel. The cold leg temperature for loops 2, 3 and 4 can be determined as a function of steam generator pressure and the steam tables.
- 12. When RCS pressure decreases 12. If a containment entry is below 1000 psig close the required the accumulator accumulator outlet valves valves may be manually (one at a time) by performing closed locally.
the following for each of the following breakers:
MOV 8808A 52-1F-46 l MOV 8808B 52-1G-07 -
MOV 8808C 52-1H-14 MOV 88080 52-1G-05
- a. Lay down close contactor seal-in wire on terminal
- 4 (inside bkr cubicle).
- b. Close breaker.
- c. Depress close contactor.
- before breaker is opened, close valve fully using local handwheel,
- e. Re-lift and tape seal in wire on terminal #4.
- f. Closure of these valves can be verified locally
.... depending on ALARA considerations.
DC0060 18II 99 e
~
- iAsto CANycN PCWEA PLANT UNIT NCtSi 1 AND 2 DATE 2/3/84 PAGE 19 CF 56 TiTuE CONTROL ROCM INACCESSIBILITY
~ ACTICNS/ESEutd FESFCNSE RES D SE NOT CETAINED
- 13. Continue to cool RCS until the temperature is less than 350*F and pressure is below 390 psig. Maintain pressure by reducing spray flow and energizing PIR heaters.
14 While preparing RHR system '
for service contact I&C Depart. m ent to perform the following to expedite RHR operation.
s g b. Install pressure gauge upstream of PCV 135 to monitor. letdown press.
- 15. Place RHR system in service on Recire.
- a. Manually CLOSE MCV 8809 A
& B (RHR to CL 1, 2, 3, &
4).
- b. Cut in control transfer .
relays cutout switches on the RHR pump brk.
cubicles.
- c. START RHR pumps locally at their switchgear cubicles.
- 1) Observe recire flow established on FIs located outside RHR pump rooms.
t t
DC0060 191I
~
'M 3ER IE CP-8 CIABLC CANYON POWEA PLANT UN#7 NCtSi I AND 2 REVISION 8 DATE 2/3/84 PAGE 20 0F 56 TITLE CCNTROL ROCM INACCESSIBILITY l
- NOTE: 00 NOT allow RHR pumps to run lenger than 30 minutes on Recire.
ACTICNS/EXPEuto FESPCNSE FESPONSE NOT CBTAINED
Cene.
- a. OPEN RHR-8741
- b. Resample RHR recire and reanalyze for Baron Conc.
l c. When RHR Baron Conc. is t equal to or greater than RCS Boron Conc. CLOSE RHR-8741.
- 18. Shutdown BOTH RHR pumps.
- 19. CLOSE MOV-8980 using
- handwheel.
- 21. OPEN MOV-8702 and 8701.
- a. Open by momentarily pushing the cpen contactor, located inside the breaker panel.
9
,e DC0060 20!I
ciasto CANYCN PcWEA *LANT Led:T h4hs) 1 AND 2 RE ON l DATE 2/3/84 PAGE 21 0F 56 I T3TLE CONTRCL ROCM INACCESSIBILITY
. fCTE: The valve is full open when the open contactor drops out. This snoulo take abcut 100 seconds.
ACTICNS/EGEucs RESRASE RESPJ4E NOT OBTAINED
- b. OPEN the valve breaker when the valve is full open.
- c. Observe local pump suction pressure indication (which shculd increase to RCS pressu re) .
- a. Open by closing air supply valves at air
(
are ATC/FO).
- 23. Start al RHR pump on recire.
- a. Monitor rec 4- ~' w locally.
- a. Observe . . .
indicator <CS t.
of RHR NX .ocated
- AHR HX room).
t DC0060 211I G
- 9 .
1 Aso g NUMBER EP CP-8 OIABLO CANYCN ACWEA DLANT UNIT Noisi REV!S:Ch 8 CATE 2/3/84 PAGE 20 0F 56 71TLE CONTROL RCCM INACCESSIBILITY ACTICNS/E6ECTED FESPCNSE FESFCNSE NOT OBTAINED
- 25. Start #2 RhR pump as per steps 23 and 24 above (except using MOV-88098).
- 26. Slowly open MOV-8809A & B to ccmmence further cooldown of RCS.
- 27. Open RHR Hx Manual Crosstie Valves RHR 8734A & B and estaolish RhR to letdewn by fully opening hCV 133.
- 28. Regulate letdcwn flow by controlling PCV 135.
- 29. When condenser vacuum can no longer be m intained, proceed as follows:
- a. Condenser vacuum can be observed at the main unit turbine pedestal on PI 256, or on local indicator in PM 177 on 104' El. (near PY 17).
- b. Terminate condenser steam dump (if in use),
- c. Break condenser vacuum.
- d. Shutdown the air ejectors and secure shaft seal -
system on the main feed pumps and main unit
- l turbine. -
l OC0060 22I!
e .
NUf:8ER EP OP-8 014eL0 cAsycN #CWEA 8LANT UNIT NCis) 1 Aht g REVIS:0N 8 OATE 2/3/84 PAGE 23 0F 56
' TITLE CONTROL RCCM INACCESSIBILITY
- ACTICNS/EGECT8 FESKNSE PESENSE NOT OBTAlt S
- 30. Open DC Control power to SI pumps at breakers 52-HH-15 and 52-HF-15 and manually shut valve MOV-8835. (SIto C.L. 1, 2, 3 ano 4).
- 31. Reduce letoewn flow less than charging flow to begin increasing PIR level to approx. 90%.
- 32. When RCS cold leg temperature has been reduced to 323'F perform the following:
- a. Verify only one charging pur.o operable.
- b. Verify both SI pumps inoperable.
- c. Verify MOVS 8701 and 8702 are CPEN.
- d. Rack out the valves and inoperable pump.
the control rocm is '
re-established.
- 33. When RCS temp. is reduced '
below 200'F. fill the steam generators all the way ar4 place in wet layup. -
_ j
% 9
\
^ -
Y T 7 g. .
S
\
CC0060 23!!
4 $
.Q
otASLC CANYCN PCwEA PLANT UNat NoiS) 1 At;D 2 R S ON CATE 2/3/84 PAGE 24 0F 56 TITLE CCNTROL RCCM INACCESS!BILITY' )
ACTIONS /E(PECTED PESPCNSE FESFCNSE NOT OBTAltE; 34 Ensure shutdown margin remains greater than 1.0% A K/K.
- 35. Fill the PZR.
NgTE: While filling and cooling down the PIR with auxiliary spray, ensure the PIR cooldewn rate does not exceed 200*F/HR. ,
- 37. Continue to cooldown the PZR until the PZR temp. is below 150*F.
CAUTION: Depressurizing the RCS before the entire RCS is below 200*F may result in void formation in the system.
- 38. Continue Cooldown of Inactive Portion of RCS:
- a. Upper head region - ALL a. IF fans NOT running THEN CROM FANS RUNti!NG. M NOT depressurize RT until upper head cools to less than 200*F (approximately 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> after RHR system is placed in service).
- b. Steam Generator U-Tubes - b. 00 NOT depressurize RCS CONTINUE DUMP!NG STEAM untti steam generators from all steam generators have stopped steaming, until it is VERIFIED that they have stopped i steaming.
l OC0060 24!!
s NUMBER EP GP-8 CIASLC CANYCN PCWEA PLANT UNIT NCtS) 1 AND 2 ' REVISION 8 DATE 2/3/84 PAEE s
25 0F 56
' 's TITLE CCATROL ROCM INACCESSIBILITY .
' ACTICNS/EXPEuto RESRESE RESR'NSE NOT CSTAINED -
- 39. Reduce the system pressure to approx. 50 psi by reducing charging ficw and increasing ,
RHR letdown flow.
- 40. Shutdown the charging pump.
- 41. Stop any spray flow in ,
x progress and close the RHR letdewn valve HCV 133. ,
- 42. Leave the RHR system in 's. "-
service recirculating from hot leg 4 to the cold legs.
- 43. After approximately 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> '
of cooling, cne RHR train and relateo auxiliary systems may be shut down. The remaining RHR train must remain in s service.
S A
'N k
e
\
b r
~. ,
, s DCC060 2SII . s
+% 9 H % 6 l - -
- - - - - L, - , ,J:
l l
'NUP"5 RE'li ION 5 CATE 2/3/84 PAGE 26 0F 56 TITLE CONTRCL RCCM INACCESSIBILITY FIGURE IF-1 REQUIRED CONDENSATE STORAGE CAPACITY AS A FisNCTION OF STANDBY TIME AND C00LDCWN TIME (RATED Mwt =3423) 73 -
1'
,- ,/
s' 1' s' 1'
, 1' -
,' ,' . 5
, . ~ 5 $' ,
s s E ,
s' ,' d n 1' -
f 'f;' ,
),
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3 ,
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y h -
k 5 ,' ,' 1 E.
,1 I
z'
^' - * ~ ~ ~
23 l 3 2 3 4 5 6
. TIME AT HOT STAN08Y (HOURS) FIGURE IB-1 DC0060 26II ee
- I
. i
~
OtABLO CANYON PCWEA PLANT UNIT NO(S) 1 AhD 2 INN' REVISIC .,,. po ON8 CATE 2/3/84 J PAGE 27 0F 56
! TiruE CCNTROL ROCM INACCESSIBILITY REQUIRED C0t10ENSATE LEVEL TO MAINTAIN A GIVEN HOT STANDBY TIME (RATED MW t
= 423) s'
/
m
/
2 SG
=
at
(
= T E
50
' S g '
- ?
E '
- = e i
E
'O < )-
E 2
- a
=
E 3
s '
5 20
?
5 F
10 emr 3 4 S' 12' 16 20 .:4 HOT STANDBY TIME (HOURS) FIGURE IB-2 1
DC0060 2711 99
-_------ --- _- - . - - - ,,.n.,,., y . -
l I
t; p.. .w :P On. .e DIABLO CANYCN ACWE A PLANT UNIT NC(S) 1 ANC 2 REVISIOi\ 8 DATE 2/3/84 PAGE 28 0F 56 TITLE CONTROL ROCM INACCESSIBILITY ;
t REQUIRED LEVEL OF CONDENSATE TO C00LDOWN TO 350F E: ?H s ges:n demicts enfy the concensate
, , sesrage cacactty recuirec fer tre coolcew.
10 2 --
3 ..
c : ...
E 4O#2,._s.: i ..
N.
y __3.
^ - 1 ,:___':-
_} +0
^. '. :: -:
=3 5- _ 13 -1 f= :4
, 22 -
-, ~: p -n F -
E- :s .
_- ;E -c
- 5 - -
2 .
- I pq c.-
30 .4,* : .' '
5
=:_: :3
.-M. ;. .'
s g .
I2
-=
o _-
55 -
E.
E-i 5
20 10 2 4 6 8 to .2 3
. , . DURATION OF C00LDOWN TO 350*F (HOURS) FIGURE IB-3 l
. t l .
OC0060 28II e
e W .
l I
I i
- lABLO CANYCN DCWER ALANT UNIT NCtSi 1 AND 2 REVISICN 8 DATE 2/3/84 PAGE 29 CF 56
' MLE CONTROL ROCM INACCESSIBILITY e' e w w T w F %
- 3 m e __
l i o'
y - y}-- r. .
_ s; --
2 yp _. f - Q ..p: g - ._.
~
. - e __,.g.
,_g,.,.
' t ' ' 2___- .- . -
- ' ' / f-, . ./
/ _y /, _ , _-.. -
I o
- I /
iCC' / / / /
t' - / / /
o i / / s
! / / '
ec -
- * / /
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/ / / /
I / _I _,
fg --
/ ;/- , / --
A 5
/ -// ,' / g i / _
. / [ /
- ~ . - - - -
c' as 70 g , ..-r ,-,- ,' y- /~ . -
-..=-
~#**
.e T
, / . **
, ,/ ,/ ,
i , y ? ! / r I w t // / / - - ~ - = -
, , / ,
-d <o o // / / -e .
m o i t / r /
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-/,1f'. , . -- * ^.~ ' . ..._~'"..--.*~...'.'
,g q -- -- -.---.
l e-O 80 ad 10 40 sco
~
a L3 to to do 40 INDICATED LEVEL (7, OF SPAN)
LI-406 PRESSURIZER LEVEL CORRECTION CURVES FOR PRESSURIZER PRESSURES (PSIG)
~
(CONTAINMENT TEMPERATURE =100*F EXCEPT AT : O PSIG, 70*F)
FIGURE 4 i
DC0060 29II .
- .O g
_. . _ . _ _ .._ _ -._ . . . . ~ , . _
OIABLC CANYCN ACWEA *LANT UNIT NO(S) 1 Aug f.UMSER EP OP-6 REVISI0tl 8 DATE 2/3/84 PAGE 3C CF 56 MLE C0:4 TROL ROCM It1 ACCESSIBILITY p
_ . w .a _
w .! .-
=.-.ce.r . ,e.o
., rc.-.c .- . c, . s. -
1- ..._, . .-
, j .i j / /
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, . / / / J /* ,
s , e o r i / s /
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/
o f s_ /
_/
> * / / / ' /
- - / / /
e
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e ! / / ,~/.
- /
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t
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, y. . . fj . . ._ i i s /
g s.
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- e p - ^-
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//, /
u so u, / / .
w . .
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a d_ .
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IO 4 .
- ~
=a ///-// + 6
. /// //
- n s // *
>=
,g ,e s //
// i
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- /
t
- / . '/
)C Vf
.. _' i 10
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,f l Q L-.
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~
7 .l ... . . l. T '. .~.: ~:.'~l '.
o io to 30 *o 10 60 to to 10 m INDICATED LEVEL (% OF SPAN)
STEAM GENERATOR LEVEL (WIDE RANGE) CORRECTION CURVES i
FOR STEAM GENERATOR PRESSURE (PSIG)
..- (CONTAINMENT TEMPERATURE-100'F)
FIGURE 5 l
l DC0060 30!! !
i 1
tiLFBER EP OP-E l OtABLO CANYCN ACWEA Pt. ANT UNIT NCiS) 1 AND 2 gg./!SION 8 DATE 2/3/84 PAGE 31 CF 56 I
- ;E CONTROL ROCM INACCESSIBILITY 2500 TECH $PEC L3 TIT CORRECTED ~ '
POR INSTRIMDIT i 2000 N "--
E l15c0 E
3ATURATICN 1000 1
PCRV Law
$E* POINT RELIEF PRESS 500 0*F/hr Z$*F/hr SC'F/hr MIN TD9
, FOR PCRV 100*F/hr LOW SETPOINT PROTICTIDM (323*F) "AI TD9 FOR RHR CPERATICN 100 2C0 3C0 400 500 6C0 RC3 TEMPERATURE ('F)
FfGURE 6 -
t e
DC0060. 3111
CIABLO OANYCN PCWE A PLANT UNIT NO(S) 1 AfiD 2 y g DATE 2/3/84 PAGE 32 0F 56 TITLE CONTROL ROOM INACCESSIBILITY f
- APPENDIX A LETDOWN ISOLATION Should letcown isolation occur due to low PZR level, proceed as follows:
- 1. Place control switch (s) for LTDN orifice valve (s) in CLOSED position.
- 2. Re-establish PZR level via charging flow control.
- 3. At nuclear auxiliary relay rack "B", depress and hold in energized position relays 33aoX / LCV 459 and 33aoX / LCV 460 for approx.10 seconcs.
NOTE: Relays 33aoX / LCV 459 and 33aoX / LCV 460 are located in the top right hand corner of RNARS (cable spreading rm.
128' el.) and are appropriately labeled.
- 4. Open letdown orifice isolation valve (s) as required from the hot shutdown panel.
- 5. Check letdown flow re-established.
- 6. Restore Group I Pressurizer Heaters by reclosing 52-130-05 locally.
l DC0060 32II g
G P OP-8
- iast.o cANycN PCwEA ALANT UNIT NCi$) 1 AND 2 DATE 2/3/84 !
PAGE 33 0F 56 I i ilTLE CONTROL ROCM INACCESSIBILITY
~
APPENDIX B PRESSURIZER SPRAY ACTUATION
- 1. This method uses a normal pressurizer spraf valve and requires a RCP associated with its respective spray valve tp be in operation.
- a. To use PCV 455A (Loop 1):
1), Contact the I&C Dept. and have them disconnect the output of PC 455G in Hagan Rack 19 at TB H leads 49 and 410, and install a 4-20 ma current source (Transmation model 1040 or equivalent) to the disconnected leads. This will allow for modulation of PCV 455A.
- 2) Establish phone communications between the Hot Shutdcwn Panel and Hagan rack area.
- 3) Increasing current to the valve will cause increased
- opening of the valve.
\ 4) When the valve is closed and operation of the valve is not required, turn off transmation unit.
- b. To use PCV 455B (Loop 2)
- 1) Contact the I&C Dept. and have them disconnect the output of PC 455F in Hagan Rack 19 at TB H leads #5 and #6, and install a 4-20 ma current source (Trasmation model 1040 or equiv.) to the disconnected leads. Th.is will allow for modulation of PCV 4558,
- 2) Establish phone communications between the Hot Shutdown Panel and Hagan rack area.
- 3) Increasing current to the valve will cause increased opening of the valve.
- 4) When.the valve is closed and operation of the valve is not required, turn off transmation unit.
+
D e
DCC060 33II S EO O
I
- lABLC CANYCN ACWEA PLANT UNIT NO(Si 1 AND 2 f)fff0N DATE 2/3/54 PAGE 34 0F 56 8
TITLE CONTROL ROCM INACCESSIBILITY
- APPENDIX C ENERGIZING NON-VITAL 480V BUSSES WITH DIESEL GENERATOR DISCUSSION This procedure is written using the 12 aiesel generator as the sour:e of power for the non vital bus. This does not preclude the use of 11 or 13 diesel generator in which case the buses and breakers unique to the 11 or 13 diesel generator would be substituted for the respective diesel generator buses and breakers.
PROCEDURE
- 1. At 4KV Bus G Switchgear 1. Leave the 480V M.C.C.
Room, remove the non-essential connected, transfer to loads from 4KV Bus G. recundant pumps on 4KV busses
. F or H if possible.
- 2. At 4KV Sus G Switchgear Room:
- a. Open S.U. power to vital ,
buses F. G, H 52-HG-15.
- b. Verify cut in all 1-2 D.G.
Protection service.
- 3. At the 12KV Switchgear room perform the following:
- a. Open or check open 52-VU-14, S.U.
- Transformer 1-2 Feeder ACB. Then open the DC l control power.
O 9
CC0060 34II
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oiABLC CANYCN PCwEQ PLANT LNIT NC(S) 1 AhC 2 RhfffCr CATE 2/3/84 PAGE 35 0F 56 I
nTLs CONTRCL ROCM INACCESSIBILITY
- 1) 52-HE-2 AUX. Feeder to 4KV Bus E.
- 2) 52-HE-3 S.U. Feeder to 4KV Bus E.
- 3) 52-HE-6 No. 2 Heater Drip Pump ACB.
- 4) 52-HE-11. Condensate and Booster Pump 12 ACB.
, 5) 52-HE-9, Condensate
( '
and Booster Pump 13 ACB.
- 6) 52-HE-12, 480V Bus 15E Feeder ACB. -
- 7) 52-HE-4, 480V Bus 13E Feeder ACB.
- 8) 52-HE-5, 480V Bus 12E Feeder ACB.
- 9) 52-HE-8, 480V Bus llE Feeder ACB.
- 10) 52-HE-7, Station Service Feeder to 500 KV Swyd.
- c. For the following ACB's on 4KV Bus 0 OPEN or check OPEN the ACB THEN 1 OPEN the DC Control l power. I
- 1) 52-HD-14 S.U. Feeder
- to 4KV Bus D
~
OC0060 35II e
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1 l
- 4sto cANYCN PCwEA PLANT UNIT NOiS) 1 AND 2 g CATE 2/3/84 PAGE 36 0F 56 MTLE CONTROL RCCM INACCESSIBILITY )
. 2) 52-HD-15. Aux. Feecer to 4KV Bus D
- 3) 52-HD-7, Condenser Vacuum Pump ACB
- 4) 52-HD-9, Condensate and Booster Pump 1-1 ACB
- 5) 52-HD-11, Station Service Feeder to 230KV Swyd.
- 6) 52-HD-8, 480V Sus 14D Feeder ACB 4 At 480V Bus 110, open all 480V breakers except 52-110-02. .
Verify tie breaker 52-11DE is
. open.
- 5. At 480V bus 150, open all 480V breakers exceot 52-150-02, verify tie creaker 52-15DE is open.
- 6. At 480V bus 120, open all breakers except 52-12D-02, 52-120M a7no e -12DJ. Verify tie breaker 52-12DE is open.
- 7. At 480V bus 12J. open all 480V breakers.
- 8. At 480V bus 130, open all 480V breakers except 52-13D-02.
Verify tie breaker 52-13DE is open. Cut 'out DC control to i pressurizer heater ACB's l 52-13D-05, 52-130-06.
- 9. At 480V Bus 12M, open all 480V breakers except 52-12MD.
Verify tie breaker 52-12MN is open.
l i
i DC0060 3611 eg .
NLMBER EP OP-E
~iaato CANYCN PCWEA 8LANT UNIT NCIS) 1 AND 1 R[y!$ { Q7, 8 DATE 2/3/84 pAGE 37 CF 56 I
firLE CONTROL RCCM INACCESSIBILITY
- 10. At 4KV Bus G, manually close 52-HG-14, start-up feeder to Bus G.
- 11. At 4KV Bus 0, manually close 52-HD-14, start-up feeder to Bus 0.
- 12. At 4KV Sus E, manually close 52-HE-3, start-up feeder to Bus E.
- 13. Locally close 52-HG-15 to energi:e 4KV Bus O fecm 1-2 diesel generator. Closely watch diesel generator during
- this operation for any sign of instability.
NOTE: There will be a short lost orge on the Diesel Generator as the
(- startup transformer 12 it energized.
LAUlluN: If tne ciesei generator appears unstacle curing tnis step or at any time beyond this point in the procedure, immediately open 52-HG-15 to separate the ciesel from the nonvital system.
14 Locally at the switchgear energi:e the 480V buses by the following actions:
- a. Close 52-HD-10 to energi:e 480V Bus 110.
- b. Close 52-HD-12 to energize 480V Busses 120, 12M, 12J.
- c. Close 52-HO-13 to energize 480V Bus 130.
- d. Close 52-HD-6 to energize 480V Bus 150.
e DC0060 37!!
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I NLMBER EP OP-E OiAsto CANYCN DCWEA *uNT UNIT Nots 1 ANO 2 REV!SICN 8 OATE 2/3/84 PAGE 38 CF 56 TITLE CONTROL ROCM INACCESSIBILITY ;
- 15. Make available, rack in the breakers and start the follcwing equipment, if necessa ry,
- a. Plant air compressors,
- b. Control rod drive shroud Coolers.
- c. Service cooling water pump.
- d. Turnine-generator lif t cur.o. turning gear drive.
Place turbine on gear if pcssible.
- 16. If the 500KV and 230KV Swyd compressed air systems need returned to service perform the following:
) a. Locally at 4KV Bus E .
. manually close 52-HE-7.
- b. Dispatch an operator to the 500KV Switchyard to verify closed or CLOSE the local 4KV bus feeder breaker in the 500KV switchyard,
- c. Operator should also verify 480V bus is energized and 500KV '
switchgear compressed air system is available.
- d. Operator should verify 230KV yard 4KV bus is energized via the .
, emergency tie cable and
- its compressed air system is available.
O e
DC0060 38!!
ee e
NUMBER EP 0P-8 Oi4sto c4NvCN #CWEA PLANT LNif NCiS) 1 At;0 ', REVIS!0fi C CATE 2/3/84 PAGE 39 0F 56
( TirLE CCNTROL RCCM INACCESSIBILITY
- 17. Additional equipment deemed necessary may be started at the discretien of the Shift Foreman. During any new operations close attention should be paid to diesel generator conditions. .
e s
f OC0060 3911 9 i
1 ANg g NUMBER EP 09-8 c'ABLC CANvCN PCWEA *LANT UN1? NCis) REVISION 8 DATE 2/3/84 PAGE 40 CF 56 mLE CONTROL RCCM INACLwSSIBILITY ,
- APPENDIX 0 TO TAKE THE PLANT FRCM HOT STANCBY TO COLD SHUTCOWN FROM OUTSIDE THE CCNTROL ROOM USING NATURAL CIRCULATION.
PREREQUISITE This Appendix procedure assumes all conditions up to and including Section B, Step 8 of the Operator Actions of EP OP-8 Control Room Inaccesibility have been met.
ACTICN/E9ECTED PESRASE PESPCNSE NOT CBTAINED
- 1. START RCS Cooldown.
- a. Maintain cooldown rate less than 25'F/HR.
- b. Slowly increase b. If pressurizer level decreases pressurizer level and to <22% STOP cooldown until maintain pressurizer level g50%.
NOTE: During cooldown, actual PZR level can be determined by using .
TTgiTre 4 at the end of the procedure and indicated level at the Oedicated Shutdown Panel (L1-406).
cal]TICN: When using the steam generator 10% dumps for cooldown, maintain steam generator pressures balanced to avoid an 51 on steam generator differential pressure.
- c. To start the cooldown SLOWLY increase the rate of steam flow through the 10%.$ team Dumps.
- d. Verify Auxiliary Feedwater System is automatically maintaining
. Steam Generator Narrow Range level at 33%.
l l .
? -
I 0C0060 40!!
- l ciasto cANycN ACWEA *LANT *'iT Noisi 1 AND 2 lf')lff0N 8 OATE 2/3/84 PAGE 41 0F 56 TITLE CONTROL ROCM INACCESSIBILITY ACTICN/EGECTED ESPCNSE ESKNSE NOT CSTAlhED
- e. Monitor the Condesate Storage Tank.
- 1) If CST level is low, and condensate pumps are available restore CST level by pumping down the condenser hotwell.
- 2) At 10t in the CST refer to Appendix E of this procedure to shift CST suction to an alternate source.
- 2. Check RCS Hot Leg
.,- g Temperature:
- a. RCS Hot Leg temperature - a. DO NOT proceed until RCS LESS THAN 550*F (as Hot Leg temperature is l fndicated at the less than 550*F.
Dedicated Shutdown Panel).
CAUTICN: AUTO and MANUAL S1 is NOT available with PY 1115 and PY 1418 OPEN. Station an operator at these breakers in communication with the Hot Shutdown Panel. Deactivation is'a violation of the Technical Specification and must be approved by a Senior Reactor Operator. This action requires immediate notification of the NRC.
- 3. When RCS temperature has been reduced below 543*F ( as indicated at the Oedicated Shutdown Panel) OPEN the
~
following instrument AC breakers to inhibit H! steam
- line flow and Low Pzr
. pr'es su re S t .
i e
DC0060 4111
~ . ;
l
' ACT:CN/EGCCTED PESPCNSE FESPCNSE NOT CbTAINED
- n. PY 1115 Train A Output Cab.
- 3. PY 1418 Train B Output Cab.
4 Commence depressurizing the RCS to approximately 1865 asig.
- 3. Depressurize RCS using pressurizer auxiliary spray, CVCS-8145 (Cedicated Shutdown Panel).
aNOT~: Table 5.7-1 of Section 5 of the Technical Specifications limits the number of unheated auxiliary spray cycles if the spray water temperature and pressurizer water temperature differential is >320*F.
- 5. Maintain the following RCS conditions:
a.. RCS pressure - about 1865 psig.
- b. Pressurizer level - about 50t.
- c. RCS cooldown rate - Less than 25'F/hr.
- d. Less than 25'F AT between loops as determined by TI-406 and Steam Generator pressure
' for selected to Loop 1 Cold Leg and loops 2. 3 and 4 OC0060 4211 99 o
~
CHA8LO CANYCN PCwEA *LANT uhuf NotSi 1 AND 2 lf(lffCN 8 DATE 2/3/84 PAGE 43 0F 56 I
TITLE CONTROL ACCM INACCESSIBILITY ACTICN/EGECTED RESPCNSE RESprGSE NOT CBTAING
- 6. Verify RCS cooldown: ,
- a. Wide Range Loop 1 Hot Leg RTD temperature-trending down (TI-406 at Dedicated Shutdown Panel).
- b. RCS subcooling -
increasing (minimum of 50'F) as determined by:
- 1) STEAM TABLES
- 2) PI-406 RCS Wide Range Pressure (Dedicated .
Shutdown Panel).
- 3) TI-406 (selected to Loop 1 Hot Leg).
( ;
- 7. Depressurize RCS as follows:
- a. If all CRDM fans are a. If all CROM cooling fans running maintain 50*F are NOT available for subcooling. operation:
- 1) Maintain 200'F subcooling until RCS pressure is 1200 psig.
- b. Depressurize using auxiliary spray, CVCS-8145(Oedicated ShutdownPanel).
9 e
DC0060 43II .
e 99 ,
ciaste CANYCN DCwER ptANT UPt? NO(Si 1 AND 2 h'[ ON DATE 2/3/84 PAGE 44 0F 56 e
TITLE CONTROL ROCM INACCESSIBILITY
' ACTICN/EXPECTtT kESPCNSE RESKNSE NOT OBTAINED
- 8. Continued RCS cooldown AND depressurization:
- a. Maintain cooldown rate -
LESS THAN 25'F/hr.
- b. Maintain subcooling b. If the required requirements of step 5. subcooling cannot be maintained, W the depressurization and re-establish the requirtd subcooling.
- c. Maintain the reactor coolant system pressure-temperature relationship within the boundaries of the Plant Cooldown Curve. Figure 6 at the end of the main procedure.
- 9. Verify NO voiding in Reactor 9. If voiding is suspected due '
Vessel Tiead Area. to large variations in pressurizer level THEN repressurize the RITto collapse the void in the head area.
- a. Pressurizer level RESPONSE NORMAL.
- 10. If all CRDM fans are NOT in operation:
- a. Maintain RCS at 1200 psig .
while continuing to -
cooldown to 350*F.
)
1 DC0060 4411 1 .. . .
l DIABLO cANYCN PCwEA PLA 'If %S) 1 AND 2 [fff0N 8 DATE 2/3/84 PAGE 45 0F 56 I
flTLE CONTROL ROOM INACCESSIBILITY
- ACTION /EGECTE ESPCNSE ESPCNSE NOT CBTAINE
- b. In Technical Support b. Maintain 1200 psig for Center use ERF05 channel, approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> observe TT-25 to allow the upperhead to thermocouple in Reactor cool off to a temperature Vessel Head. less than saturation for 400 psig (445'F) before continuing with the depressurization.
- 1) Do not depressurize to <l200 psig until upperhead area is less than saturation temperature for 400
. psig (445'F).
- 11. Check if SI system should be disabled:
( 1000 psig but greater system equipment if th;n 700 psig. greater than 1000 psig.
- b. Average RCS temperature - b. 00 NOT disable any SI LESS 350*F but RCS cold system equipment if leg temperature greater Average RCS temperature than 323*F. is greater than 350*F.
- c. Isolate Si accumulators. c. If NO ALARA considerations required and containment entry is necessary, Si accumulators may be isolated manually.
1 e
OC0060 4511
~- '.
v -
OIABLO CANYCN PCwE A WAo' 3 't *CS- 1 AND 2 [fff0N 8 OATE 2/3/84 pAGE 46 0F 56 rale CONTROL ROCM INACCESSIBILITY
~ ACTION / EXPECTED ESPONSE ESPONSE NOT OBTAIN8
- 1) Close each isolation valve (one at a time) by performing the following for each of the following breakers:
MOV 8808A 52-1F-46 MOV 8808B 52-1G-07 MOV 8808C 52-1H-14 MOV 88080 52-1G-05 a) Lay down close contactor seal-in wire on terminal
- 4 (inside bkr cubicle).
b) Close breaker.
c) Depress close contactor.
d) When close contactor drops out, immediately re-open breaker.
If open contactor picks up before breaker is opened, close valve fully using local handwheel. .
e) Re-lift and tape seal in wire on .
terminal #4.
OC0060 46!1 i
- - - 6
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1
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- iAsto CANycN POWEA Plata tact r<hs) 1 AND 2 R ff0N DATE 2/3/84 PAGE 47 0F 56
! TITLE CONTROL ROOM INACCESSIBILITY
- ACTICN/ EXPECTED FESPCNSE RESPCNSE NOT CBTAINED f) Closure of these valves can be verified locally depending on ALARA considerations.
- 2) Rack out each isolation valve b reaker.
- d. Disable the safety injection pumps by opening the CC control power to the pump breaker.
(, e. Disable the non-operating centrifugal charging pump by opening the DC control power to the pump breaker.
- 12. Open additicnal letdown orifices if necessary to maintain normal letdown flow.
- 13. Maintain adequate RCP Seal Injection Flow,
- a. Adjust HCV-142, as necessary.
- 14. When system pressure has been reduced to approximately 400 psig, hold it constant at this value by reducing auxiliary spray flow and energizing the PZR heaters as -
'necessary.
i' OC0060 47!1 8@ ,
NUM5ER EP OP-8 oiAsto CANYON PCwER O'_ ANT Ut97 NCiss 1 AND 2 REVISION 8 OATE 2/3/84 i PAGE 48 0F 56 '
TITLE #
CONTROL ROOM INACCESSIBILITY
' ACTICN/EXPtuto ESPCNSE ESKASE NOT CBTAINED
- 15. When RCS hot leg temperature has been reduced to less than 350'F and pressure is between 380-420 psig, place the RHR system in service recirculating from hot leg 4 to the cold legs as follows:
monitor latdown press.
- b. Manually CLOSE MOV 8809A
& B (RHR to CL 1,2,3&4).
- c. CUT IN control transfer relays cutout switches on the RHR pump bkr.
cubicles.
- d. START RHR pumps locally at their switchgear cubicles.
- 1) Observe recire flow established on FI's located outside RHR pump rooms.
OC0060 4811'
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- iAsto CANYCN PCWER PLANT UNIT Nots) 1 AND 2 R ON DATE 2/3/84 PAGE 49 0F 56 TITLE CONTROL RCCM INACCESSIBILITY
- NOTE: 00 NOT allcw RHR pumps to run longer than 30 minutes on Recire.
ACTICN/ EXPECTED RESPCNSE RESPCNSE NOT OBTMNED
RCS Baron Conc.
- 1) OPEN RHR-8741
is equal to or greater than RCS t
Boron Conc. CLOSE RHR-8741.
- g. Shutdown BOTH RHR pumps.
CLOSE MOV M 0 using handwheel.
- h. Close the breakers for MOV-8701 (52-1G-25) &
8702 (52-1H-19).
- 1. OPEN MOV-8702 and 8701.
- 1) Open by momentarily pushing the open contactor, located inside the breaker panel.
i i
0C0060 4911 l l
I
', l
---,.w..
' ACTICruEXPECTED ESPCASE ESPCNSE NOT CBTAINE) f : The valve is full open wnen the open contactor drops out. This snou a take about 100 seconds.
- 2) OPEN the valve
~
breaker when the valve is full open.
- 3) Rack out motor -
breakers for MOV 8701 and 8702.
- 4) Observe local pump suction pressure indication (which should increase to RCS pressure).
J. OPEN FCV-364 and FCV-365, RHR Hx CCW outlet vivs.
- 1) Open by closing air supply valves at air manifold P-85G-01.
(FCV's are ATC/FO)
- k. Start #1 RHR pump on recire.
- 1) Monitor recirc. flow
- locally.
- 1. Slowly open H0V-8809A until an increase in flow is observed. This is to allow the RHR system to heat up.
DC0060 50!! -
- -O e
OiAsto cANvcN *Cwta *Last uv t 40 56 1 AND 2 kE CN 8 OATE 2/3/94 PAGE 51 CF 56 titta CONTROL RCCM INACCES$1BILITY ACTICNMCTD PE!PmSE PESPCNSE POT CBTAIND
. 1) Cbserve local temperature indicator l on RCS outlet of RHR HX(IcCatedinRHRHX room).
- m. Start #2 RHR pump as per steps k and I above
! (except using MOV-88098),
- n. Slowly open MOV 8809A & 8 to commence further cocidown of RC$.
16.. Open RHR HX Manual crosstie valves RHR 8734A & B and establish RHR to letdown by fully opening HCV 133.
- 17. Regulate letdown flow by controlling PCV 135.
- 18. When RCS cold leg temperature reduces to <323*F notify the NRC that Pressurizer PORV Low Pressure Protection will not be available, untti the control room accessbtitty is re established.
- 19. Reduce letdown flow less than charging flow to begin increasing PIR level to approx. 905.
- 20. When RC5 temp. is reduced below 200'F. fill the steam .
generators all the way and place in wet layup.
/
d f
OC0060 51!!
ciasso cANYCN MWl A 86 4M *
- f NC 5) 1 AND 2 $0hg [OP-8 OATE 2/3/84 PAGE 52 0F 56 d
TITLE CONTROL ROOM INACCES$181LITY
- ACTICN/DPECTED FESKt.!E ESPCNSE NOT CBTAINED ;
- 21. Ensure snutdown margin remains gretter than 1.05 a K/ K.
- 22. Fill the PZR. ,
g: While filling and cooling down the PZR with auxiliary spray, ensure the PZR cooldown rate does not exceed 200'F/HR.
- 23. Return to Section B Step 37 of Main Procedure.
e l
I I l k- ,
1 t
4 e
DC0060 52!! .
og ,
e
l DABLC CANYCN PCWEA PLANT UNIT NOiSi 1 AND 2 ff0N 8 OATE 2/3/84 PAGE 53 0F 56 TcLE CONTROL ROCM INACCESSIBILITY APPENDIX E AUXILIARY FEED PUMP SUCTION SUPPLY FRCM FIRE WATER TANK The operator has 20 minutes to perform this operation after the lo lo level alarm on the condensate storage tank and before the AFW pumps lose suction.
JThis provides sufficient time; however, the operator must not delay and must carry out the valve line up in order as written.
If the AFW pumps are being supplied from the raw water reservoir and a seismic event occurs with resultant loss of AFW suction and auxiliary feedwater flow to the steam generators, the steam generators will boil dry in about 30 minutes. Under these conditions, it is especially important to expedite this procedure and re-establish AFW flow to the steam generators prior to the reactor losing its heat sink.
ACTIONS COMMENTS ,
Using the attached drawing, proceed to supply the AFW pumps
(, ,
suction from the fire water tank.
- 1. Close or verify closed 1. Closing these valves prevents MU-0-2E4 and MU-0-286. losing fire water out a possible break in the reservoir supply line.
- 2. Close er check closed MU-1-298.
- 3. Close or check closed MU-0-325.
- 4. Close or check closed MU-0-427.
- 6. Notify the control room that the suction for the AFW pumps is now available from the fire water tank.
- 7. Locally open FCV-436 and 437.
s DC0060 53II -
. x
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_ g.
h O!ABLO CANYCN PCWEA PL/.NT .Jo"T NO(Si 1 AND 2 h fP OP-8 DATE 2/3/84 P?GE 54 0F 56 TITLE CONTROL ROCM INACCESSIBILITY
- ACTIONS COMMENTS
- 8. Proceed to the auxiliary feedwater pumps and vcnt the pump casings if required to remove air.
m' l
DC0060 54II
- W &
u CIABLO CANYON PCWER PLANT UNIT NOiS) 1 AND 2 OATE h[2/3/84 PAGE 55 0F 56 I TITLE CONTROL ROOM INACCESSIBILITY APPENDIX E Fire Water Tank To M U.
Scaled FP-0-4 rp 0 33g Til te rs Open w ' (
To fim Valve 0,3en Puer Suction Open p 7 Close Y MU.0-325
, Cinte A N
1
- h k tu.0-pgg slaw uater Hea Lia If0" R3W Cluse Wtu.1-291 liter 'teservoir 4 A MU-0-427 'P Close SIR Package if W j- O own M.U. Filter Oypass FCV-43G u ATW U pp .; M g gl-297 Scaled Open Open Valve FCV 437 g AN Fire Water Tank to IPl~l- Open A P W Suction i
DC0060 551I -
-9
CIABLC CANYCN ACWEA NT .;r'iT N0isi 1 AND 2 (' S Off DATE 2/3/84 PAGE 56 0F 56 TITLE CONTROL ROCM INACCESSIBILITY APPENDIX Z NOTIFICATION INSTRUCTIONS
- 1. When this procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Designate this event an Alert. NotifyplEntstaffandresponse organizations required for tnis classification by implementing Emergency Procedure G-2 " Establishment of the Onsite Emergency Organization" and G-3 Emergency Procedure " Notification of Offsite Organizations" in accordance with Emergency Procedure G-1
" Accident Classification and Emergency Plan Activation."
- b. If, after evacuation of the Control Room, control of snutdown systems cannot be established within 15 minutes, redesignate this event as a Site Area Emergency. Notify plant staff and response organizations requirea Dy EP G-2 and EP G-3 in accordance with EP G-1.
Notification requirement must be carried out either at the g:ical Tecnn Support Center or Administration Building communication equipment.
s e W
DC0060 56II .
eO e
l 3 Sv.43 Pacific Gas and Electric Company NUMBER EP OP-13 i CEPARTMENT CF NUCLEAR PLANT CPERATICNS s I I DIASLO CANYCN PCWER PLANT UNIT NO(S) 1 AND 2 DATE 2/1/84 EMERGENCY OPERATING PROCEDURE PAG e. 10F 9 m , MALFUNCTION OF REACTOR PRESSURE CONTROL SYSTEM O IMPORTAN i APPROVED- T A Y ) Y " $4 TO PLkNTMANAGER M CATE SCOPE The purpose of this procedure is to provide instructions to be followed in the event of a malfunction of the reactor pressure control system. For simplicity, this procedure is subdivided into four parts as follows:
PART A: Pressurizer Pressure Channel fails high.
PART B: Stuck open spray valve.
PART C: Pressurizer heater malfunction.
PART 0: Stuck open or leaking power operated relief valve.
This procedure and changes thereto requires PSRC review.
PART A: PRFSSURIZER CHANNEL FAILS HIGH SYMPTOMS
- 1. Failed channel will indicate high pressure. Give the high pressurizer pressure alam (PK05-16) and trip the associated reactor trip bystable (PK05-6). ,
- 2. Other pressure channels show actual pressure is decreasing and gives low pressure alam (PK05-17).
- 3. PRT pressure, level and temperature indicators on VB-2 show abnomally high indication.
- 4. " Pressurizer PORY Temperature High" annunciator alams (PK05-23).
AUTOMATIC ACTIONS -
- 1. If the controlling channel fails high.
~
- a. Both spray valves open.
- b. All pressurizer heaters de-energized.
- c. PCV-455C opens (closes again when pressure decreases to 2185 psig).
e e
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, - - -- - - - . - - , -,r -- ~ .
. 1 NUMBER EP OP-13 OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 2/ 1/84 PAGE 2 OF 9 in12: MANFUNCTION OF REACTOR PRESSURE CONTROL SYSTEM ;
- 2. If the selected protection channel fails high, PCV-474 and PCV-456 will open (but close wnen actual pressure decreases to 2185 psig).
- 3. Possible reactor trip on low pressure.
- 4. Possible safety injection signal on low pressure.
OBJECTIVES
- 1. To regain pressure control by selecting the alternate control channel to terminate event without a reactor trip.
- 2. To restore pressurizer pressure and level to reference values.
- 3. To trip all the bistables associated with the failed channel within one hour. ,
I!HEDIATE OPERATOR ACTIONS ACTION C0leENTS
- 1. Select alternate channel for pressure 1. Insure that the position control on selector switch P/455A. selected does not utilize the defective channel .
- 2. Verify spray valves closed, PORV's closed and heaters energized.
- 3. If step 2 does not occur, place the master pressure controller (HC-455K) in manual and return pressure to normal.
- 4. Stop any unit load changes in progress.
. 5. If a reactor trip occurs, refer to Emergency Operating Procedure No. OP-5 ,
- 6. If a safety injection occurs, refer to Emergency Operating Procedure No. OP-0.
SUBSEQUENT OPERATOR ACTIONS l ACTIbN COMMENTS l
1
- 1. Select the pressurizer pressure ;
recorder to record a valid pressure channel (P/455B).
~
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49 e
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)(8S ON 3 DIABLO CANYON PCWER Pt. ANT UNIT NO(S) 1 AND 2 DATE 2/1/84 PAGE 3 OF 9 k Tnts: MALFUNCTION OF REACTOR PRESSURE CONTROL SYSTEM ACTION' COMMENTS
- 2. If a reactor trip does not occur:
- a. Ensure pressurizer level and pressure return to their normal value.
- b. Within one hour trip, all the by- b. See Table III A-1 in stables associated with the failed Volume 9 of DCPP pressurizer pressure channel. Plant Manual.
- 3. Refer to Operating Procedure No. A-48 to return the PRT to normal.
PART B: STUCK OPEN SPRAY VALVE SYMPTOMS
- 1. All pressurizer pressure channels show decreasing pressure.
- 2. Low pressurizer pressure alarm (PK05-17).
- 3. Pressurizer heaters and spray on at the same time.
- 4. Pressurizer surge line temperature is lower than normal due to upsurge and will give an alann.
AUTOMATIC ACTIONS
- 1. Backup heater energize.
- 2. Possible reactor trip on low pressure.
- 3. Possible safety injection signal . ,
OBJECTIVES
- 1. To terminate spray valve action.
- 2. To restore pressure control. .
r l 1 1
t NUMBER EP OP-13 OtABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 2/1/,84 PAGE 4 OF 9 TU12: MALFUNCTION OF REACTOR PRESSURE CONTROL SYSTEM IMMEDIATE OPERATOR ACTION ACTION COMMENTS
- 1. Place affected spray valve controller to manual and close the spray valve.
- 2. If spray valve does not completely close, ensure all heater groups are energized.
- 3. Quickly drop load, if necessary, to 3. If the RCP is tripped at reduce the power level to about 20%. a power level much greater Then trip the reactor coolant pump of than 20%, the reactor will the loop associated with the defective probably trip on low steam spray valve. generator level. If the RCP is tripped above 35% power, the reactor will trip.
NOTE: Loop No. I feeds N 455A and Loop No. 2 feeds PCV-4558.
- 4. If step 3, above, results in a reactor trip, then:
- a. Trip the reactor coolant purg of the loop associated with the affected '
spray valve.
.b. Proceed to Emergency Operating Procedure No. OP-5.
- 5. If a safety injection occurs, proceed to Emergency Operating Procedure No. OP-0.
SUBSEQUENT OPERATOR ACTIONS ACTION COMMENTS
- 1. If system pressure was maintained without a reactor trip.
1 a,
Return system to normal pressure a. Use the minimum number of by manual heater operation. heater banks to maintain pressure.
)
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NUMSER EP OP-13 OtABLO CANYON POWER Pt ANT UNIT NO(S) 1 AND 2 REVISICN 3 DATE 2/1/84 PAGE- 5 OF 9
( TmLE: MALFUNCTION OF REACTOR PRESSURE CONTROL SYSTEM ACTION COMMENTS
- b. If normal spray is not useable or inaffective when system pressure is restored, use auxiliary spray or use a pressurizer relief.' Follow step No. 1C or 10 below.
- c. If auxiliary spray is needed. *
- 1) Ensure letdown is not isolated. 1) If letdown is isolated or becomes isolated, auxiliary spray cannot be used due to the .tT limit (Tech Spec 3.4.9.2).
- 2) Close the, normal charging path to the reactor coolant loop. .
- 3) Monitor and maintain adequate RCP seal injection.
- 4) Open auxiliary spray valve to control pressure.
- d. If a pressurizer relief is needed for pressure control,
- 1) Close one pressurizer relief isolation valve.
- 2) When the isolation valve is closed, open its' associated PORV.
- 3) The motor operated isolation valve can now be jogged for pressure control.
- e. If a spray valve is stuck open, evaluate the conditions necessary for containment entry to repair or isolate the defective valve.
- f. If the defective valve was closed, repair if possible or evaluate plant .
I conditions to determine the feasibility of continued power operation in such a mode.
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EP OP-13 "hBER DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 g S DATE 2/ 1/84 l
PAGE 6 CF 9 intE: MALFUNCTION OF REACTOR PRESSURE CONTROL SYSTEM .
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PART C: PRESSURIZER HEATER MALFUNCTION SYMPTOMS The following are symptoms for 3 possible failures:
- 1. If controlling pressurizer heater channel fails low.
- a. Low pressurizer pressure and alarm (PK05-17) on defective channel.
- b. High pressurizer pressure and alarm (PK05-16) on other channels.
- c. Pressurizer high temperature alarm (PK05-18).
- d. No automatic initiation of sprays.
- 2. If heaters fail to de-energize.
- a. Pressurizer sprays and heater operating simultaneously.
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- 3. Loss of pressurizer heaters.
- a. Low pressurizer pressure on all channels and alarm (PK05-17).
- b. No automatic initiation of pressurizer heaters.
AUTOMATIC ACTIONS
- 1. If controlling channel fails law, backup heaters will energize and soon pressurizer power operated relief valves will open when actual pressurizer pressure reaches 2335 psig.
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- 2. If the heaters fail to deenergize automatically, pressurizer sprays will actuate to maintain pressure.
OBJECTIVES
- 1. To maintain pressure with manual control of heaters if it is determined that the pressurizer heaters are malfunctioning.
- 2. To reestzblish automatic pressure control by selecting the alternate l pressurizer control channel.
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NUMBER EP 09-13
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DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 2/1/84 PAGE 7 OF 9
( TN1E: MALFUNCTION OF REACTOR PRESSURE CONTROL SYSTEM IMMEDIATE OPERATOR ACTIONS ACTION COMMENTS
- 1. Take manual control of heaters and restore pressure to normal setpoint value.
- 2. If the controlling pressurizer pressure channel failed low, select the alternate control channel and reestablish normal auto pressure control
- 3. Stop any unit load change in progress SUBSE00ENT OPERATOR ACTIONS ACTION COMMENTS
- 1. With a failed pressurizer pressure
, channel, within one hour trip all i the bistables associated with the failed pressurizer pressure channel. -
pART 0: _ STUCK OPEN OR LEAKING F0WER OPERATED RELIEF VALVE SYMPTCMS
- 1. Low pressurizer pressure indication and alarm.
- 2. Dres:arizer relief tank pressure, level and temperature indicators read high (VB-2).
- 3. Pressurizer relief valve discharge temperature indicator reads high (VB-2).
- 4. Pressurizer PORV high temperature alarm (PK05-23).
AUTOMATIC ACTIONS l 1
- 1. Backup heaters energize.
- 2. . Reactor trip on low pressurizer pressure.
- 3. Safety injection on low pressurizer pressure.
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J 8R EP CP-13 otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 sO 3 DATE 2/1 /84 PAGE 8 OF 9 in1E: MALFUNCTION OF REACTOR PRESSURE CONTROL SYSTEM f IMMEDIATE OPERATOR ACTIONS COMMENTS ACTIONS
- 1. If the defective relief valve can be identified by position lights, close its motor operated isolation valve.
- 2. If the defective valve cannot be iden-tified by position lights, close all three motor operated PORY isolation valves.
- 3. If the reactor trips, refer to Emer-gency Operating Procedure No. OP-5.
- 4. If a safety injection occurs, refer to Emergency Operating Procedure No. OP-0.
SUBSE00ENT OPERATOR ACTIONS ACTIONS COMMENTS
- 1. 'If the defective relief valve is isolated witncut a reactor trip, restore pressuriz.*r pressure .and level to referen e values.
- 2. If the defective valve was not identified: .
- a. Wait until tne discharge header temperature decreases.
- b. One at a time, crack open a b. Identify by using the motor operated isolation valve discharge header temper-and identify the defective PORV. ature, PRT conditions and I
' RCS pressure fluxuations.
- c. When identified, close the associated isolation valve at the faulted PORV.
- d. Open the' isolation valves on the unaffected relief valves.
- 3. sWith abnormal conditions in the PRT, refer to Operating Procedure No.' A-48.
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o NUMBER EP OP-13 otAsLO CANYON PCWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 2/1/84
( TiTts. MALFUNCTION OF REACTOR PRESSURE CONTROL SYSTEM PAGE 9 0F 9 l APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Notify the Plant Superintendent, Supervisor of Operations and Plant Manager or their designated alternates.
- b. Designate this event a Significant Event. As a minimum, within one hour notify the NRC Operations Center using the red phone in the Control Room. Gather sufficient information from all sources prior to calling so that the phone call is meaningful. Refer to Operating Procedure 0-4 " Operating Order (One Hour Reporting Require-ments to the NRC)" for a suggested format for this report. Notify the NRC that your call is pursuant to 10 CFR Part 50.72, (Notifi-cation of Significant Events).
- c. If the pressure transient results in one of the following:
- 1) Overtemperature AT or Overpcwer aT protection channel activated and not as a result of instrument failure.
- 2) Exceeding the DNB parameters of technical specificatinn 3.2.5.
while in mode'1.
- 3) Failure of a relief or safety valve to close.
Designate this event a Notification of Unusual Event. Natify Plant staff and response organizations required for this classi-
. fication by implementing procedures G-2 " Establishment of the On-Site Emergency Organization" and G-3 " Notification of Off-Site Organizations" in accordance with Emergency Procadure G-1 " Accident Classification and Emergency Plan Activation".
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?G5u3 Pacific Gas and Electric Company NUMBER EP OP-25
( CEPARTMENT CF NUCLEAR PLANT CPERATICNS I
DIABLC CANYCN POWER PLANT UNIT NC(S) 1 AND 2 DATE 2/2/84 i EMERGENCY OPERATING PROCEDURE PAGE 10F 4 m LE:
g TANK RUPTURES APPROVED-. Yd PLANTMANAGh DATE SAFETY SCOPE This procedure outlines the steps to take in the event a gas decay tank, liquid holdup tank or volume control tank ruptures and releases radioactive gas and/or liquid to the auxiliary building.
This procedure and changes thereto requires PSRC review. !
SYMPTCMS
- 1. Plant vent monitor high radiation alam and containment ventilation iso-1ation.
7 2. Possible LHUT or VCT low level alarm.
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- 3. Gas decay tank, LHUT, or VCT low pressure alarm.
- 4. Persons near the affected areas may find themselves contaminated when checking out at access control or exposed to above nomal radiation levels.
AUTOMATIC ACTIONS
- 1. High radiation on plant vent air particulate monitors (9-28 A or B) or.
- plant ver.t radio gas monitors (R-14 A or 8) initiates containrrent vent-tilation isolation.
- 2. At St VCT level charging pump suction valves from RWST 8805 A & B open and VCT outlet valves LCV's 112 B & C close.
- 3. Low pressure or low level in LHUT trips LHUT recirculation pump.
l OBJECTIVES
- 1. Alert on site personnel.
- 2. Evaluate the release and take appropriate protective measure.
IMMEDIATE OPERATOR ACTIONS ACTIONS COMMENTS
- 1. Initiate the site emergency signal 1. Evacuation of personnel from -
affected area
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DiAsto canyon POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP OP-25 REVISION 2 DATE 2/2/84 PAGE 2 0F 4 '
i Tnts. TANK RUPTURES ACTIONS COMMENTS
- 2. Place auxiliary building ventilation 2. To reduce Iodine release in charcoal filter made by SI test from plant vent.
. signal at POV 2.
- 3. Either shutdown or place the unaffected units auxiliary building ventilation system in the charcual filter mode of operation.
SUBSEQUENT OPERATOR ACTIONS ACTIONS
- 1. Evacuate all personnel from the affected area. -
- 2. Refer to the following emergency operating procedures applicable:
R-1 Personnel Injury (Radiological Related) and/or overexposure P-2 Release of Airtorre Radioactive Materials R-4 High Exterr.al Radiation R-5 Radioactive Liquid Spill
- 3. Isolate the release
- a. For a gas decay tank rupture: -
- 1) Select the affected tank to standby so that it is neither filling nor providing recycle gas.
- b. For a LHUT rupture:
- 1) Stop any transfer or recirculation operation involving the affected LHUT.
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- 2) Line up a different LHUT to receive letdown from the primary systen other .
than the affected LHUT.
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DiAsto cANYCN POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP OP-25 REVISION 2 DATE 2/2/84 TITts. TANK RUPTURES ACTIONS COMMENTS
- 3) Stop any cover gas recycle to the affected LHUT.
- 4) Check VCT and accumulator test line discharge lined up to another LHUT and isolate discharge to affected LHUT.
- c. For a VCT rupture
- 1) Place the VCT level control LCV-112A in the DIVERT TO HOLDUP TANK position.
- 2) Check transfe-red or transfer pump suntion from VCT charging to RWST (open 8805 A&B and close LCVs 112 B&C).
' 3) Terminate VCT makeup.
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- 4) Secure hydrogen supply to the 4) Make arrangements for an affected unit's VCT at the alternate souce of hydrogen hydrogen bottle rack. cakeup to Unit 1 generator.
and PIR licuid space and steam space sample line containment isolation valves (9355A, 9355B, 9354A,93548).
- 6) Concence a controlled reactor 6) Drop load on unit as neces-shutdown. sary to maintain rod position and Tavg approximately equal
- 4. Verify containment ventilation isolation to Tref, and reset containment ventilation isolation trains A & B t
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OtAeto CANYCN PCWER PLANT UMT NCIS) 1 AND 2 NUMBER EP OP-25 REVISION 2 DATE 2/2/84 PAGE 4 0F 4 TiTu!. TANK RUPTURES ,
APPENDIX Z j EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS l
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- 1. yhen this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
"a. The precise designation of this event will be determined by the radiological effect of the leak. Refer to Emergency Procedure l R-2 " Release of Airborne Radioactive Material" and R-4 "High Radia-tion (In-plant). As a minimum, in the. absence of data on radiation levels or release rates, designate this event a Notification of Unusual Event. Notify plant staff and response organizations required by Emergency Procedures G-2 " Establishment of the On-Site Emergency Organization" and G-3 " Notification of Off-Site Organi-zations" in accordance with Emergency Procedure G-2 " Accident -
Classification and Emergency Plan Activation."
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NUMBER EP R-1 3 39#3 Pacific Gas and Electric Company REVISION 11
' CEPARTMENT CF NUCLEAR PLANT OPERATIONS DATE 2/21/84 q ,
I CIABLO CANYCN PCWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 16 EMERGENCY PROCEDURE PERSONNEL INJ'IRY OR ILLNESS (RADI0 LOGICALLY TITLE: RELATED) AND/OR OVEREXPOSURE g
APPACVED: Y [
PLANTM@$ER DATE SCOPE This procedure describes the actions which are to be taken in the event of:
- 1. Personnel injury or illness (minor or serious) where the victim is radiologically contaminated.
- 2. Overexposure (or suspected overexposure) frcm an external source.
- 3. Overexposure (or suspected overexposure) from an internal source.
4 A ccmbination of the above.
Injuries er illnesses which to not involve radioactive contaminaticn or overexposure are bandled in accordance with Erergency Frecedures M-1 or M-2. This procedure and changes thereto requires PSRC review.
DISCUSSION Any radiolcgically related injury or illness or potential radiation overexcesure is a serious matter recuirire prompt attention tc the care o#-the patient and prempt appropriate corrective action tc preclude re-cccurrence. In addition, fallewup investigation to cuantify the eAtent c/ exposure to radiation requires care in the gathering and retention of samples, radiation readings and other evidence wnich may contribute to the understanding of the incident and assist botn in care of the injured and in preventing re-occurrence.
IPNEDIATE ACTIONS
- 1. The employee (s) who are at the scene shall:
- a. Render all necessary first aid.
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- NLhBER EP R-1 OtA8LC CANYON PCWER PLANT UNIT NC(S) 1MD2 REVISIGN 11
- DATE 2/21/84 PAGE 2 0F 16 mim. PERSONNEL INJURY OR ILLNESS (RADIOLCGICALLY RELATED) A80/0R OVEREXPOSURE 1
- b. Notify the control room (Shift Foreman) as soon as practical, and provide a phone number for the patients location.
g: The Shi may be notif Dialing dialin tivatas the M l an medical emergen e call. The caller sust remain on the phone to enable the Shift Foreman to dial into a conference call.
- 2. Shift Foreman (Interim Site Emergency Cookinator)
- a. Evaluate plant status that may have produced the personnel injury, illness and/or overexposure. Sound the site emergency signal to clear the affected area, if the situation warrants it. '
- b. Dispatch additional firs s h as the project construction EMT xt. 'the scene of the injury or illness. f requi .
distice Protection persont.el
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- c. ext.
- d. Call an ambulance if the injury warrants it. Refer to Appendix 1 " Measures to be taken if Medical Care Is Required" for instruct 1ons. .
SUBSECUENT ACTIONS The Shift Foreman shall direct all sucsequent actions until relieved by the long-terr Site Emergency Coordinator if the situation warr.tnts i t- ,
- 1. Actions Coccon to All Occurrences
- a. Transport the patient to the first aid room, provided that l this can be done without aggravating the injury.
- b. Take actions as specified in the following sections as appropriate for the particular occurrence.
Section 2: Minor injury when can.tamination is present.
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OCCC84 2%II l
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1 Age 2 NUMBER EP R-1 otAeLo CANYON POWER PLANT UNIT NC(S)
REVISION 11 DATE 2/21/84
( PAGE 3 0F 16 7,7tg' PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/0R OVEREXPOSURE Section 3: Serious injury when contamination is present.
Section 4: Overexposure from external source Section 5: Overexposure from internal source.
- c. Perform the notifications required by Appendix Z " Emergency Procedure Notification Instructions."
NOTE: Form 69-9221 " Emergency Notification Record" is provided to record notifications not documented elsewhere,
- d. Collect personnel dosimetry assigned to the individual and have it evaluated.
- e. Begin sathering information to assist the long-term Site Emergency Radiological Advisor in his evaluation. Guidance on things which should be investigated is given in Appendix f 2 " Factors to Consider in Making a Preliminary Evaluation."
I f. Close out the event with the following written reports:
- 1) Report to NRC (required within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for an Unusual Event, or within 30 days for a report under 10CFR20.403).
- 2) Form 62-4587 " Report of Industrial Injury to Erployee."
- 3) Form 62-4586 " Employers' Report of Occupational Injury or illness."
- 4) Nuclear Plant Problem P.eport. (See Nucitar Flurt Administrative Procedure C-12.)
NOTE: Reports to f1RC and the Nuclear Plant Problem Report are not required for minor injuries or illness for which onsite first aid and decontamination is 1 adequate. '
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OC0084 3XII
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DIABLC CANYCN PCWVEA PLANT UNIT NC(S) 1 AND 2 RE S CN 1 l DATE 2/21/84 PAGE 4 0F 15 7gtg. PERSCNNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/0R OVEREXPOSURE
- 2. Minor Injury or Illness When Contamination is Present The following steps apply to injuries where prompt medical attention is not required (i.e., first aid at the plant is adequate).
- a. Make the following surveys and record the results on the
" Skin and Clothing Decontamination" Form (Form 69-9392).
- 1) The wound prior to decontamination.
- 2) The object causing the injury (if possible) and any clothing penetrating or touching the injury. These items should be retained, if possible, until the long-term Site Emergency Radiological Advisor has completed his evaluation so that detailed radionuclide analysis can be performed, if required.
- 3) The wound during each decontamination and after final decontamination.
NOTE: These personnel surveys are in addition to other radiological surveys (e.g., work area, equipment) which may be required by radiation protection renagement.
- b. Deco 5tamitta^e the wound using the standard procedures discusred irr Radiation Control Procedure G-4. In cases of severe car.tamination, where there is a realistic ' possibility that significant internal retentica of radionuclides may have occurred, it is destrable to retain wash solutions (or samples thereof), swabs, and other such material which may be useful to the Site Emergency Radiological Adviso .
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f Refer to E.nergency Procedure RB-5 " Personnel Decontamination" in the event normal decontamination facilities are overloaded or unavailable.
- c. Complete any additional first aid measures.
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DCD084 4XII e9 e
ciAsLO CANYON POWER PLANT UNIT NC(S) 1 AND 2 hh0N DATE 2/21/84
( PAGE 5 0F 16 TITLE. PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AN0/0R OVEREXPOSURE
- d. Complete accident report Form 62-4587, " Report of Industrial Injury to Employee" and forward to plant clerk for processing.
10TE: This documentation requirement assumes no medical attention (beyond first aid) is required and that no lost time occurs. If lost time beyond the day of injury is likely, or if medical treatment (including doctor referral) is required, complete Form 62-4586,
" Employers' Report of Occupational Injury of Illness" and forward to plant clerk.
- 3. Serious Injury or Illness When Contamination is Present The following steps apply to injuries or illnesses where prompt medical attention is required (i.e., the patient must be taken to a hospital) and the patient is contaminated. In this type of circumstance, the need for treatment of the injury and comfort of the patient will take precedence over the need for decontamination.
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- a. Call San Ldis Amoulance and French Hospital and have the patient transported to French Hospitat. The d? tailed steps to be taken if this is required are given in Appendix 1 of this procedure. The Control Room should keep personnel attending the patient informed of the status of the ambulance,
- b. During the interval until the ambulance arrives keep the patient as comfortable as possible. Survey and cecontaminate the patient to tne extent that time and conditions permit. Do not decontaminate the catient if it will aggravate his injury. Recoro survey results on tce
" Skin ano clotning Decontamination" Form (Form 69-9392.)
- 1) Survey any wounds and/or the victim's skin (if possible).
- 2) Survey the object causing the injury (if possible) and any clothing penetrating or touching the injury. These items should be retained, if possible, until the long-term Site Emergency radiological Advisor has completed his evaluation so that detailed radionuclide analyses can be perforwed, if required.
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OC0084 SXII 90 e
DIABLO CANYON PChNER PLANT UNIT NO(S) 1 AND 2 DATE E
{bl 2/21/84 PAGE 6 0F 16
- 7y~ PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/0R OVEREXPOSURE
- 3) Decentaminate the patient using the standard procedures discussed in Radiation Control Procedure G-4 In cases of severe contamination, where there is a realistic possibility that significant internal retention of ,
radionuclides may have occurred, it is desirable to retain wash solutions (or samples thereof), swabs, and other such material which may be useful to the Site Emergency Radiological Advisor.
ETE: Refer to Emergency Procedure RB-5 " Personnel Decontamination" in the event nonnal decontamination facilities are overloaded or unavailable.
- c. Have the hospital kit and a handheld radio available for transport to the hospital with the monitor accompanying the patient, or the tetm dispatched to the hospital.
4 Overexposure From External Source The following steps apply to cases where the patient has (or is suspected to have) received a dose from an external source to the whole body, or any portion thereof, in excess of an 1pplicable lirit contained in Radiation Centrol Standa-d Ko. 1 and where the individual does not require proept medical attention for ar.y other reason. Personnel suspected of overexcesure shill not re-enter radiation controlled areas unless auth:rized by the Site Emergency Cooreirator.
- a. Provide any first aid or radica7 attention which the patient may required.
- b. Notify San Luis Ambulance and French Hospital and transport the patient to French Hospital in accordance with Appendix 1 for observation or treatment in any of the following circumstances: 1) The patient is known or suspected to have received at least any of the following:
a) 25 rem to the whole body, active blood forming organs, lens of eyes, gonads, head or trunk.
CC0084 6XII W e
DIASLO CANYON power Pt. ANT UNIT NO(S) NUMBER EP R-1 1 AND 2 REVISICN 11 DATE 2/21/84 PAGE 7 0F 16
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yu PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AN0/0R OVEREXPOSURE b) 150 rem to the skin.
c) 375 rem to the extremities.
- 2) The patient shows signs of radiation sickness, such as nausea, vomiting, extreme sweating, weakness, diarrhea, extreme anxiety, incoherence, sensitivity of the nerves (tingling or itching sensation).
- 3) The patient shews evidence of radiation dermatitis *
(skin damage). Except for extremely high skin dose (greater than 5,000 rem), in which case pain occurs promptly and is intense, the symptoms at the time of exposure are a sensation of wamth and itching.
Redness, blistering and other effects may not appear for several days.
- c. If the patient requires transportation to the hospital, during the interval until the ambulance arrives keep the patient comfortable. Survey the individual and perform any decontamination which circumstances require and/or pemit.
Do not acgravate any infury or unduly alarm the ntient in performirg these coerations. Record survey resuits on tne
" skin ano Glotning DecontamiN. tion" Tcrm (Form 69-9292) and/cr " Radiation t,ose kata Survey Record" (Form C9-9316).
In cases of severe contamination, handle as in Step 3.c tc the extent practical.
- d. To the extent practical, save all vomit, urine, feces or other sarples whict may assist the long-tem Site Emergency Radiological Advisor in evalesting the accident. This is particularly importent if internal deposition of radioactive -
materials is suspectcf.
- e. Collect the patient's personnel dosimetry and any materials which may have been activated (if a neutron exposure is suspected) such as belt buckles, watches, jewelry, prior to sending him to the hospital or releasing him. This will be processed for evaluation.
- f. Subsequent actions will be based upon the results of the evaluation of the external exposure.
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DC0084 7XII
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i NUMSER EP R-1 ciAsto cANYCN POWEA PLANT UNIT NO(S) 1 AND 2 REVISION 11 CATE 2/21/84 PAGE 8 0F 16 TITm PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/OR OVEREXPOSURE
- 5. Overexposure From Internal Sources The following steps apply to cases where the patient has (or is suspected to have) ingested a significant quantity of radioactive material . If the ingestion was by breathing, this procedure applies any time that the concentration to which the person has been exposed is greater than' or equal to (MPC) x PF, where (MPC) refers to the normal (40 hr.) maximum permissible concentration, and PF refers to the protection factor the patient cbtained when a quantitatively fit tested to the respirator that was worn for the job.
- a. Take any medical action which may be required as a result of injury or external dose received (Steps 3 and 4 above). The treatment of these effects should take precedence over the evaluation of internal exposure.
. b. Remove and retain for subsequent radiological analysis the patient's clothing and respirator.
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- c. Survey the patient thoroughly and record the results on the
" Skin and Clothing Decontamination" Form (Form 69-93:12).
- d. Cecontaminate individual to as low as practicsl withcJt i causirg further injury. If practical, sase 5:7.ples of the decentaminat1on solutions, swabs, and other materials which nay be of use in subsequent radiological evaluations.
- e. Ccunt the patient on the whole body counter. The results of this analysis will, in large ressure, detennine the necessity for further medical attention or serveillance.
- f. Collect and save any urine, feces, or vuinit which is passed from the patient. The long-term Site Emergency Radiological l
Advisor may request that special urine samples be collected for bicassay.
- g. Subsequent actions will be based upon the results of the evaluation of the internal exposure,
- b. If the patient is sent to the hospital, make arrangements to have all urine, feces or vemit samples retained for radiological analysis.
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l cuBLO CANYON power Pt. ANT UNIT NC(S) NUMBER EP P-1 1 AND 2 REVISION 11 CATE 2/21/84 9 0F 16 I PAGE
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rnis. PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/OR OVEREXPOSURE REFERENCES
- 1. Radiation Control Standard No.1, " Personnel Exposure."
.2. Radiation Control Standard No. 2. " Internal Exposure Controls."
- 3. Radiation Control Standard No. 5. " Medical." .
4 Radiation Control Standard No. 8 " Reporting Requirements."
- 5. Radiation Control Procedure No. G-3, " Personnel Internal Exposure Control."
- 6. Radiation Control Procedure No. G-4, " Personnel Contamination Control."
- 7. Radiation Control Procedure No. G-7, " Radiation Surveys."
- 8. Emergency Procedure G-1, " Accident Classification and Emergency Plan Activation."
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- 9. Emergency Pro:edure G-2, " Establishment of the Onsite Emergency Organization."
- 10. Emergency Procecure G-3, " Notification of Offsite Organi:aticns."
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- 11. Emergency Procedure R-4, "High Radiation (In Plant).
- 12. Emergency Pro:eoure RB-5, " Personnel Decontamination."
- 13. Emergency Procedure OR-1, "Offsite Support and Assistance" APPENDICES
- 1. Appendix 1, Measures To Be Taken If Medical Care Is Required.
- 2. Appendix 2, Factors To Consider In Making A Preliminar'y Investigation.
- 3. Appendix 2. Emergency Procedure Notification Instructions.
w OC0084 gXII
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1 NcMSER EP R-1 DIABLO CANYCN PCWER PLANT UNIT NCIS) 1 AND 2 REVISION 11 OATE 2/21/84 P.15E 10 0F- 16 _
TITLE ~
PERSONNEL INJURY OR ILLNESS (RACIOLOGICALLY RELATED) AND/OR OVEREXPOSURE ATTACHMENTS
- 1. Form 69-9221 " Emergency Notification Record."
- 2. Form 69-9316, " Radiation Oose Rate Survey Record."
'3. Form 69-9392, " Skin and Clothing Decontamination."
4 Form 62-4587, " Report of Industrial Injury to Employee."
- 5. Form 62-4586, " Employers' Report of Occupational Injury or Illness."
- 6. Form 62-6015. " Medical Referral."
- 7. Light Outy Program Letter.
- 8. Safety. Health and Claims Personnel to 8e Contacted for Reporting of Injuries at Diablo Canyon (3/83).
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cuaLC cANYCN PCWER Pt. ANT UNIT NC(5) NUMBER EP R-1 1 AND 2 REVISION 11 OAtE 2/21/84
( PAGE 11 0F 16 rira PERSONNEL IN'URY OR ILLNESS (RADI0 LOGICALLY ;
RELATED) AN0/0R OVEREXPOSURE APPENDIX 1 MEASURES TO BE TAXEN IF MEDICAL CARE IS REQUIRED The follcwing are the procedural steps to be taken in the event a contaminated patient trust be transported to the hospital for medical SanLuisA.bulanceTPher ergency No I and provide the follcwirig information:
- a. Name of caller.
- b. Ccepany affiliation,
- c. Phene numcer of caller. (Where he can be reached.)
- d. Name of injured cr ill person.
- e. Where the patient is located.
I
- f. Where the patient is to be transported (French Hospital).
- g. Nature of injury or illness,
- h. Patient is centacinated.
- 1. Any other medical inforr.ation which might be pertinent to transporting the patient.
Record this *nforr.ation on Form 69-9221, "Erergency Notification Record," or other suitable log.
- 2. Contact the Security Shift Superviso d g call the security force at the Port San Luft entrance and alert them that the arrtulance is entering. It is also a~dvisable to have an escort accompany the arrtulance frem the Security Building to the first aid room to minimize the delay in reaching the destination.
- 3. The victim shall be trans
- d to French Hospital. Call ahead tothehospital[ Phen -
nd provide the following informa tion:
- a. Name of caller.
(
d CCCC84 11XII
k h
otA8tO CANYON POWEA PLANT UNIT NCIS) 1 AND 2 E h EP R-1 DATE 2/21/84 PAGE 12 0F 16 Tats. PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AN0/OR OVEREXPOSURE APPENDIX 1 (Cont'd)
MEASURES TO BE TAKEN IF MEDICAL CARE IS REOUIRED
- b. Company affiliation,
- c. Phone number of caller. (Where he can be reached.)
- d. Name of injured cc ill person.
- e. Age of injured or ill person (approximate if not known),
- f. Extent of injury, illness or symptoms.
- g. Medical history (if known).
- h. Radiological conditions.
Record this information on Form 69-9221, " Emergency Notification Record", or other suitable log.
4 Prior to arrival of the ambulance, the patient s'hould be decontaminated to the extent practical without aggravation of injury.
- 5. If the patient cannot be completely decontaminated prior to arrival of the ambulance, wrap him in a blanket prior to placing him in the ambulance in order to minimize the spread of contamination. Alternatively, he may be placed in the plant's Nuclear Accident Emergency Carrier.
- 6. An individual qualified in radiation monitoring shall accompany the victim to the hospital. This individual should take a hospital kit and a handheld radio with him. l NQTE: Two hospital kits and radios are stored in Access Control.
Additional equipment and radios are also available at the PG&E San Luis Obispo Service Center.
- 7. Two addit.icnal individuals qualified in radiation monitoring should be dispatched to French Hospital to assist hospital personnel.
- NOTE: Refer to EP OR-1 "Offsite Support and Assistance" for air ambulance and medivac support.
)
OC0084 12XII
.S e
s DiAsto CANYON power Pt ANT UNIT NC($) EP R-1 1 AND 2 3 g DATE 2/21/84
( PAGE 13 0F 16
' rats. PERSONNEL INJURY OR ILLNESS (RADIOLOGICALLY RELATED) AND/0R OVEREXPOSURE APPENDIX 2 FACTORS TO CONSIDER IN MAKING A PRELIMINARY INVESTIGATION
-It is important to conduct the preliminary investigation in a systematic manner to assure that potentially valuable evidence is not overlooked, lost or destroyed. The following is a reference listing of items which should be checked (if they are applicable). Also, two other factors are important in conducting an investigation of this type, namely: a) information which is gathered should be written down in a comprehensive, neat manner, and b) all samples, clothing, or other articles which are collected should be put in sample bottles or plastic bags, and labelled with the patient's name, date, collection time, sample identification, and other pertinent data.
- 1. Factors Cormon to All Accidents
- a. Date, time of occurrence.
- b. Basic reconstruction of events.
f
- c. Probable source (s) of radioactivity involved.
- d. Names and addresses of all witnesses.
- 2. Considerations in Evaluating External Exposure
- a. Exactiv where was the patient located at the time of exposure?
- b. How was patient physically oriented with respect to source (will help to evaluate nonuniform exposure)?
- c. On what part(s) of body were dosimeters being worn?
- d. Were self-reading dosimeter readings recorded and all nonself-reading types collected?
- e. Are there any " natural" dosimeters available? (Belt buckles, wrist watches, gold tooth fillings, and other such items are useful in determining neutron dose.)
- f. Exactly what was the time interval over which exposure occurred?
i e
i DC0084 13XII l
oiA8LO CANYON POWEA Pt ANT UNIT NO(S) 1 AND 2 [#?'y [ R-1 DATE 2/21/84 PAGE 14 0F 16 '
r!TLE. PERSONNEL INJURY OR ILLNESS (RADIOLOGICALLY -
RELATED) AND/OR OVEREXPOSURE
- g. Are there any applicable dose rate measurements, and if so, exactly where and when were they made?
- 1) Ion chamber measurements
- 2) Area monitors
- 3) Other
, h. What was the status of the plant at time of exposure?
- 3. Considerations in Evaluating Internal Exposure
- a. Where was the patient located at time of exposure?
- b. Exactly what was the time interval over which exposure occurred?
- c. Can sample (s) of liquids which were internally deposited be obtained?
- d. Can samples of airborne activity which were breathed be obtained before the area is purged?
- e. Are there any applicable monitor readings?
- 1) Process monitors
- 2) Continuous Air Monitors
- 3) Area Monitors
- 4) Other
- f. Can samples of patient's clothing, decontamination solutions, secretions, respirator filters, be saved?
- g. Can the region in the vicinity of the occurrence be smear-tested, or can decontamination solutions be retained?
l -
1 DC0084 14XII G
w - e@
CIA 8LO CANYCN PCWEA PL. ANT UNIT NCIS)
NUMSER EP R-1 1 AND 2 REVISION 11 CATE 2/21/84
(
PAGE 15 CF 16
' PERSONNEL INJURY OR ILLNESS (RADIOLCGICALLY rats.
RELATED) AND/0R OVEREXPOSURE APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been activated and upon tirection from the Shift Foreman, proceed as follows:
- a. In case of a minor injury with contamination present or an overexposure case from any source which does not meet the criteria for an Unusual Event, notify the Plant Manager, Plant Superintendent and Supervisor of Chemistry and Radiation Protection or their designated alternates.
- b. Designate this a Notification of Unusual Event in any case of an injury or overexposure requiring transportation of the patient to an offsite hospital or if extensive ensite decontamination is required (soap and water washings do not remove contamination or offsite decontamination assistance is' required). Notify plant staff and response organizations
- recuired for this classification by implementing Emergency
! Procedures G-2 " Establishment of the Onsite Emergency Organization" and G-3 "Notificati~on of Offsite Organizations" in accordance with Emergency Procedure G-1
" Accident Classification and Emergency Plan Activation."
- c. If the case involves an overexposure from an external source which exceeds:
Innediate Not.ification* Notification Within 24 Mcurs 25 Rem Whole Body 5 Rem Whole Body 150 Rem' Skin 30 Rem Skin 375 Rem Extremities 75 Rem Extremities Notify the Director, NRC Region 5 by telephone and telegraph, mailgram and facsimile within the appIIcable time frame described above. Indicate the notification is pursuant to 10 CFR20.403 (Notification of Incidents).
- 0esignate this a Notification of Unusual Event and complete I the additional noti?ications prescribec in section 1.b.
above.
I V
l OC0084 15XII
.@ O
NU,*SER EP R-1 CIABLO CANYCN PCWER Pt. ANT UNIT NO(S) 1 Agg g REVISION 11 CATE 2/21/84 PAGE - 16 0F 16 TITLE. PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/0R OVEREXPOSURE
- 2. In addition to notification performed above, also notify the following in any case where NRC notification is required.
- a. Supervissng Nuclear Generation Engineer (Personnel and Environeantal Safety) or his alternate in the Department of Nuclear Plant Operations:
~
Mr. W. H. Fujimoto PGaadE:
Plant Ext.:
Home: ,__
i a s
- b. Compensation Claims Representative in the Cesartment of Safety, Health and Claims, per the attached list of personnel.
NOTE: 1) The System Dispatcher will handle the notification of General Office Personnel if they cannot be prcmptly reached.
- 2) Nuclear Mutual Limited (NHL) holds the Ccmpany liability and property damage insurance for Company personnel and property. They should be notified under the same circumstances as the NRC.
Notification is made by the Company's Insurance Depa rtment. The Cepartment of Nuclear Plant .
Operations should be requested to interface between the plant and the Insurance Department when required. American Nuclear Insurers / Mutual Atomic Energy Liability Underwriters ( AN!/MAELU) holds third party insurance coverage and would be similarly notified in accidents involving a third party.
n OCCC84 16XII
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j a- est a=. ins l PACIFIC GA3 AND El.!CTRIC COMPANY Raoort of Indusinei taiury to Errimovee g'
1
- 1. Name S. Division
- 2. Adores #
.t. Tetohorse No. 7. Decermtent 4 Social Security No. 8. Date of Accudent
- 5. Osuuseoon 9. Time of Acculmst 10, t.aceoon of Acceent 11. Nonae of Irvjury 11 What were you doing and how did aceaant occur?
11 Camribe First Aid rundered:
14 Wlmesmas no asesourre i 1.
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- 3. 15.
Sipienuwof Emo6cyee
- 18. Cam injury rumorma:
1
- 17. Cam 30 days sanoses 13.
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- See Over Sipisture of Suoervisor INSTRUCTIONS: This rumort (Items 1 mru 15 should be arresar and syssef try me ansWoves morson-m& anc coumersgnes try me supervoor. It is for asi Inouserted inturies and is in cuolicate. The ongmat is to be retswies for Ccmoeny recoras; me cosy is a he asteined after comosecon anc given to me
' amo6even. Before sgnmg in item 18. me massrvisor viouts: fill in the does of tne resort (item 181 ane l-comous and nouse me dem JDdaye frorn me dem me injury was rumorted (Item 171.
If me emotoyee tener roomrus tresument try a docar or bemomes disablest. Form 82-485 must be preserna sect itsemerced m Ine Sefuty. Healtn and C*.aems Oscartment IMMEDIATELY' accomoemaa
! try tne orgnal of mis rumort j If me emodoves is unamie a f!Il out or sipi mis rumort,it snould be presered,sened by me superviser 1 sul tne employee should be yven a copy wisiti 5 days as reouiresi try law.
If me i a emolayee cannot wr+te Englisn, me resort mov be made accoteing to a verbed statement. j If necomary,. me employee
- may sign by a merit and a witness to me rumort should sign betow me em-pioves's maris. -
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I Report e Date 19 -
Dr.
- Cadly give to bearer.
I Mr./Ms.
medical artention, and forward a compiere detailed resort immedi.
ately to Manager, $afety Healm and Cams Dept. 245 Market Street.
San Franczsca.94106. Your eilts should be itemized and all bills and reports rendered in tripiicate.
PACIFIC GAS AND ELECTRIC COMPANY sy l **
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1 Pt. EASE COMPLETE AND RETURN TO EMPt.OYEE (supunts murr navstmasps.rras cAan m asTuam m womal Passfic Gas and E!asaris ca.: Dess 19 _
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Mr./Ms.
Occupadon Report e Employed By ! **
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tanared at ." en ,19 l C asase se Ass was inansmiums,
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hant you '5r : sing cne of cur panel ;nysicians =4: : sa: cur enreicyees.
Cur =rs=a y g:al is u previca emolcyees was sustain incust.-f at injurias reciraag =ecical 4:.an:1cn wim . ,... first-class trea . ant. Ycur assistanca in =1s ensaavor is a srecia-ad.
Thars is an arsa of c=nca,rm u us. khile ca maese of anic1cyees ::.a:
rectre : et= ant by a saysician has re:ained stacle or in se a :ssaswort, cacitase. ma nu==se of disa:1ing injuries escuiMag it=a saay ^. -
f.a.. Ics: time injuries, has dramattcally increasan.
D
' !se believe cat s=me of =1s :tme away fWu wert nipt possitty 23 avoidae if ma avaitaatlity of ligt (modified) duty or desk-type wort wet =sre
' wicaly kacWR. $ces pfrysicians have statad f.*lat in see cases :Ma patient will res end sure residly to treatserrt if kept tusy in a lignt-duty casacity.
P-ecus:1ve, lipt-outy azzigramanu are almes always availa=le f r encicytes released f:r wars wi=in ma medical res:Mettens esunlisned my :se pnysician.
I: our solicy u have an injured enslayes ac=meanied by a susaniser or 7
c rsr recrtsann *ve on =a first acc=r's visit. Dould tsart to any cuas-
- 1-n amou: == availasility or type af lip: Ju:y ::.at c.an ca previsac, : <
ce sne vill na aale := answr f=r us.
car sueleyees' welfare is our sain c=ncarn. Dould you have any cites:1cns a: cut our progras, I will to glad to call on you a your c==venienca.
' Sincarely ,
- 2. C. DCANIEKXT RC kg-l l l t .
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3/83 PACIFIC GAS AND ELECTRIC CCMPANY Page 1 of 2
('> R19 OEPARTNENT OF NUCLEAR PLANT CPERATIONS 01ASLO CANYON PCWER Pt.MT UNIT NOS.1 AND 2 Safety, Health and Claims Personnel to be g i
Contacted for Reoortino of Injuries at Diablo Canven i
D*PLOYEE INJURIES In all cases of serious employee injuries (for example, injuries involving I
l hoscitali:ation, electric :entact, hernia, amoutation, fractures, or injuries expected to result in lost time from work beyond the cay of injury) l or deatn, =nich occur while on the joo, report should be made as felicws:
! Ourine Wertina Hours:
T. 3. Honey PGancE local (If Mr. Honey is not available, the person answering the telephone will take the cessage and notify Mr. Honey or any other parties necessary in tne Safety. Health and Claims Oesart:nent).
Any Other Time: l 1
i Report to one of the persons on the following list, trying each in order until one is contacted: -e i
i f 1. T. B. Honey Pinole I i
\ 2. A. Themas San Fr'ancisco
- 3. C. 8. Pcwell San Francisco 1 4 P. 5. Senitet San Rafael l S. T. G. Scott Oakland
- 6. L. 1.asagna Albany
- 7. C. W. Allen San Francisco
- 3. S. L. Wade La rtsour I 9. J. A. G11avne Canv111e
- 10. J. C. Vocke Lafayette i
- 11. W. A. Hutenison San Carlos l 12. M. C. Colan Oakland
- 13. M. W. Jonnson Walnut Creek
! 14 R. W. Hall Richomed
- 15. I. M. Crawford Hercules i 1
- 16. R. G. Schumatar El Granada
- 17. R. O. Fagg San Rafael l
i 18. P. C. Soettcher Moraga
- 19. H. W. Reynolds Sunnyvale
- 20. 8. P. Sadler . Belmont i
I l
j l'his listing extrseted fr:ta Safety. Health, and Claims tutmo regarding
' *ersonnel to be Cantacted for Re ceting of Ac:icents, dated 01/13/83.
I d
l L. .
l 3COC84 16V!!!
i
I i
l Safety. Healtn and Claims Personnel to be l Contacted for Reporting of Injuries at,Diablo Canyon ~
Page 2 of 2 t
i Non-Emelovee Infuries C. O. Senreil, San Luis Cbispo,' office) i i
(office
. (home) _,
If he cannot be reatned, contact one of the-following in orcer of preference:
Curing working hours:
1.
2.
3.
'onn C. Ecnois Ocug G. <eeler George G. Perg (collection only)
Af ter working hours on Moncay necugh 8:00 a.m. on Friday, except holidays:
E__
i
- 1. John C. Echols Pleasant Hill
- 2. Ocug G. (meler Concord
- 3. Jonn C. Vocke Layfayette l
- a. Anos L. Secntold Cacertino /
- 5. William H. Singaman Novato I
- 5. E. Antnany Giucici San Carlos i
- 7. J. Alex .wcCor;uccale San Ramon i i
- 8. 3mca 8 Sadler Seimont j Hayward 9.
i i
(colfactiononly Geore G. Pern )
Fairfield I
- 10. Stanley W. Johnston -
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Af ter 5:00 p.m. on Fridays to 8:00 a.m. on . Mondays and holidays:
He Contact tne Investigator delegated to stay on call for all emergencies.
If he is not available, ne l i
may te reacned tnreugn tne System Dispatener.
l Dis;a:cner will follow the precedures for "After Working Hours."
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CC0084 17VII .
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" 8E" EP "-7 I35M3 Pacific Gas and Electric Company REVISION 4
(
DATE 11/21/83
, CEPARTMENT CF NUCLEAR PLANT CPERATICNS 4
1 AND 2 PAGE 1 0F 10 lU ciABLo CANYCN PCWER PLANT UNIT NC(S) -
\
! EMERGENCY PROCEDURE IMPORTANT M LE: OFFSITE TRANSPORTATION ACCIDENTS TO APPROVED: Yb DATE
~
PLAhiMANAGg SCOPE This procedure discusses the response of the plant personnel to transportation accidents which occur offsite involving shipments of radioactive material. Accidents which occur onsite are handled using Emergency Procedures R-2, R-3, R-4, or R-5 as appropriate. This proceoure and enanges thereto requires PSRC review.
DISCUSSION Once a shipment of radioactive roterials has left the site, or prior to its arrival on the site, the responsibility for it rests with the carrier. In the event of a transportation accident, the responsibility for recovery
\ rests with the ' carrier and local and state officials, rather than with the I- Company. However, if an accident occurs in the vicinity of the plant, local officials may request the assistance of plant personnel for radiological monitoring because of their knowledge and experience and because of the monitoring and other equipment at their disposal. Plant personnel should be prepared to assist to the maximum extent practical, while at the same time recognizing that they are acting in a strictly advisory capacity.
SYMPTOMS The Shift Foreman is notified that an accident involving radioactive material has occurred.
IMMEDIATE OPERATOR ACTIONS
- 1. In the initial contact, the individual receiving the message should try to gather the following infonnation:
- a. Location of accident.
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l DIABLO CANYCN PCWER PLANT UNIT NO(S) 1 AND 2 ON CATE 11/21/83 PAGE 2 0F 10 Tats. OFFSITE TRANSPORTATION ACCIDENTS
- b. Type of material involved:
- 1) New fuel
- 2) Spent fuel
- 3) Solid radwaste
- 4) Liquid radwaste
- 5) Pharmaceuticals
- 6) Sources
- c. Type of container (s) involved.
- d. Apparent extent of damage,
- e. Is there fire or submergence of the containers?
- f. Are there personnel injuries? l l
- g. The results of any measurements which have been made,
- h. Who is on the scene and who is in charge?
- 1. What recovery actions are olanned or being taken?
- j. The identity of the carrier.
- k. Origination point and destination of the shipment.
- 1. The name and phone number of the caller. ,
- 2. Notify the Shift Foreman.
i 3. The Shift Foreman should insure that a record is kept of the j initial contact as well as all subsequent contacts with offsite persons. Form 69-9221. " Emergency Notification Record " is provided to assist in this.
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1 AND 2 CIABLO CANYCN PCwER PLANT UNIT NO(S) f0N DATE 11/21/83
- PAGE 3 0F 10 ,
TITLE: OFFSITE TRANSPORTATION ACCIDENTS SUBSECUENT ACTIONS
- 1. Perform the notifications reqaired by Appendix Z.
- 2. Send a two man survey team to the scene. The team should carry the following minimum equipment:
- a. Dose rate instrument (HPI-1010, Radowl or equivalent).
- b. G-M survey instrument.
- c. Alpha survey instrument (only if the accident involves new fuel assemblies or an alpha emitting source),
- d. Air sampler with appropriate filters and cartridges,
- e. Radiation barrier rope.
- f. Warning signs: " Caution - Surface Contamination Area" and
" Caution - Radioactive Materials."
- ( g. Smear pads and/or 2" duplex papers
- h. Plastic bag for retent'an of smear samples.
- 1. Pocket dosimeters and (if time pemits) the team members' personnel dosimeters (film badge or TLD).
- j. Survey foms (Fams 69-9315 and 69-9316 preferred, but Form 69-9259 is also okay).
EL1: It is highly desirable to take a radio if time pemits.
Al but the radio, film badge and alpha survey meter are located in the various emergency kits. Preferably, an entire kit should be taken to the scene. Radios are available in the Security Building Emergency Operations Facility and Mobile Radiological Van.
POTE 2: If criticality is a possibility (i.e. if fuel is
' suomerged.in water) a neutron dose rate meter (such as the l PNR-4cr5) could be taken if readily available. This instrument is not necessary, however, since ganna raatation always
, accompanies a criticality.
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NUMBER EP R-7 OIABLO CANYCN POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISION 4 DATE 11/21/83 PAGE 4 0F 10 Tnts. OFFSITE TRANSPORTATION ACCIDENTS
- 3. Close out with a verbal summary to offsite authorities in step 1 above. If classified as an Unusual Event, follow with a written summary to NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
INSTRUCTIONS FOR MONITORING TEAM
. 1. Make gamma dose rate measurements since this is the most likely hazard. If any significant garna dose rate is measured, erect a barrier so that all locations where the dose rate is greater than or equal to 5 mR/hr are located within it. Hang Radiation Area signs as appropriate.
10IE: Members of the general public, not participating in the recovery effort, should be kept at a distance beyond the 0.6 mr/hr isodose line by an appropriate barrier.
- 2. Make a direct alpha and/or beta-gamma survey, as appropriate, of the ground and the surfaces for the container if contamination is a possibility. If contamination is found, above the specified limits, erect a barrier around all areas where the contlevel is the most restrictive of the following:
- a. 100 dpm/100 cm2 if Pu *439 may be present.
- c. 5,000 dpm/100 cm2 if none of the above are likely to be present in significant quantities.
The survey is made by holding the probe within 1/2 inch of the surface without actual contact. The net count rate is converted to dpm/100 cm' by the following formula:
[dpm/100 cm2] . (CRn ,g) epsilong OC0009 4I!!
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N CIABLO CANYON power PLANT UNIT NO(S) 1 AND 2 R ON DATE 11/21/83 PAGE 5 0F 10
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Tnis. OFFSITE TRANSPORTATION ACCIDENTS where:
CR = net cpm on instrument net
= (cpm) gross, shield off -(cpm) background epsilent = probe efficiency factor from Table 1 NOTE 1: The alpha probe is sensitive to sunlight. Therefore, sniend the probe to the extent practical.
NDTE 2: It is not necessary to erect barriers for both contamination and dose rate. Just erect the one which keeps persons farthest from the source and place both types of signs on it.
- 3. If significant contamination is found in Step 2 above, smear samples can be taken to determine whether snearable contamination is present. If alpha contamination is likely, use 2" filters for i taking the shears. Retain all smear samples for subsequent
- laboratory analysis.
Count the samples and determine the [dpm/100 cm2J in accordance with the following formula:
[dpm/100 cm 2 j .
net)
(epsilon 2) (A) where:
(CRnet) = net cpm as above epsilon 2 = probe efficiency factor from Table 1 A = area smeared (ft2 )
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ciAeLC CANYCN POWER PLANT UNIT NO(S) 1 AND 2 h CN CATE 11/21/S3 PAGE 6 CF 10 TiTts. OFFSITE TRANSPORTATION ACCIDENTS 4 If criticality or fuel melting is a possibility, erect barriers at least 100 yards frem the scene.
- A criticality is accompanied by a blue flash which is dQI(ble visi even when a person is not looking at the source.
S. Obtain liquid samples if it appears liquid contamination is a problem. These should be labeled and returned to the lab.
- 6. Report in to the Site Emergency Coordinator at least once per hour and determine the meteorological conditions.
- 7. Maintain exposure as low as reasonably achievable. Do not exceed any normal exposure limit without authorization of the Site s Emergency Coordinator. Try to prevent any unbadged person from 4
receiving more than 250 mrem.
- 8. Advise state and/or local officials of methods which could be used to contain the spread of contamination or minimize the radiation field. These may include the use of wood or metal sheets, plastic or cloth tarpaulins, firefighting foam or dirt berwm and rocks.
- 9. Advise and assist in the treatment of any injured and/or contaminated personnel using the techniques specified in the Radiation Control Standards and Emergency Procedures.
ATTACHMENTS
- 1. Form 69-9221 " Emergency Notification Record"
- 2. Form 69-9315. " Contamination Survey Record"
- 3. Form 69-9316. " Radiation Dose Rate Survey Record"
- 4. Form 69-9259, " Emergency Environmental Monitoring Field Data Sheet" e
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l DIABLO CANYON PCWER Pt. ANT UNIT NO(S) 1 AND 2 {0N 01TE 11/21/83 PAGE 7 0F 10
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TITLE: OFFSITE TRANSPORTATION ACCIDENTS
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SUPPORTING PROCEDURES EP G-2 Establishment of the Onsite Emergency Organization EP G-3 Notification of Offsite Emergency Organizations EP R-1 Personnel Injury (Radiologically Related) and/or Overexposure'.
EP RS-4 Access to and Establishment of Controlled Areas Under Emergency Conditions.
RCP G-6 Release of Materials from Controlled Areas.
EP RB-6 Area and Equipment Decontamination.
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, 1 NUMBER EP R-7 otABLO CANYCN PCWER PLANT UNIT NC(S) 1 AND 2 REVISIGN 4 CATE 11/21/83 PAGE 8 0F 10 rnts. OFFSITE TRANSPORTATION ACCIDENTS TABLE 1 i
PROBE EFFICIENCIES FOR SURVEY INSTRUMENTS PROBE EPSILON' (direct survey) EPSILON 2 (smear)
(com/ dom /100 cm2) (com/ dom)
HP-240 0.011 0.018 HP-260 0.040 0.20
? HP-210 0.040 0.18 HP-230A 0.0029 0.016 i
Alpha 0.056 0.095 O
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l NUMBER EP R-7 ,
CIABLO CANYCN POWER PLANT UNIT NC(S) 1 AND 2 RE'/ISION 4 i
CATE 11/21/83 PAGE 9 0F 10 7nts 0FFSITE TRANSPORTATION ACCIDENTS APPENDIX Z EFERGENCY PROCECURE NOTIFICATION INSTRUCT!CNS
- 1. When this emergency precedure has been implemented, and upon direction from the Shif t Foreman, proceed as follows:
- a. Notify the follcwing plant staff personnel, or their designated alter 9ates:
Plant danager Plant Su:erintendent Supervisor of Chemistry and Radiation Protection Pcwer Plant Engineer Supervisor of Ccerations Technical Assistant to tne Plant Manager
- m. Report the situation to the Ccunty Sheriff's Office and California Office of Emergency Services. They may already be aware of the situation, so this may be a courtesy call.
- c. If the shi; ment originated or had a distinction at the plant, designate this event a Notification of Unusual Event.
Notify plant staff and resconse agencies required oy Emergency Procedures G-2
- Establishment of tne Onsite Emergency Organization" and G-3 " Notification of Offsite Organizations" in accordance with Emergency Procedure G-1
- Accident Classification and Emergency Plan Activation."
- 2. In addition to any notifications performed under 1 above, also notify the following company personnel:
- a. Supervising Nuclear Generation Engineer (Personnel and Environmental Safety):
Mr. W.H. Fujimoto "PGandE office l Office Mcme 1
$[IE: If the above cannot be premptly reache request the system dispatcher to contact alternate personnel.
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1 Nyvera ep p.7 OtABLO CANYCN PCwEA PLANT UNIT WS) 1 AND 2 REN5*0N 3 CA?E 11/2;/82 PAGE 10 CF 10 rir a OFFSITE T:tANSFORTAT CN ACCIDENTS
- b. Los Pacres District Manager:
Mr. D.L. Kennady _
lffice Office Home
- If the above cannot be promptly hed request "cero pSwitchingCentertocontactalternatepersennel.
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69-9315 7/30 (100) DEPARTMENT OF NGCLEAR" PLANT OPERATICNS DIABLO CANYCN PCWER PLANT CCNTANINATION SURVEY RECCR0
' SURVEY NO.
t- SWP/RWP NO.
CATE TIME AREA CR ECUIPMENT DIRECT SURVEY RESULTS TYPE INST. DETECT 0p GROSS BX3 NET EFFI. cem_
CIENCY Cm' ITEM CESCRIPTICN , l g, , fjQ USG CPM CPM CPM l l I I l
REMOVABLE CCNTAMINATION SURVEY RESULTS INSTRLNENT USG TYPE AREA, COUNT TOTAL GROSS B.% NET EFFI. dem ITEM OESCRIPTICN , jov d TIME COUNTS cpn can cm CIENCY cm-l l
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CCm ENTS COUNTED BY CATE/ TIME SURV YED BY ,
REVIEWED BY DATE j
SUPERVISCR
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69-9316 7/00 (100) DEPARTMEtiT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT RADIATION DOSE RATE SURVEY RECORD
( TIME SWP/RWP NO SURVEY NO.
DATE AREA CR EQUIPMENT '
SHEET OF TYPE OF SURVEY l
BETA GAMMA NEUTRON ITEM DESCRIPTION NO* m rad /hMistance mR/hrldistancerem/hr I distance 1
i SURVEYED BY SURVEY TYPE INSTRUMEffT TYPE DETECTOR SERIAL NO. DATE CALIS. DUE BETA GAP 9%
NEUTRON COPMENTS RECOMMENDATIONS SURVEY REVIEWED OATE SUPERVISOR e
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Page I of 2 69 9159 7 /83 (10CO) PACIFIC GAS AND ELE:Taft COMPANY
- NUCLEAa PLANT ;PERATIC;'$ ,
DIABLO CANTON PC'=ER P'. ANT LNIT NOS.1 AND 2 EwEt:ENCY ENv!RCriMENTAL *CNITCR t:G F;ELO DATA Skt!T _
Team Leacer ueceer
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%nttoring Location l
l I 1. THREE FOOT SETA.G#eA RA0!ATICN FIELO READIMS
- s. Count Rate Calibration Due cate f, C Wfshield offfv7)] :Puf tmiele en(ee.n)]
7,, ,f Tj,me,, 8mee Gross SG' Net Gross fr0* Net i
- b. Oose Eate Calibration Due Date ,
i at/netuincow Ceen) at/*rfwaee. C1esed) instrurwat Gross 8G' - fiet Gross Br3* 9et l Tfw
- c. Integral Dose g g g g g Time Time DuratRn(HR) Total Dose ea tefmR/hr) instrument Sta rted Casolete (Ij.w Cose(wt) @. O
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\ t I 2. AIR $ AMPLE DATA Calibration Due Time Time vuration Flow hte Samole Volume i
(*nutesi (CFM) frT3) f
$arelee M Comoleted I
- 3. PARTICtJLATE DETERMIMT!DN l
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Tice of C W(Shield off) O O a, E. f C'm59'IOg,w 8eece Gross SKG
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4 1001NE DETERMIMTION
@s $9:10 Typ of CPMf5ntetd Off) @ g C yolume(FT8) gd a b:aL 'ac:11_ SE2' Met ..
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- %'MERICAL VALUE FOUNO IN OtERGENCY PROCEDURE RI.7 QR RI.8 i __
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- 5. ENVIRCbkb5L NNITOR REA0!NGS I
P!C Reading Calteration Owe D. T*f0 4 Reactng Calibration Owe a.
time Dole Rate (mR/he) h h Count Scaler Time @+@
t= Alar
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- 7. VEGETATION $AMPLES NOTE: USE HP.240 CA EQU1YALENT PRCBE CPuf5hield off) ti=
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Desce+otten Gross E
' 8. SMt.AA SAf9LES 3 Area 0.11 3 0
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- 9. LIQUID SAMPLES l I"'nersion Data Time Volume of Gross Net
,I Desertotion Samole Counted CPM BKG* CPM l
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- 10. REMARK 5
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NLMBER EP M-1
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~ J E; 1- Pacific Gas and Electric Company REVISION 11 DATE 12/29/33 EFAATMENT OF NUCLE AR Pt ANT CPERATICNS
, OIABLC CANYCN PCVvER PLANT UNIT NC(S) 1 AND 2 'PAGE 1 0F S h
IN Ph EMERGENCY PRCCEDURE h TITLE EMPLOYEE INJURY OR ILLNESS (NCNRADICLOGICAL)
AP*aCVED: Yb CATE PLANT MANAG8 SCC E This procedure cescribes the actio,15 which are to be taken in the event of an illness er injury to an employee which does not involve Injuries in which radicactive contamination or overexcesure.
radiolcgical censiderations are involved are discussed se:arately in the R series of Emergency Procedures. This procedure and changes thereto requires PSRC review.
APDLICA3ILITY This peccedure is to be folicwed for incidents involving Nuclear Plant Ccerations personrel, or other coepany employees at the plant site at tne recuest of tne Nuclear Plant Operations Department. In the eve'1t I of an incident involving any other ccmcany employee (such as a General Construction Emcloyee), perform only the asterisked (*) steps in :nis orCCedure.
I+EDI ATE ACT!CNS The emoloyee(s) who are at the scene shall:
- 1. Render all necessary first aid.
- 2. Notify the control recm (Shif t Foreman) as soon as practical.
hif* reman m
- notifiedbydialing5xt PCTE: 7 ialing activates the fist alarm and recical emergency code ca i. The caller must remain on tne phone to enable the Shift Foreman to dial into a conference call.
SUBSECUENT ACTICNS The Shift Fereman shall direct all subsequent actions until relieved by the long term Site Emergency Coordinator if the emergency warrants it. Sucn actions snould include the following:
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- HASLO CANYCN PCWEA PLANT tmaT NOl51 ON DATE 12/29/S3 PAGE 2 CF 5 78TLE EMPLOYEE INJURY OR ILLNESS (NONRADICLOGICAL)
- 1. Scund ecergency signal, code override, or other general warning signal to clear the area if tne situation warrants it.
- 2. Dispatch additien11 first aid persor.nel such as the project
- ne scene of :^e construction injury or illness ifEMT L(Extension=M.
recuired rersonne o have not ceen instructed to provide assistance at the scene should remain on their jces and stay clear of the affected area.
- 3. Trans; ort the injured person to a Ccepany panel physician of hospital if the situation warrants it (refer to the attached list). If possible, tne employee is to be acccroanied by a su;e rv i so r. The practices wnich are to be follcwed if this step is necessary are given in the follcwing section of this procecure.
4 Secure the names and adoresses of all witnesses (both Cor:any ano non-Cor;any).
- 5. Perform the notificatiens required by Appendix Z.
- 6. Complete the appropriate accident report (s) and forward to the office supervisor for processing.
- a. Form 62-4587, " Report of Industrial Injury to Employee" in cases =nere no medical treatment was required other tnan minor first aid at the plant.
- b. Form 52-4586, " Employer's Report of Occupational Injury of Illness" in all cases requiring medical treatment (including cector referral) other than first aid or results in lost time beyond the day of injury,
- c. Form 52-5542, " Report of Automobile Accident" if appropriate.
a TRANSPORT 4TICN OF INJURED PERSCNNEL
- 1. The preferred mode of transportation for injured persons is by Company panel amoulance service. Company or private venicles should only be used in cases where the delay associated with securing an ambulance might result in significant deterioration of tre injured._ person's condition, or when the injury is of a minor nature where use of an ambulance is not. warranted.
OC0152 2XII e
I AND 2 I . U M-1 3 ,4 ego :ANvCN ACWEE D'JNT UNIT NCISi CATE 12/29 53 PAGE 3 CF 5 t,t LE EMPLOYEE !!CURY OR ILLNESS (NCNRACICLOGICAL)
- 2. When retuesting ambulance service (refer to the attached list;,
. provice the following infcrmation to the amoulance service,
- a. Name of caller
- b. Company affiliation
- c. pnene numcer of caller (where he can be reached)
- d. Name of injured or ill person
- e. Where the patient is located
- f. Where the patient is to be transported 9
Nature of injury or illness
- h. Any other medical information which might be pertinent to transporting the injured person Record this information on Form 69-9221. " Emergency Notification
' Record", or otner log.
- 3. If ameulance or medical rsennel are to enter the site, contact I the Security Department
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nd have them notify tha security force at the Port LuipeTtrance. It is necessary :.o have an escort accompany the amculance personnel from :ne ;
l Security Buildin's to the patient.
i n 4 If possible, have a supervisor accoccany the injured person to '
the hospital (or docto'r's office). If this is not practical, call a supervisor and have him meet the patient at the hospital (or doctor's office). The supervisor should inform the doctor about the Company's light duty program.
- 5. If possible, call ahead to the hospital (or doctor) and provide the following information:
- a. Name of caller
- b. Company affiliation i
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- sasco cANYCN POWE A PLANT UNIT NC($)
DATE 12/29/53 PAGE 4 0F 5 T6TLE EMPLOYEE INJURY OR ILLNESS (NCNRADIOLOGICAL)
- c. Phone number of caller (where he can be reached)
- d. Name of injureo or ill person
- e. Age of injured or ill person (approximate if not known)
- f. Extent of injury, illness or symptoms .
- g. Medical history (if known)
- h. Radiological conditions.1 Record this information on Form 18-9221, " Emergency Notification Record", or other log.
- 6. A medical referral, Form 62-6015, shall be completed and sent to the hospital (or doctor) with the injured person along with a copy of the Light Duty Program Letter (copy attached). These forms should be taken by the accompanying supervisor, the patient, or the ambulance driver, as appropriate. Do not delay transport of seriously ill or injured persons while obtaining these forms.
REFERENCES
- 1. Rule 16, PGandE Accident Prevention Rules.
- 2. PGandE Standard Practice 250.
- 3. NRC Information Notice 80-06, " Notification of 'Significant Events."
ATTACHMENTS
- 1. Form 62-4587, " Report of Industrial Injury to Employee"
- 2. Form 62 4586, " Employer's Report of Occupational Injury or Illness" .
Ilf the injury or illness is involved with radiation, see "R" Emergency Procedures. However, the hospital should also be informed when radiation is not involved, because in the absence of such knowledge, they wiTT assume that radiation is involved.
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SNE 2 NUNObb bb N-I OiABLC CANYCN PCWER PLANT UNIT NC(S) REVISION 11 DATE 12/29/S3 PAGE 5 CF 5 7'TLE EMPLOYEE INJURY OR ILLNESS (NCNRADIOLOGICAL)
- 3. Form 62-6015. " Medical Referral" 4; Form 62-4542, " Report of Automcbile Accident"
- 5. Form 69-9221, " Emergency Notification Record"
- 6. Light Duty Program Letter
- 7. Company Panel of Physicians, Ambulance, and Hospitals serving the immediate area around Diablo Canyon.
- 8. Panel of Physicians, Ambulances and Hospitals, Coast Valley Division, SP 251.1-1.
- 9. Safety. Health and Claims Personnel to be contacted for Reporting of Injuries at Diablo Canyon.
- 10. Appendix Z, Emergency Procedure Notification Instructions I.
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i 3 nea7*er.?n1 PACIFIC GAS ANC !!.IC RIC OOMPANY f 1 i
Resort of incustrial Injury to Emcloyee
- 1. Name S. Civissen Accress I:P 2.
- 3. Teisonene No. 7. Cecertment i
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4 Social Secunty No. 8. Cate of Accicent S. Cae:.cacon 9. Tme of Accicent
- 10. t.ccreen of Ac=: cent i t. Nature Of Injury i
- 10. 'Nhat were vcu =cing anc ' ow cic sc:: cent oc=ur?
- 13. Cascrte F rst A;c rencerec:
14 Wivesset n accicene 1.
2.
- 3. 15.
Sgnanareof Emciavee
- 16. Oate irnury ascce se:
! 7. Cate *0 . esys etanses: 18.
-' See Cver Sqnsnare of Sucerviser INSTMUCUCNS. D s recen litems 12*u 15 secuic ce arrr:3n anc signed =v me emcievee ersen.
ar/v anc ==untersgne2 tv me sacervisor. It is 'or asi Incuseas iniur'es anc is in cucticate. De cr ginai
.: m :e aetainec 'or C.:mcany recorus: me =cov is :n to cetacec after c=mstet:en anc given :n me emaioves. Sefere sgning 'n item 18.-fe asservrsor snouic 511 in me case of me ascert (Item 161 anc c=rnoute anc netzte me cate .70 cay ' rem me case me iniury was recorren (Item 171.
If me amcievee 'ater scuirse ressment =v a.=ce:nr or tec=mes cissoiscr. Ptrm 52-a535 must :s
. m. anc trwercee :n me Safety. Healm anc C". aims Cecartment /MMfCIA'"Eif amcaniec ey me original of mis recer: .
If me ernotaves is uriscie :n 511 out or sign mis racer. It snoute te .:recarea signec ev me sucerviser anc me emaiovee sncuic ce given a c=cy wimin 5 cays as recuirac tv 'aw, if me insurec erncievee =snnet nr'te Ing:isn me scort mav :s mace ac=crcing :n a -eer:si r:ztr set.
if ecesserv, me smeieves may sgn av a marx anc a witness to me recort snovic sign :eicw me em.
=ioves s marx.
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une omsug omsesusue a se asne of eview.
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- I
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4 Resort e Date 19 -
Dr.
Cnciv pv'e :o : ester.
we. . Ms.
.necic:a a:ennon, wo 'orwar 2 :omoiete e:2nec ecor meeci.
untv :o Manager. 54ierv. .wesam wa Caams Oecc. 245 warue: Scree:.
San F .nc:sco 4 tC6. Your ills snousa se itemizee wa al = dis we resorts weerse in :rtaticata.
P4CFIC GA5 ANO El.IC t:C COMP ANY i
i
! g, :== '
. m .. ..cv s,eei w '- - 8==a-Pt.D5E COMPT.E'E ANO RETURN TO LMPt.QYE1
'escuzvts wust wavs cease r ra came to a:Tuan to woax:
Pissfic Gas ane Ese:nc Cu Cass 19 _
wr W.
Occusanon Resort
- L-eosovea av _ '"" Divmon.
m Inmren at s.m. on .19
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O % woru W M O umsse a -ers .sima '
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(*
(
Report = Date 19 -
Dr.
- Kindly give to bearer, Mr./ Ms.
medical attention, and forward a complete oetailed recort immedi.
stety to Manager, Safety. Heaitri and Casms Deet. 245 Market Screet, San Franc:sco,94106. Your bills snould be itemized and all bills and reports rendered in trioticate.
PACIFIC GAS AND ELECTRIC COMPANY Sy I*** I se ees (nev.s/sel angr. Fe-amm. h t
( Pt. EASE COMPT.ETE AND RETURN TO EMPt.OYEE (EasnLovt1 asuS7 MAwt1:DeantrTED CAAS M RETURM 70 WORK Pacific Gas and Eastric Ca.: Dase ,'19_
Mr./Ms.
Occupadon Report =
Employed By l **
- I Division.
Iniured at S. on ,19 C Ramon to fWI warm inunaminary C Assammswarsumse C Unmue en uswu unal C Rummenene er unnamens C Reesu Aest. Ommet T1nuut C Demmergus semi summaane -
sised wo.
e O
- n I
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- i
[ canna.nti.i For Use by Company AT:cmeys Only
- ~**"""** REPORT OF AUTOM'OSILE ACCIDENT h OTHEURIVER se-e accre. s u. u...
- eae No va.e :s -a.ee ,e ,,,y,,,,c,,yuy,,,
- are or covator s Alons voor Sec. % moc : v er 5,rta L c. No. $ tate insursace Coraosaw
@ OTHER VEHICLE 08 PSOP'*N OWNER -
same accre. e cee No.
. Co,or vree v s.e 7,oe ve .r L.c. N.
eiaCht No
- - " - *e% ass :DI.'** .
maut acCaEss 0
PAS $1NGERS~ - - - -
IN OTHER - -
V!HICLE S. 3 WIT N ESSE S. 4 - - -
OR INJURED -
PERSONS 5-6 aw. ;-ta s..*t; e**cas se -ts =o -
=aus accatss G ,
PASSENGERS - - -
IN COMPANY VEMICLE 7
, =
O5 On at mours. Ca ' ~ ~ ~
DATb1ME in AND LOCATICN at aear '"" " " " " ' ' '
- ~ - - ' " ' * " " " " '
0F ACC:0ENT
'/-
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DESCRtPTtCN OF ACC; DENT Camesete setsds of ' low .. . . .__ _.
accisent occuttee O'#** "" t" *8 8"8 '*l" 8 :8"8'*"5 Nwmoor or inet ce'es *a Camoan, ven.c e Nwmoer of test seits in se at t rae or acticeat
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CESC9iSE OAvaOE TO Cast if snowa or eer-ce Otrer vrec'e ss or 8-ooerry vecer $3
- Over !!
@S 5 : Lev 5*:
VEHICLE CESCRISE CAMAGE 'O C Camoen, venicie C Lesse 8aataa vece CPersoeas vence Cast 'f snown ,0' est:raate.
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& Cm 3nver:L.c. No. Cass Emoerotion Date Y
INFOR ATj0N E**" O O O' " 0***"'"'
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nu:22'* =f C* st*Iing indufi ts -tCui-* ng -
i . e. , its: re 1.*Qud ts , "las tr1Jua C1Ily ine tasad.
' we :ei f e e =a: s_- :e :1 =1s :d== awy f-:s wort sign: essitiy te aveicac f f Os tv4fla211f ?/ cf lign; (mecifi4C} Cu?/ cr cask-7/*4 wert wert ::-"3 wi esiy i.-=wt. !c:a :nysicians have s 2:ac =a in s::ne cras =a :at ent wit: ess:=nc i1.:-t .t=icly = : ta==ent if ke t tusy in a lignt-car / c2:ac rf.
7-::::: ve.1:gns. cur / ass enstan= An al==st dalways availa-Ie #te ac:*:yass etieasac ':r acrt imin =a =aci:21 -tst:- ct :ns es" lisc.ec ty es :. ysician.
- ur ::1f:y := ' ave an injurtc arelcytt ac_ .aniecShtvulc a su ar-riser
=ar's :s any=r: ss-c:str t:-tsan 2=ve :n =2 fint :: .:r's 'tisit.
ti n a:cu: =t availacti tr/ cr :/ a 41 I f g.-: :u:y : .a: =an :x :r: ri:ac. .is r see .31** :s acit = ans er f:r as.
Se ewicyees
- elfart is :ur ra's ==:a - . Theut e you ' ave an/ :ues- :=s a::u; :ur :r:;-s=, I will te glac = :211 en ycu at ycur ::nsenianca.
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Page 1 of 2
- /c3 CEPARTMENT OF NUCLEAR PLANT OPE
- A*!CNS DIAELO CANYON POWER PLANT Cemeany Panel of Physicians, Ameulances, anc Hescita's l
Servine the Imreciate Area Arcure Diacle Canyen' Arbulance Name Address Phone Re9 arts l Radiation Ex;csure l San Luis Acculance Service Da: Tents l
I 1
< Five Cities Actulance Se rvice i
Scuth Bay Fire /Arculance l
Bay Acculance i CENTRAL DISPATCH FOR ALL OF THE ABOVE AMBULANCE SERVICES l rescitals l Radiation Excesure l Frencn Hcspital i Patients-External !
- Defit. E uio.
l 1
i ** Sierra Vista Hospital External
! (20 minutes to clear for Defibrillation I
helicopter) Ecui; ped a
I Arroyo Grande Community External I Hospital anc Fecical Defibrillation Center --- E;uipment l
f l
OC0152 6VII
i Page 2 cf 2 Physicans San Luis Medical Clinic I l
I
- Richard E. Fleming Industria: Inj u ry ,
- Treatren
- anc E.<e Injuries
) .
4 T. A. Beresky Eye In;ur:es l
Industrial Injury I =0av1c ~. Ralston anc Preem:i:fre-: ,
Physical Exams j
Laurence H. Lot: Industrial Injurf and Preem:loycent l
- Physical Exams l 1. This list extracted from Standard Practice No. 251.1-1, Panel of ,
l Physicians, Amculances, and Hospitals,' Coast Valleys Division, l
- dated 9/29/83.
I {
4
- 2. See also EP OR-1 "Offsite Support and Assistance" for Air
{' Ambulance and Medical Support.
I *Willing to fly
- helicopter landing facility available l
l l
l l
l l
l l
DC0152 7v11 ,
l
- G e
PACIFIC GAS AND ELECTRIC COMPANY SAFETY, HEALTH, AND CLAIMS CEPARTMENT PANEL OF PHYSICIANS, AMSULANCES, AND HOSPITALS CCAST VALLEYS DIVISICN l
. SP 251.1-1 Page 2.1 Issued: 9/29/83 TCWN ACCRESS TELEPHONE SERVICE
{ AR;Cv0 GRANCE I Five Cities Ac:ulance I i Service l I CENTRAL CISPATCH j A.G. Ccnrunity Hcspital
- and Mecical Center ,
i I l l
ATASCACERO [
t .
I I Occtors l i !
l North County Medical l Services (Emergency .
. Mecical Tecnnician)
J CENTRAL DISPATCH i
l Twin Cities Ccmrunity j HCs; ital SAVWC00 PARK - LOS 0505 -
Scuth Bay Fire /Arculance CENTRAL DISPATCH 1
1 1 - Industrial Injury Treatment i E - Preemployment Physical Examinations l EYE - Eye Injuries i
PM - Paramedic Services ,
j "OEF" - Hospital Equicced with External Defibrillators !
l - Willing to Fly
- - Heliccater Landing Facility Available ;
RAD Radiation Excesure Incidents ;
l l l
l
- l r
l OC0152 8VII t
- - - . - - - - - - , . na,-- ._.n .. -- -.
SP 251.1 Page 2.2 Danel of Physicians, Ambulances and, Hosp,itals Issued: 9/29/53 Coast Valleys Division ADDRESS TELEPHCNE SERVICE TCWN CAPSRIA ,_.
Am:ul Cam.Oria Ambulance
, Service Am:ul CE.'CRAL DISPATCH l CAR *EL g Am0ul Red Cross Acculance C: uni:y Hes: ital of Has: C E.:
ne w cnterey Peninsula 1
i CARyEL V ALLEY
.. I C. Winter Van Horn t.
I
- aulino E. Ic::ne: !-E
- AS~RCV:LLE i I
i
'ose:n L. Kirch I-E l I-E l 3ert Clair Eliason FCLL! STER f
! N.L. Currie .E Ma- in M. Bress I.E 5:e:rens & 3cletti Accul l
! Am:ulance i
Ha:el Hawkins Hescital H0sp OEF
<! u CITY l Ouane F. Hyde I-E 5outh County Artulance Actul George L. Mee Mercrial Hoso OEF HosDital i
OC0152 9VII
.O
l l
- SP 251.1 Page 2.3 Parel of Physicians A.Teulances and Hospitals *
- Issued: 9/29/$3 l
Coas: Valleys Divisien i
TC N ADDRESS TELE 3hCNE S ER's :C E LCMPCC l C:rrunity Ameulance A,r u i i Se rvice l .
i Lemecc Hospital Distric: Hes: CEF
.{
l t
.I LOS CSCS
! l I '
(cuth Bay Fire A;:ul Ce:artrent/Artulance
! CENTUL 015 PATCH I
' l
- C N ~. :. .rY . g l a.A. Carna::o I.E l Nelle 3 Terri
- .E
- H: ward 3 ess . I.E j Jcnn J. D'A::il:0 Eye j George S. Cam:icn .
e je I
Eskat:n Health Care Hos; CEF g
j Center (24-hour i
Emergency Service) 1 Peninsula Cen unity Hosp CEF I
i I
VC970 SAY g Bay atr::alance Actul i
k I
1 1
l i
1 l
i CC0152 10VII O
W
Page 2.4 SP 251.1 Danel of Physicians, Ambulances an( HosQitals Issued: 9/29/B3 Coast Valleys Civision ADCRESS TELEDHCNE S ER'! CE TC'.N PASO ROBLES
' Stanley J. Kirk $ I-E Physicians' Ex:nange Pr;fessional Arculance Ar:al l
l Se rvice CENTRAL OISPATCH ac:ul i
Iwin Cities Hos; ital H0s0 CEF 1
SALINAS i.
t W.H. Lawler, Jr. I-E l
i l
dcward C. Miles I-E l E?
l Glean H. SE.i!N f
! E.2. Ocng E/e l 4:cer! Avila I-E l
i A-1 Arculance Service Arcul j
Saliras Valley Hesp OEF Memcrial Hcspital l l I 1
- 3::ert G. Van Hcrne E
! l SAN LUIS OS!SP0 l
- Rt: nard E. F1 eming I-E I.A. Beresky Eye l
.i I 4
-l Laurence H. l.ot: I-E '
i, SLO Medical Clinic ,
i
- San Luis Amculance Accul RAD l Se rvice CENTRAL DISPATCH Accul i 1
French Hospital H0s0 CEF RAC l 1
" Sierra Vista Hcspital Hos: lEF '
(20 minutes to clear for checcer) i l
l Ca<id W. Ralston I-E l
\
l OC0152 11VII i
l l
SP 251.1 Page 2.5 Panel of Physicians Ambulances and Hospitals * *
!ssued: 9/29/83 Coast Valleys Division
- C'a N ACCRESS TELEPHCNE SERV!CE SANTA SA EARA St. Francis Wescital esc CEF SAETA WARIA Brian J. Kiniry I l Jules Ser ero I-E
'w a rry (, Lienke !-E
'Ocnale E. Reiner !
l 0.0. Sne;ar Eje I
a
- Incustrial Medical Greus of
{
- Or. Se: y Suits Tices !-E Or. William J. Tites !-E acculance Service Accul :M Santa Maria irculance A.?cu l l Se rvice k olice Oe:artrent Accul i (For Emergency Cnly) {
- arian Hospital Hos; OEF Valley Community Heso aos:1:al
- SCLE:A0 1
1
! Selecac Am.culance Accul
! Service (County Emergency
) Se rvices )
I i
1 1
i i .
OC0152 12VII
l l
l Page 2.6 -
l SP 251.1 Issued: 9/23/33 l Panel of Physicians Actulances anc Hospi.ois Coast Valleys Divisien l
TEL~ PHONE SE;V!CE TOWN ADCRESS i
I i
50LVANG
! I-E
! F.A. Pedersen I-E W.B. Van Valin .
l '
accui l Coas Actulance Se rvice ^
l 4
Hesc OEF j Santa Ynez Valley
- Mospital l
i TEv:LE7;N, l
I-E I
- eter S. Davis ,
i 1
l I-E i Wittarc Csitin -
l *a.A. areenman .
i
. l A.T.c u l CENT:AL DI57ai;H f
I Hes: CEF i in Cities bes: ital l .
' WATSCNVILLE I-E t
'E.H. Eiskarc l I-E i
! P.K. Gilman I-E i Cavic E. Sas.. Tan Eye !
- cuglas A. Licciccat ye ;
l 4 dece Wilscn !
l i A.?cul l
) A-1 Watsonville ;
l A.?culance i
- Mcsp CEF i
- Wa:scnvilla Ccmmunity i ecsoital I
OC0152 13VII
'_.e---.,-...-.---c.
PACIFIC GAS AND ELECTRIC CCMPANY Page 1 of 2 11/83
! DEPARTMENT OF NUCLEAR PLANT OPERATICNS
]
l DIABLO CANYCN PCWER PLANT UNIT NCS.1 AND 2
! Safety. Health and Claims Personnel to be y Centacted for :ecertinc of In:urtes at Oiatlo Canycn
, EMP.0YEE INJURIES In all cases of serious employee injuries (for example, injuries involvin; l
J nespitalization, electric contact, hernia, amputation, fractures, er injuries excected to result in Icst time from aork beyced the day c' injury) er deatn wnicn occur while an the jce, report snould be mace as folicws:
Curinc '=crcinc deurs:
T. B. Mcney GandE loca (If Mr. Screy is not availacle, the peIsen answering the tele:ncre will take l
the message anc not1fy Mr. Hcney or any otner parties necessary in tne j Safety, deal tn anc Claims Department),
i An_v C:ner Time:
1 Re;cet to one of the persons on the follcwing list, trying each in creer until one is contacted:
l i
- 1. T. B. Herey Pinole
- 2. A. Thcras San Francisco
- 3. C. B. Pcwell San Francisco P. S. Senitez San Rafael 4
S. T. G. Scott Oakland i 6. L. Lasagna Albany 7 C. W. Allen San Francisco
' 8. B. L. Wace Larkscur
- 9. J. A. Glime Danville
- 10. J. C. Vccke Lafayette
- 11. W. A. Hutchisen San Carlos
- 12. M. C. Colan Oakland i 13. M. W. Jennsen Walnut Creek' 14 R. W. Hall Ricncmod
- 15. I. M. Crawford Hercules
- 16. R. G. Scnuraker El Granada
( R. D. Fagg. San Rafael 17.
- 18. P. C. Scettcher Moraga
- 19. H. W. Reynolds Sunnyvale
- 20. 9. P. Sadler Belmont IThis listing extracted from Safety, Health, and Claims remo regarding Personnel to be Contacted for Re orting of Accidents, dated 01/13/93.
I Fcund in PG&E Standard Practices S.P.251-2. l ,
DC0152 14IX
Safety, health and Claims Personnei' to Se Page 2 of 2 Cor.tacted for Re;crting of Injuries at Diablo Canycn Non-Emclcyee Infuries ,
C. O. Schreil, San Luis Obisco, office)
(office)
(heme) ,
If ne canne: te reacned, centact one of the'fellcwing in orcer of preference:
During acrking hours:
- 1. John C. Echols
- 2. Ocug G. Xeeler
- 3. Gecrge G. Perry (collection only) after .ortine hcurs en Scaday tnecuch 9:00 a.m. en Fridav, exce h lidavs:
'~
- 1. Jonn C. Ecnols Pleasant Hill
- 2. Ocuglas G. Keeler Concord '
- 3. Jenn C. Vocke Layfaye::e A. Cenald A. Rushton San Mateo S. William H. Bingaman Novato
- 6. E. An:neny Giudici San Carlos
- 7. J. A'ec ucCor;uccale San Ramen S. Stanley W. Jennscn Fairfield
- 9. Secrge G. Perry Hayward (c0llection only)
- 10. Bruce P. Sadler Belmont Af ter 5:00 p.m. on Fricays to 8:00 a.m. on Mondays and holidays:
Ccntact :ne Investiga:cr celegated to stay on call for all emergencies. :-e may be reacNed thecugn tne System Dispatener. If he is not available. ne Dis;atener will follcw the precedures for *Af ter Working Hcurs."
i OC0152 15IX
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' " 0 'I I OiASLO CANYCN ACWEA p'. ANT UNif M3tSi l' A$D 2 REVISION 11 1 DATE- 12/29/83 1 fiTLE EMPLOYEE INJURY OR ILLNESS (NON-RADIOLOGICAL)
PAGE 10F 1 l ATTACHMENT 10
. EP M-1 APPENDIX Z z l
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- 1. When this energency procedure has been implemented for injuries or illnesses Occurring within the plant gate, and upon direction frem the Shift Foreman, I l proceed as follcws: i
- a. Notify the Plant Manager or his designated alternate,
- b. Notify the Cemeensation Claims Representative, Department of Safety Health and Claims, per the attached list of personnel.
- c. Review the circumstances causing the injury or illness against the crite-ia for re:crts to NRC contained in Acministrati <e Or:cedure C-11, -
Sc:cleme9: 1, 'Su: clement 1 to Non-Routine Notification ana Re:orting to the NRC anc Otner Goverr ental Agencies," Accendix 1.19. "Rescrting of Significant Ocerating Events.' If circumstances warrant, designate tne event in accordance witn the criteria contained in Procedure C-11.
t
- d. Also notify the follcwing if NRC is notified - Supervising Nuclear l !
Generation Engineer (Persencel and Environmental Safety) er his alternate in tne Ce:artment of Nuclear Plant Operation:
Mr. W. H. Fujimoto
~)GanoE ' l Plant Extension Hcme .
NOTE: If the above General Office person cannot be pecmotly reached, l l retuest the Systems Discatcher to centact alternate personnel.
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CURRENT E!1ERGENCY PLAN I!1PLEMENTING PROCEDURES TABLE OF CONTENTS Volume 3B t
TITLE REV Offsite Support & Assistance 3 CR-1 2
OR-2 Release of Information to the Public Activation and Operation of the Technical Support Center 2 EF-1 Activation of the Operational Support Center 2 EF-2 EF-3 Activation and Operation of the Emergency Operations Facility 3 3
EF-4 Activation of the IE!1L Emergency Equipment, Instruments & Supplies 4 EF-5 EF-6 Operating Procedures For EARS 9845C Controlling Stations 1 1
EF-6S1 Transfer of EARAUT Control EF-7 Activation of the Nuclear Data Communications Systems 1 EARS Operating Procedures for TSC-CC HP-1000 Station 0 EF-8 RB-1 Personnel Dosimetry Not Issued Emergency Exposure Guides 0 RB-2 Stable Iodine Thyroid Blocking 0
.- RB-3
- RB-4 Access to & Establishment of Controlled Areas 0 Under Emergency 0
RB-5 Personnel Decontamination
- 1 RB-6 Area & Equipment Decontamination 3
Emergency On-Site Radiological Environmental Monitoring i RB-7 Emergency Off-Site Radiological Environmental Monitoring 2 RB-8 Calculation of Release Rate & Integrated Release 2 RB-9 0
RB-10 Protective Action Guidelines 3 RB-11 Emergency Off-Site Dose Calculations
- i. RB-12 Mid and High Range Plant Vent Radiation Monitors 1 Improved In-Plant Air Sampling for Radioiodines 0 RB-13 i
I 03/26/84 e
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EP RS-2 n,,, 20 unasc.iC 20 i a ad rise EMERGENCY EXPOSURE GUIDES 7p. et c..ange: @ PEi wANENT(p ens O izuacaear tv --i; cz.,r. tion :at.
Chemistry & Radiation Protection enginator _ M. R. CreaCh p,c.,,,n, e ,,,n,,n, proco d enang.: (coes ess anertne eners of engsw p,ocedure? hs h No)
(ca.s*
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'Page 2: Pr'ocedure Section 3.b.1) .
Change to read: Two (2) direct-reading. pencil dosimeters fo'r whole body exposure:
1 - 100 or 50R range 1-E-5R range.
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} GEt3 Pacific Gas and Electric Company NUMsER EP EF-5 m REVISION 4
( , , , CEPARTMENT OF NUCLEAR PLANT OPERATIONS CIABLO CANYCN POWEA PLANT UNIT NC($)
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[ ME EMERGENCY PRCCEDURE W EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES IMPORTAN TO APAAOVED: 77 - 3'S SAFETY Daae FLAhIMAhAug SCOPE This procedure provides an inventory of emergency ecuipment, instruments, and supplies (both portable and fixed) with inspection frequencies.
This procedure and changes there:o require PSRC review.
PORTABLE EMERGENCY EQUIPMENT
- 1. Radiological Emergency Kits The kits consist of three boxes each. Each box is clearly identified first by kit numbers, and second by box letter A, B or C. The ,
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contents of each emergency kit are given in Table 1. The contents of f each box of an individual emergency kit can be found in the notebook of each box. In addition, protective clothing and shoe covers are located at the Energy Information Center and the DCPP Security 3 Building for use in case personal effects are contaminated.
- a. Location -
Kit Nos.1, 2 and 3 - PG&E San Luis Obispo Service Center Mobile Environmental Monitoring Laboratory (MEML)
Garage Kit Nos. 4 and 5 - Diablo Canyon Power Plant Security Building, Exit. Foyer.
b' . Use The kits are available for use in case of a radiological emergency,by a designated monitoring team composed of at least two individuals trained in emergency radiological monitoring.
The team will be directed by the Control Room or TSC (onsite teams) or the EOF (offsite teams) as to which areas they will
- ' monitor. Other instructions are contained in the notebook of each kit.
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N OIABLO CANYON POWER Pt. ANT UNIT NO(S) . 1 AND 2 R ON DATE 10/28/83
. PAGE 2 0F 38 TITLE EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES
- c. Obtaining an Emergency Kit
. 1) Kits No.1, 2 and 3 can be obtained by the designated monitoring teams from the PG&E San Luis Obispo Service Center, in the Mobile Environmental Monitoring Laboratory (MEML) Garage. The personnel dispatched to the MEML garage will generally consist of Chemistry and Radiation Protection Technicians (C&RP), the MEML Operators from PGandE Department of Engineering Research, and San Luis Obispo County Environmental Health Department Personnel.
NOTE: If the MEML garage is locked, personnel should not open the door without a burglar alarm defeat key available. The front door is the only access that has a 45 second time delay to permit use of the defeat key (see Figure 1). The defeat key is available from the plant if the DER personnel are not available. The DER personnel will be called out as part of the call-out list in Emergency Procedure EP G-2.
When PGandE personnel have reached the MEML garage, establish telephone contact with the Radiological Emergency (RERH) at the Emergency Operations Facility (EOF). The phone number is listed in Attachment 1. If the MEML garage is locked and access cannot~be obtained from the DER personnel assigned to the van, then use the telephone in the division office building (see Figure 1). ~
NOTE: If the RERM cannot be reached at the EOF, then contact the Emergency Radiological Advisor (ERA) at the onsite Technical Support Center. The phone number is listed in Attachment 1.
If the RERM or the ERA require immediate deployrent of the MEML and/or the field monitoring teams, and access to the garage is still not available, inform the RERM/ ERA that access is not available and request the Cypher Pad Code that will open the door. Also, request the ERA to dispatch an individual from the plant to reset the alarm.
Call DCPP security to inform them the MEML garage will be ent2 red, and that the alarm will be actuated. The phone number is listed in Attachment 1.
[0))h When sound thelocally, alarm until is actuated reset. a loud electronic warbler will DC0118 2XII 99 e
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OlABLC CANYCN PCWEA AWT UNIT NO(S) 1 AND 2 h0N DATE 10/28/83 PAGE 3 0F 38 i -
TITLE EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES
- 2) Kits No. 4 and 5 can be obtained by the designated
+ monitoring teams from the site security building exit foyer (cabinet in northwest corner).
'd. Surveillance Frequency
- 1) Kit inventory wili be performed by the Chemistry and l Radiation Protection Department annually and after each use.
Form 69-9823-1, 69-9823-2, and 69-9823-3 are used to document the inventory.
- 2) Kit radiological instruments will be replaced or recalibrated quarterly in accordance with the norral practice established by the I&C Maintenance Department.
- 3) Dosimeter charger and flashlight batteries will be replaced quarterly.
- 2. Emergency Evacuation Kits
. Each kit consists of a box, clearly identified. The contents of each emergency evacuation kit are given in Table 2. The contents of each box can be found on the inside cover of the box. In addition, two cases of protective clothing and two cases of shot covers are stored near the evacuation kits for use in case personal effects are contaminated. Additional protective clothing is also available at the Energy Information Center.
- a. Location The two emergency ev'acuation kits are located in the Exit Foyer of the Plant Security Building.
- b. Use The kits are available for use in the event site evacuation is ordered by the Site Emergency Coordinator. The Evacuation Coordinator would then have the kits and clothing issued to the evacuation team leaders.
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OLASLO OANYON PCWER Pt ANT UNIT NCIS) 1 AND 2 REh0N DATE 10/23/33 PAGE 4 0F 33 Titts EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES ~
- c. Obtaining an Emergency Evacuation Kit The emergency evacuation kits can be obtained by going to the Exit Foyer. located at the Plant Security Building, and removing them from the storage cabinet in the northwest corner of the r foyer.
- d. Surveillance Frequency
- 1) Kit inventory will be performed by the Chemistry and Radiation Protection Department annually and after each use.
Form 69-9369 is used to document the inventory.
- 2) Survey meters and dose rate meters will be replaced or recalibrated quarterly in accordance with the normal practice established by the I&C Maintenance Department.
- 3) Desimeter charger, bullhorn, calculator, and flashlight batteries will be replaced quarterly.
- 3. First Aid Supplies
- a. Location The location of first aid supplies are listed in Table'3.
(([];: Not all first aid supplies are presently deployed at their locations. However, they will be in place by power ascension above St.
- b. Surveillance .
First aid supplies are inventoried monthly by the Support Services Organization.
- 4. Hospital Kits Each kit consists of a bcx, clearly identified. The contents of each l hospital kit are given on Table 4.
- a. Location The two hospital kits are located in the Exit Foyer of the Plant Security Building.
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OiAsLO CANYCN AOWE A p; ANT UNIT NO(S) 1 AND 2 REVISION i~~ l DATE 10/23/S3 I PAGE 5 0F 35 i
( tit;g EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES l
- b. Use The kits are available for use in the event an injury victim, involving radioactive contamination or overdose, is sent to an offsite location for treatment or decontamination. l
- c. Obtaining a Hospital Kit The kits can be obtained by going to the Exit Foyer located at the Plant Security Building, and removing them from the storage cabinet in the northwest corner of the foyer.
- d. Surveillance Frequency
- 1) Kit inventory will be perfonned by the Chemistry and Radiation Protection Department annually and after each use. l
- 2) Survey meters and dose rate meters will be replaced or recalibrated quarterly in accordance with the normal practice established by the I&C Maintenance Department.
I
- 3) Dosimeter charger batteries will be replaced quarterly.
S. Respirators (Self-Contained Breath'ing Apparatus or SCBA)
- a. Location
- 1) Eight SCBA units are maintained in the control room for shift fire brigade members.
- 2) Sixteen SCBA units are located in the fire brigade locker on the stairway landing above the 85' elevation between the turbine building and auxiliary building.
- 3) ,Five SCBA units and five 30-minute spare tanks are located at the Technical Support Center.
- 4) Two SCBA units are maintained on the east side of intake structure in two yellow cabinets.
- 5) Thirty SCBA units are maintained at or near Access Control
, for normal radiological use. Thirty 30-minute spare tanks are also maintained at this location.
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NUMBER EP EF-5 DIABLO CANYON PCwER PLANT UNIT NC(S) 1 AND 2 REVISION 4 DATE 10/28/33 PAGE 6 0F 23 Titts. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES
- 6) Seven SCSA units are stored in the Auxiliary Building stairwell on the west sice at the 90' elevation.
- 7) One SCSA unit is maintained at the Unit 2 Auxiliary Operator's Office.
- 8) Forty SCBA units and sixty-five 30-minute spare tanks will be stored in the turbine building.
- b. Surveillance
- 1) SCSA units will be inspected by the Chemistry and Radiaticn l Portection Department monthly.
, 2) The forty SCBA's stored in the turbine building will be l inspected prior to use.
- 3) All SCSA units will be inventoried semiannually.
- 6. Portable Survey and Dose Rate Instruments .
A variety of portable count rate and dose rate instruments are available at the plant for routine radiological monitoring, and also
,, for use in emergencies, if necessary. The general types and approximate quantities of this ecuipment are summarized in Table 5 and
- 6. It should be noted that this list is 19 tended only to be illustrative of the plant's capabilities; precise quantities and models of specific equipment may vary from time to time as conditions I change, different products appear on the market, etc.
l The equipment listed in the table is normally located at access control when not in use.
- 7. Post-Accident Sample Kit The kit consists of two storage lockers, clearly identified. The contents of the lockers is gi,ven on Table 7.
- a. Locations .
l 1) 85' locker located in the turbine building elevator vestibule.
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- 2) 115' locker located across the passageway from the IPLSS panel.
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0:A81.0 CANYON PCWEA PLANT UNIT NC(S) 1 AND 2 DATE 10/28/83 PAGE 7 0F 23
(. TITLE EMERGENCY EOUIPMENT, INSTRL:MENTS & SUPPLIES 1
- b. Use The lockers are available for use in the event a high activity sample is anticipated from the post-accident sampling system.
- c. Surveillance Frequency Kit inventory will be performed by the Chemistry and Raciation Protection Department annually and after each use.
- 8. Protective Clothing Protective clothing for nomal and emergency use is located at access control and the laundry room. Other locations where clean protective clothing may be found are:
- a. Plant warehouse
- b. PGandE Energy Infomation Center l
- c. Operational Support Center (OSC)/DCPP Security Building Exit Foyer
- d. Technical Support Center (TSC)"
- 9. Mobile Environmental Monitoring Laboratory (MEML)
The following equipment is available in the MEML for use in routine and emergency environmental monitoring. Surveillance is performed in normal use.
- a. Na! Detector
- b. ige Detector
- c. HP 9845C Computer
- d. Multichannel Analyzer ,
- e. High-Volume Air Sampler
- f. Pressurized Ion Chamber (3) 9 High-Pressure Gas Sampler
- h. TLD Reader
(
- i. Instrument-Grade Electric Generators ,
DC0118 7xI
ciAsto cANYCN ACwEA PLANT UNIT NC(s) 1 AND 2 NUMBER IP EF-5 REVISICN 4 DATE 10/25/E3 PAGE 8 0F 38 ;
ritts EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES
- 10. Plant Vehicles Plant vehicles s' hall be inventoried by the Personnel and General Services Department. The plant vehicle list shall be updated annually. The plant vehicle list can be found in Table 8.
- 11. Radio Pagers Radio pagers are assigned to selected positions of the emergency organization, as a convenience, for use when the on-call person for the position is not available at their normal telephone numcers.
Normal pager assignments are given in Table 8~ a. A group page and .
test message is given on the first of each month at about 8:00 p.m. to provide a check on pager operation.
FIXED EMERGENCY EQUIPMENT
- 1. Early Warning System Testing and maintenance for the EWS Stren Units, listed in Table 9, shall be performed by Los Padres District personnel according to the following schedule: .
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- a. Monthly: A test cancel signa'l will be initiated, counter readings will be taken and a visual inspection made,
- b. Quarterly: The inside of the compressor and the control and j
receiver cabinets will be inspected, and the sirens will be growl tested.
- c. Annually: A complete inspection of all major components, as well as lubrication and cleaning of the unit will be done.
EMERGENCY FACILITY EOUIPMENT
- 1. Control Room Equipment available in the Control Room for radiological emergency assesment and comunication and the surveillance performed on this equipment is listed in Table 10,
- 2. TechnicalSupportCenter(TSC)
Equipment available in the TSC for emergency assessment, comunication and other emergency functions of the facility and the surveillance l
performed on this equipment is listed in Table 11.
DC0118 SXII
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- AaLO CANYCN PCWEA Pt. ANT UNIT NC(S) 1 AND 2 f[
OATE CN 10/2S/53 PAGE 9 0F 38
- f. TITLE. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES
- 3. Operational and Operations Support Centers (OSC) l Equipment available in the OSC for emergency functions and communications and the surveillance performed on this equipment is listed in Table 12.
- 4. Emergency Operations Facility (EOF)
Equipment available in the EOF for emergency assessment, communication and other emergency functions of the facility and the surveillance performed on this equipment is listed in Table 13.
- 5. Energency Procedure Phone Numbers Telephone numbers in the emergency procedures are v'erifted quarterly by the emergency planning staff, using Form 69-9043.
FIGURES
- 1. MEML Garage Layout and Access TABLES
- 1. Contents of Radiological Emergency K1's t ,
- 2. Contents of Evacuation Kits
- 3. Locations of First Aid Supplies 4 Contents of Hospital Kits
- 5. Portable Count Rate Meters
- 6. Portable 00se Rate Instruments
- 7. Contents of Post-Accident Sample Kit
- 8. Plant Vehicle List 8a. Emergency Organization Radio Pagers
- 10. Control Room Emergency Plan Equipment t
e DC0118 9XII 49 9 n, .. - , -- . .- - -- - - - - - - . -
- TITLE. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLES (continued)
- 11. Technical Support Center Emergency Plan Equipment
- 12. ' Operational and Operations Support Center Emergency Plan Equipment l
- 13. Emergency Operations Facility Emergency Plan Equipment ATTACHMENTS
- 1. Emergency Facility Phene Numbers
- 2. 69-9823-1 Emergency Kit Inventory Checklist Box A
- 3. 69-9823-2 Emergency Kit Inventory Checklist Box B 4 69-9823-3 Emergincy , Kit Inventory Checklist Box C
- 5. 69-9369 Evacuation Kit Inventory Checklist
- 6. 69-10598 Hospital Kit Inventory Checklist
- 7. 69-10507 Post-LOCA Sampling Kit Inventory Checklist
- 8. 69-9043 Emergency Plan Phone Number Verification Checklist
- 9. 69-10766 Control Room Checklist
- 10. 69-10767 Technical Support Center Checklist
- 11. 69-10768 Technical Support Center Equipment Quantity Checklist
- 12. 69-10769 Operational Support Center and Operations Support Center Checklist
- 13. 69-10770 Emergency Operations Facility Equipment Function Checklist 14 69-10771 Emergency Operations Facility Inventory Checklist
- 15. 69-10582 Emergency Facility Forms File List DC0118 10XII l
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ciAet CANyos PowEA H. ANT UNIT NC(S) 1 AND 2 REVISION i~.
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DIASLO CANYON PCWEA PLANT UNIT NC(S) 1 AND 2 S ON DATE 10/28/83 PAGE 12 0F 38 '
Tirts EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 1
- CONTENTS OF RADIOLOGICAL EMERGENCY KITS QUANTITY g KIT e IHM 1 2 3 4 5
- 1. Instructions, Procedures and Supplies
- a. Instruction binder 1 1 1 1 1
- b. Table of contents 1 1 1 1 1
- c. Sanford Marking Pens 2 2 2 2 2
. d. Red Marking Pens 2 2 2 2 2
- e. Bla:k Marking Pens 2 2 2 2 2
- f. Ball Point Pens 2 2 2 2 2
- g. San Luis Obispo County .
Map 1 1 1 1 1
- h. Equipment Location Dwgs. l (sets) Unit 1 1 1 1 1 1
- 1. Emergency Environmental Monitoring Field Data Sheet (Fam 18-9259) 100 . 100 100 100 100
- j. " Emergency Onsite Radiological Environ-mental Monitoring Program" EP RS-7 1 1 1 1 1
- k. " Emergency Offsite Radiological Environ-mental Monitoring Program" EP RB-8 1 1 1 1 1
- 1. " Emergency Equipment, Instruments and Supplies" 1 1 1 1 1 EP EF-5
- m. Corporation Key (3A90909) 1 1 1 1 1
- n. Infonnation Center Key 0 1 0- 1 1
- o. Pocket Calculator 1 1 1 1 1
- p. High Security Pin Tumbler Key (for PIC) 1 1 1 1 1
Fom #18-9395 1 1 1 1 1
- r. Computation paper (packet) l' 1 1 1 1 l nrollA 177f .
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2863 CANYCN PCWE A P'JNT UNIT NC(S) 1 AND 2 'h']j ON DATE 10/28/83 PAGE 13 0F 38
( T;TLs EMERGENCY ECUIPMENT, !NSTRUMENTS & SUPPLIES TABLE 1 (Continueo)
. CONTENTS OF RADIOLOGICAL EMERGENCY KITS OUANTITY KIT e j
ITEM 1 2 3 4 5
- 2. Monitoring Equipment *
- a. Do'se Rate Meter (Rad Ow1/ 0 1 0 0 0 R0-2)
- b. Dose Rate Meter (HPI-1010) 1 1 1 1 1
- c. Survey Meter (Eber.
E-140 or E-140/N) 1 1 1 1 1
- d. Standard G-M Probe (Eber. HP-240/HP-270) 1 } 1 1 1
- e. Pancake G-M Probe (Eber. HP-210 or HP-260) 1 1 1 1 1
- f. PocketDosimeters(0-5R) 2 2 2 2 2
- g. Pocket 00simeters 1
(0-200mR) 2 2 2 2
- 2
- h. Dosimeter Charger 1 , 1 1 1 1
- 3. Air Sampling Equipment
- a. 12 V Air Sampler and Sample Head (w/o Battery, Radeco H-809C) 1 1 1 0 0
- b. 12 V Air Sampler and Sample Head (w/ Battery, Radeco H-8098) 0 0 0 1 1
- c. 120 V AC Air Sampler and Sample Head (RadecoHD-288) 0 1 1 0 0
- d. Air Sample Particulate Filters (pkg of 10) 10 10 10 10 10
- e. Iodine Filter Cartridges (pkg. of 10) 2 pkg - TEDA, 3 3 3 3 3 1 pkg - AgZ
- f. . Smear Packets (5 smear /
Packet) 50 50 50 50 50
- g. Pacer Envelopes for AIR Particulate Samples 25 25 25 25 25 l'
- Equipment of equivalent function may be substituted. .
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NUMSER EP EF-5 DiA8LQ CANYCN PCWEA PLANT UNIT NO(S) 1 AND 2 REVISION 4 CATE 10/25/S3 PAGE 14 0F 38 TITLs EMERGENCY EQUIPMENT,' INSTRUMENTS & SUPPLIES TABLE 1 (Continuec)
CONTENTS OF RADICLOGICAL EMERGENCY KITS OUANTITY KIT a ITEM 1 2 3 4 5
- h. Plastic Envelopes for lodine Cartridges (Ziplac baggies) 30 30 30 30 30 l
- 1. Forceps 1 1 1 1 1
- j. Compressed Air Cylinder, 2 2 2 2 2 1700 psi
- k. Sample Head w/ Adapter to fit Air Cylinder 1 1 1 1 1
- 1. Air Cylinder Regulator 1 1 1 1 1 4 Protective clothing /
Decontamination ,
- a. Protective Clothing Sets (coveralls, hood, booties, rubbers, gloves) 2 2 2 2 2
- b. Full Face Mask 2 2 2 2 2
- c. Type GMR-S or GMH-!
(or equivalent)
Ultra Filters for Face Masks 2 2 2 2 2
- d. Skin Decontamination Soap (pt. bottle) 1 1 1 1 1
- e. Hand Brush 1 1 1 1 1
- f. Floor Scrub Brush 0 1 0 1 1
- g. Paper Towels (pkg.) 0 1 0 1 1
- h. Smear Pads 8"x8" cotton l (pkgof10) 1 3 1 1 11
- 1. PlasticBags(38"x65") 3 3 3 3 3
- j. Bucket (10 quart) 0 1 0 1 1
- k. Decenticination Agent.
(gallonbottles) 1 1 1 1 1
- 5. Signs / Barriers
'a. Radiation Signs (w/3 inserts) 2 4 2 4 4
- b. Radiation Barricade Tape '
(100' rolls) 2 2 2 2 2 9
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DIA81.C OANYCN POWE A PLANT UNIT NCIS) 1 AND 2 ON DATE 10/28/S3 PAGE 15 0F 38
( Titts EMERGENCY ECUIPMENT, INSTRUMENTS & SUPPLIES TABLE 1 (Continuec)
CONTENTS OF RA0!0 LOGICAL EMERGENCY KITS CUANTITY l KIT r 8 ITEM 1 2 3 4 5
- 6. Sampling Eouipment
- a. Sample Bottles (1 liter) 2 6 2 4 4 I
- b. Plastic Bags Approx. 15 15 15 15 15 I (18"x24")
. c. Trowel 1 1 1 1 1
- 7. Miscellaneous Equipment ,
- a. First Aid Kit (size 10) 1 1 1 1 1
- b. Screwdriver 1 1 1 1 1
- c. Crescent Wrench (8") 1 1 1 1 1
- d. Scissors 1 1 1 1 1
- e. Stopwatch 1 1 1 1 1 i f. Roll of Dimes 1 1 1 1 1
- g. Masking Tape (2" wide rolls) 2 2 2 2 2
- h. Flashlights w/ Batteries 1 2 1 2 2
- 1. Extra Batteries 2 4 2 4 4
- j. Battery-Powered Lantern w/6 V Battery 1 1 1 1 1 l
- k. Bolt Cutter 0 0 0 1 1
- 1. " Kwik-kold" Packs 4 4 4 4 4
- m. Grass Shears 1 1 1 1 1
- n. KI Tablets (bettle) 1 1 1 1 1
- c. Gummed Labels (sheet) 5 5 5 5 5 I
DC0118 15XI .
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DIABLO OANYON POWEA PLANT UNIT NO(S) 1 AND 2 5 ON CATE 10/28/S3 PAGE 16 0F 38 TITLE. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES -
TABLE 2 CONTENTS OF EVACUATION KITS QUANTITY ITEM PER KIT .
- 1. Eberline E-140/N Survey Meter with HP-240/HP-210 Standard G-M Probe 1
- 2. Rad Owl Dose Rate Meter 1
- 3. Self-Reading Desimeter Pencils, 0-200 mR Range 4 4 Dosimeter Charger w/ extra battery 1
- 5. Barricade Tape,100-Foot Rolls 2
- 6. Packages of 2-Inch Filters (10 filters / package) 50
- 7. Bullhorn w/ extra battery ,
1
- 8. PlasticBags(14'X24") 3
- 9. Ballpoint Pens ,
4
- 10. Flashlight w/two extra batteries 1
- 11. Pocket Calculator w/ extra battery 1
- 12. Corporation Key (3A90909) 1
- 13. Inforr.ation Center Emergency Room Key 1
- 14. Instruction Binder:
- a. Emergency Procedure G-5, " Evacuation of I
Nonessential Site Personnel" i
- b. Form 69-9310. " Post-Evacuation Vehicle Monitoring Data" 50
- c. , Form 69-9311. " Evacuee Monitoring Data" 100
- d. Form 69-9369, " Evacuation Kit Inventory Checklist" 5-10
- e. Emergency Procedure G-4, " Personnel Accountability and l Assemoly" 1 1
- 15. Information Center Decontamination Shower Key (A53) 1 DC0118 16X!
ee O
DiAsto cANycN ACwEA DLANT UNIT NC(s) 1 AND 2 R ON DATE 10/25/33 PAGE 17 0F 35 k TITLE EMERGENCY ECUIPMENT, INSTRUMENTS & SUPPLIES TABLE 3 LOCATIONS OF FIRST AID SUPPLIES LOCATION EOUIPMENT
- 1. Administration Building First Aid Station
- 2. Security Building First Aid Station
- 3. Training Building First Aid Station
- 4. Intake Structure First Aid Kit. Basket Stretcher
- 5. Cold Machine Shop First Aid Kit
- 6. Access Control (First Aid Room) First Aid Locker, Stretcher, Gurney, Scoop t Stretcher, Backboard, 4
Oxygen, Splints 3 7. Turbine Building 104' Elevator Landir.g First Aid Station 119' Elevator Landing First Aid Station 140' Elevator Landing First Aid Station
- 8. Control Room First Aid Kit, Burn Kit
- 9. Auxiliary Building 75' Elevator Landing First Aid Station 100' Elevator Landing First Aid Station 115' Elevator Landing First Aid Station
- 10. Hot Machine Shop First Aid Station
- 11. Containment Personnel Hatch . First Aid Kit, Basket Stretcher I
S
, DC0118 17XI se e
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e l
NUMBER EP EF-5 CIA 8LO CANYCN PCWEA PLANT UNIT NO(S) 1 AND 2 REVISION 4 DATE 10/28/83 PAGE 18 0F 38 Titts EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES -
TABLE 4 CONTENTS OF HOSPITAL KITS Each of two hospital kits shall contain the following minimum items:
ITEMS OUANTITY Full face respirators w/ Type H '
or ecuivalent filters 2 each Disposable coveralls 4 each Hood 4 each Disposable shoe covers 4 pair l Surgical latex gloves 1 box Rubbers 4 pair Masking tape, 2" width 2 rolls Duct tape, 2" width 2 rolls
" Radioactive Material Area" sign 5 each
" Surface Contamination Area" sign 5 each '
"High Radiation Area" sign 2 each
" Radiation Area" sign 5 each Barricade tapt,100 yd. roll 2 each Ty raps Minimum 30
" Radioactive Material" labels 4"x6" -
10 each
" Radioactive Material" labels 1"x3" 1 roll E140N/HP-210T 1 each HP-260 1 each Spare detector i each' 1 Allen wrench 1/16" . 1 each 1 HPI-1010 or equivalent i each 0-200 mA pencil dosimeters 2 each 0-SR pencil dosimeters 2 each dosimeter charger 1 each 2" smears w/ packets (5 smears / packet) 50 each 2" air sample filters w/ envelopes 50 each Plastic envelopes.3"x5" 30 each Gummed labels 40 each Plastic bags 38"x65" 6 each Grease pencil 2 each Ballpoint / felt tips pens 3 each Waterproof pen 2 each Personnel Decon Record Sheet (69-9392) 6 each Bendix BOX-60 Air Sampler 1 each
, 38mm air filters / holders for BDX-60 1 box i e
DC0118 18XI ,
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1 AND 2 OuSLC CANYON ACWEA PLANT UNIT NCIS) ff CN DATE 10/28/83 PAGE 19 0F 3s I TITUE EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES
~
TABLE 4 (Cont'd)
CONTENTS OF HOSPITAL KITS (Cont'd)
ITEMS QUANTITY
~
Contaminatien Survey Sheet (69-9315) 6 each Radiation Survey Sheet (69-9316) 6 each Fdeceps _
1 each Smear pads 8" x 8" cotton (pkg of 10) 2 pk9 Medical referral form 62-6015 3 each Light duty letter 3 each Plastic bags 18"x24" 12 each 4
0 e
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DC0118 - 19XI
NUMBER EP EF-5 DIA8LO CANYCN POWEER AANT UNIT NO(Si 1 AND 2 REVISION 4 DATE 10/28/83 PAGE 20 CF 38 TiTLs EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 5
. PORTABLE COUNT RATE METERS Instrument Detector Radiation Typical Prima ry (Model No.) Tyoe Measured Ranne Use Beta-Garma Survey 0-700, 0-7000 General Meter (E-la0), with 0-70,000 CPM contamination the following surveys detectors;
- a)~ Hand probe (HP-260) GM Beta, Gamma b)Handprobe,and window, (HP-230A) GM Beta, Gamma c) Hand probe (HP-240) GM Set'a , Gamma d) Shielded hand probe, (HP-210) GM Beta, Gamma Count rate meter 0-500,0-5K, Personnel (RM-15) for use with
- 0-50K, 0-500K contamination GM' probes listed . GPM surveys above, and:
a) alpha scintil- Alpha
~
ins (Ag),
lation probe 59 cm (AC-38 7) sensitive area b) gamma scintil- Na!(TI), Gamma lation probe 2" x 2" (SPA-3)
Count rate neter 0-500, 0-5K, General (PRM-6) for use with 0-50K, 0-500K contamination GM probes listed CPM surveys above AC-38-7 and See See SPA-3 probes above above ,
l .
1 l
i DC0118 20XI .
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OiAa C CANYCN PCwEA #LANT uni? NC(S) 1 AND 2 marg v[rfj;c3
'p rr '
l OATE 10/25/83 PAGE 21 0F 35
( mLE EMEPGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 6 PORTABLE DOSE RATE INSTRUMENTS Instrument Detector Radiation Primary (Medel No.) Tyoe Measured Rance Use Rad Owl (RO-1) Ion Chamber Beta, Gamma Dose rate: Beta and Gama 1.7 mg/cm' 0-5, 0-50, dose rate beta window, 0-500 mR/hr air fill gas 0-5, 0-50 0-500 R/hr Integrate:.
0-5, 0-50, 0-500 mR Radgun Pressurized Beta,Gama 0.01-10 mR/hr Gama (AGB-10K-SR) argon fill 0.01-10 R/hr dose rate gas 10-10,000 R/hr
- tonchamger.
20 mg/cm i beta window, '
(10 atm)
HP! Multiplying Gama Dose rate: Low level Multiplying ion chamber Neutron 0-0.1, 0-1 gama ton Chamber tissue 0-10, 0-100 dose rate (1010) equivalent 0-1000 mrads/
walls and hr fill gas Integrate:*
0-0.01, 0-0.1, 0-1 mrad Portable REM BF Neutron, 0-5, 0-50, Neutron 3
Counter
- themal to 0-500,0-5000 dose rate (PNR-4) 10 MeV mrem /hr -
Teletector Twin G-M Beta,Gama 0-2 mR/hr, Beta, Gama 6112 tubes 30 mg/ 0-50 mR/hr dose rate cm' beta 0-2 R/hr window 0-50 R/hr 0-1000 R/hr R0-2 ton chambgr Beta.Garlea Dose rate: Beta, Gama 3.5 mg/cm 0-5, 0-50, dose rate beta window. 0-500 mR/hr ai- fill gas 0-5 R/hr .
DC0118 21XI ,
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NUMSER EP EF 5 1 ANg g OiAaLo CANYON PCWEA PULNT UNIT NCis) REVIS:0N 4 CATE 10/28/83 PAGE 22 0F 38 TITLE EMER3ENCYEhUIPMENT, INSTRUMENTS & SUPPLIES TABLE 7 CONTENTS OF POST-ACCIDENT SAMPLE KIT ITEM . ,
OUANTITY
- 1. Instruction Binder Sanford Marking Pens 2 a.
Red Marking Pens 2 b.
Black Marking Pens 2 c.
Ball Point Pens 2 d.
- e. EP EF-5
" Emergency Eouipment, Instruments and Supplies" I
- f. CAP G-1 Access to IPLSS Area, Post Accident Sample Precaration Handling, and Analysis I
- h. Emergency Phone Directory 1
- 1. Achesive Backed Sample Labels 20
- 2. Monitoring Equipment 1
- a. Teletector (Eber11ne6112)
- b. Pocket Dosineters (0-5R) 2
- c. PocketDesimeters(0-200mR) 2
- d. Cosimeter Charger 1
- e. Finger Rings 12
- f. Oose Rate Meter (HPI-1010 or R0-2) . 1
- g. Survey Meter (Eber. E-140/N) I
- h. Pancake G-M Probe (Eber. HP-210 or HP-260) 1
- 1. Bendix 80X-60 air sampler 1
- 3. Air Sampling Equipment
- a. Tongs 1
- b. Forceps I
- c. Silver Zeolite (AQZ) Cartridges . 12
- d. 5 cc Shielded Syringes 5
- e. Glass vials (14 cc) w/ rubber stoppers 12
- f. Air Sample filter / cartridge holder assembly 2 i
l OC0118 22XI
Oiast: cANYCN POWEA p' ANT UNIT NCr$) 1 AND 2
[fff0N DATE 10/23/33 PAGE 23 CF 3S I. title EMERGENCY EQUIPMENT INSTRUMENTS & SUPPLIES TABLE 7 (Continued)
. CONTENTS OF POST-ACCIDENT SAMPLE KIT ITEM QUANTITY
- 3. Air Sampling Equipment (Continued)
- g. Surgical Tubing (1/4") 5'
- h. Duct tape 3
- 1. Air Sample Particulate Filters (pkg of 10) 3
- j. Compressed Air Cylinders 2
- k. Air Cylinder Regulator 1
- 1. Plastic Bags (15" x 30") 20
- m. 8-0 Hypodermic needles (LUER-LOX pkg of 12) 4 .
- n. " Radioactive Material" Labels 1 roll
- o. Licuid Sample Vessel adapter tubing (Plastic tubing w/ male adapters) . 2
- p. 38mm Air Filters for Bendix 80X-60 air sampler 1 box
- 4. Miscellaneous Equipment
( a. Protective Clothing Sets (coveralls, hood, booties, shoe covers, gloves) 2
- b. Stopwatch I
- c. Calculator 1
- d. Crescent Wrench (8") -
1
- e. Screwdriver 1
- f. Allen wrench (3/32") 1
- g. Masking tape (2" wide rolls) I
- h. Flashlight w/ batteries 1
- 1. Extra Batteries 2
- j. Allen wrench (5/64") I
- k. Key to East gates outside elevation 115' 1 DC0118 23XI .
i .
1.
h ciAsto cANYCN PCWEA PLANT UNIT NC($) 1 AND 2 R ON DATE 10/28/83 PAGE 24 0F 22 m LE EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 8 DIABLO CANYON POWER PLANT PLAhi VEHICLE LI5T Primary position holders of certain emergency response positions are provided with VHF radio-equipped company vehicles. Because these persons are essentially on-call at all times, use of these vehicles is warranted in off hours to ensure rapid communication and response. These personnel are icentified in EP G-2, " Establishment of the On-Site Emergency Organization."
My
- CLASS DESCRIPTION MAKE LICENSE ASSIGNED TO 8-6145 P-1 Sedan 84 FORD 1HQN330 Plant Manager 8-0402 P-1 Sedan 83 FORD 1FTZ284 Department Henc 8-0394 P-1 Sedan 83 FORD 1FTZ282 Department Head 8-0388 P-1 Sedan 83 FORD 1FTYS38 Department Head .
8-0408 P-1 Sedan 83 FORD 1FTZ285 Department Head 8-0401 P-1 Sedan 83 FORD 1FTZ283 Department Head 8-0389 P-1 Sedan 83 FORD 1FTY983 Department Head 8-7820 P-1 Sedan 84 FORD 1HQN227 Office Supervisor 8-7821 P-1 Sedan 84 FORD 1HQN226 Office Supervisor 8-6470 P-1 Sedan 78 PLYMOUTH 238 UKX Office Supervisor 8-5014 P-1 Stationwagon 78 PLYMOUTH 745 UUA Office Supervisor 8-AS70 C-2 Van 79 000GE 137 XLR Office Supervisor j
8-9064 P-1 Sedan 79 PLYMOUTH 292 WEJ Security Supervisor 8-A713 C-4 Pick 0p 78 000GE 1M85862 Security 8-6258 Bronco 84 FORD Security DC0118 24XI e
49 g
NUMBER EP EF-5 ciASLO CANYON PCwEA PLANT UNIT NC($) 1 AND 2 R VISION 4 DATE 10/28/53 PAGE 26 CF 38 7ti d EMERGENCY E;UIPMENT, INSTRUMENTS & SUPPLIES TABLE 8.a
. Emergency Organization Radio Pagers Pager Grou; Page Emergency Position Encode Numeer Encoce Numcer j l
Site Emergency Cocrainator Erergency Operations Coorcinator l (Plant Superintencent) l l
j E.wrgency Evaluation & Recovery Coord. i
' ( Asst. Plt. Mgr./ Tech. Srves. )
Emergency RadiologicI
- Advisor
]
Emergency Liaison Cocrdinator .
i Acvisor to ne County E:nergency Organization
( Asst. Pit. Mgr./Su;; ort Srves.) l' j
- Emergency Maintenance Coordinator Site Chem.istry & Radiation Protection Coorcinator Emergency Liaison Assistant #1 f
I Emergency Liaison Assistant #2 I
l Ca:a Process 0r No. 1 l
l l Ca:a Prccessor No. 2 Instr *,. ment Maintenance C0cedinator l
i Electrical Maintenance Coordinator :
becnanical Maintenance Coordinator i
Fire Marshal EARS C;erator - ISC Mcoil Envir:enental Monitoring Lab Operator Interim Puolic Infor .ation Recovery Manager Sue Brewn Missie Hoosen CCC118 26XII og
- ww w w m '# ~=wwr
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ciastO CANYON POWEA NANT UNIT NO(S) 1 AND 2 33 4 OATE 10/28/83 PAGE 25 0F 38 I. riTts EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 8
. DIASLO CANYON POWER PLANT PLAhi VENICLE LIST (Concinued)
MV 8 CLASS DESCRIPTION MAKE LICENSE ASSIGNED TO 8-2480 Pickup 82 FORD 2C85704 Securi ty
~
8-7825 Pickup 84 FORD 2G74627 Mechanical . Maintenance l 8-4229 C-2 Pickup 78 FORD 1K74799 Mechanical Maintenance l
8-0003 C-2 Pickup 73 000GE 1739700 Mechanical Maintenance 8-2903 C-2 Sccm Truck 72 FORD 69676L Nechanical waintenance 8-7331 C-2 Pickup FORD 1G49905 Mechanical Maintenance 8-A258 C-4 Pickup 79 CHEVROLET 1N20205 Operations ,
8-3800 Pickup 81 FORD 1Y53259 Operatier.s l 8-0435 Pickup 80 CHEVROLET' IV61228 Chem & Rad 8-3597 Pickup 80 CHEVROLET 1580741 Chem & Rad 8-3882 Pickup 79 CHEVROLET 1970245 Chem & Rae (on loan to Security) 9 l . .
8 .
OC0118 25XI og O
I DIABLO CANYCN PCWEA PLANT UNIT NO(S) 1 AND 2
"[3h R 0N l DATE 10/23/83 PAGE 27 0F 33 ;
( TITLE EMERGENCY ECUIPPENT, INSTRUMENTS &' SUPPLIES TABLE 9
. EWS SIREN LOCATIONS SIREN NO. LOCATION 1 North Morro Bay . near the intersection of Sequoia and Alder.
lA Near intersection of So. Ocean and Chaney Ave, off Highway 1.
18 Near the Cayucos Cemetary on Highway 1.
1C Cayucos near the in'tersection of 4th &
Park 2 On PG&5 property at the Morro Bay Power Plant, Near Highway 1 2A On PG4E property at the Morro. Bay Power
( Plant, Near the Embarcadero 3 In Morro Bay, on Morro Avenue north of Olive.
- 3A In Morro Bay, near the intersection of Ridgeway street and Fairview Avenue.
1 6 In Baywood Park near the intersection of Santa Ysabel and 2nd St.
4 6A In Baywood Park near the intersection of El Morro Avenue and 8th Street.
7 .!n Los Osos on Pecho Valley' Read several blocks west of Pine Avenue.
8A Montana de Oro Park near the Ranger Station.
88 Montana de Oro Park near the Ranger's residence.
8C On the Field's property south of the bgate. _.
i I
s.
l DC0118 27XI
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4 DiAsto cANycN powEA PLANT UNIT NO(S) 1 AND 2 5 ON DATE 10/28/83 PAGE 28 0F 32 TITts. E.MERGENCY CQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 9(Continued)
, SIREN NO. LOCATION 80 On the Field's property near the Ffeld's residence.
9 Near Highway 1 on PG&E's Baywood' substation yard.
10 Near Highway I west of San Luisito Creek Road.
12 On Highway 1 just north of Cuesta College.
13 On Highway 1 northwest of animal shelter.
14 On Highway 1 about 1/2 mile west of the California Division of Forestry.
15 In San Luis Obispo across the street frem '
City Fire Station on No. Chorro Street.
ISA On Foothill Blvd. just outside San Luis Obispo, 3/10/mi ' southwest of Rosita St.
16 In San Luis Obispo near Grand Avenue and Slack Street.
17 In San Luis Obispo parking lot next to the fire station on Garden Street.
18 In San Luis Obispo on Augusta St. near Sinsheimer School.
19A On Clark Valley Rd. off Los Osos Valley Rd.
near PGandE 500kV right-of-way.
. 19C ,
Los Osos - near the end of Valley -
View Place.
190 In Los Osos - on Nipomo Avenue East of l
' South Bay Boulevard between Willow Dr and Andre Ave.
19E In Los Osos near the fire station on Calle Cardonay. ,
a m
OC0118 28XI e9 e
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- hABLO CANYCN PCWEA PLANT UNIT NC(S) 1 AND 2 NU;Mgg,,jjjg3 [
OATE 10/25/83 FAGE 29 0F 32
' TiTug EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES
(
TABLE 9 (Continued)
. SIREN NO. LOCATION 20 On Los Osos Valley Road near the 500 kV right of way west of Turri Road.
21 On Los Osos Valley Road east of Turri Rcad.
22 On Los Osos Valley Road about 2 miles west of Foothill Blvd.
23 Near the intersection of O'Connor Way and Foothill Blvd.
23A' On O'Connor Way about 2 miles west of Foothill Blvd.
24 On Perfumo Canyon Road about 2 miles from Los Osos Valley Rd.
b 24A At end of private dirt road about 2000' south
- from point that Perfumo Canyon Rd pavement ends.
248 Near the end of Sycamore Canyon Road off Clark Valley Rd.
25 At the top of Perfumo Canyon Road.
25A On Andres property along Coon Creek Road about 1-3/4 miles west of upper end of See Canyon Road.
26 Near intersection of See Canyon Road and Davis Canyon Road about 3.6 miles off of San Luis Bay Drive.
26A On See Canyon Rd about 4.6 miles off of San Luis Bay Drive.
27 On See Canyon Rd about 1.2 miles off of San Luis Bay Drive.
}
27A.-
~
On See Canyon Road about 2.4 miles off of San Luis Bay Drive. -
27B On See Canyon Road about 3 miles off of San Luis Bay Drive.
( .
DC0118 29XI -
MO .
NUMBER EP EF-5 DiAaLO CANYON POWEA Pt ANT UNIT NO(s) 1 AND 2 REVISION 4 DATE 10/28/83 PAGE 20 CF 38 TITLE EMERGENCY EQUIPMENT, INSTRUMENTS 4 SUPPLIES TABLE 9 (Continued)
, $1REN NO. LOCATION 27C On Davis Canyon Ro about 1/2 mile off of See Canyon Road.
B27D On Davis Canyon Rd about 1.6 miles off of See Canyon Road.
27E On Davis Canyon Rd about 1 mile off of See-Canyon Road.
29 On Los Osos Valley Road about 2000' south of Madonna Road by Pacific Beach Continuation School 29A Off Los Osos Valley Road in Laguna Lake , area by Descanso Drive.
298 On Calle Joaquin next to Madonna shopping center parking lot in San Luis Obispo. ,
30 In San Luis Obispo on Prado Road.
31 In PG&E's Service Center yard on So.
Higuera.
31A On Jesperson Road, south of Buckley Road.
31B On Highway 101 Frontage Road 1 mile south cf Higuera off ramp.
31C On Highway 101 Frontage Road, just off Higuera off-ramp, about 2000' north of 500kV right of way.
31D Near end of private dirt road west of Higuera off-ramp.
31E Near 12kV line off Castro Canyon Road 1/2 mile off Highway 101 Frontage Road. (
32 - On Squire Canyon Road east of Highway 101 near intersection of San Luis Bay Drive and Monte Rd.
33 Across street from Bellview - Santa Fe Elementary School on See Canyon Road off San Luis Bay Drive. .
I DC0118 30XI i
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NUM3ER EP EF-5 i DIASLO CANYCN PCWEA Pt. ANT UNIT NOIS) 1 AND 2 REVISION 4 DATE 10/23/83 PAGE 31 0F 35
( Tirts EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 9 (Continued)
, SIREN NO. LOCATION 34 In Avila Skach near DCPP security gate.
34A Light house local coverage.
B34B 4 miles off See Canyon Road near 500kV right of way, by John Knemeyer's house.
35 In downtown Avila Beach near San Antonio Street.
36 Off Highway 101 Frontage Road near intersection of Shell Beach Road and Landing Road.
36A Off Highway 101 Frontage Road near intersection of Ontario, Road and Avila Road.
37A At Shell, Beach fire station.
t 38 On Mattie Road near McClintock's restaurant.
38A On Shell Beach Road near Price St. intersection.
39 In San Luis Obispo on Santa Fe Road south of Tank Farm Road.
40 On private property south of San Luis Airport.
41 On Biddle Ranch Rd just east of Edna Road.
42 On Price Canyon Road on Grace Oil property.
43 On Price Canyon Road about I mile north of Pismo Beach.
44 In Pismo Beach on a watertank in subdivision above Pismo Beach.
~
- 45. In Pismo Beach on Bello Road near Veteran's Hall.
46 On Highway 1 in So Pismo Beach 1/2 mile north of Grand Ave.
( -
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DC0118 31XI .
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NUMBER EP EF-5 ot4si.o CANYON powEA Pt. ANT UNIT NC(S) 1 AND 2 REVISION 4 DATE 10/28/93 PAGE 32 0F 38 TITLE EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 9 (Continued)
SIREN NO. LOCATION 47 In Grover City - 4th and Manhattan.
48 In Oceano on Railroad Avenue.
49 In Grover City at Water Tower on Hillcrest Dr.
49B On Oak Park Blvd. in Arroyo Grande .3 miles from Noyes Rd.
49C In Arroyo Grance near intersection of Oak Park Blvd. and Vista Del Robles.
50 Near Oceano on The Pike between LaVista and So.
Elm.
51 In Arroyo Grande near new fire station.
51A At PGandE Oceano substation on Valley Road south of Arroyo Grande.
52 In Arroyo Grande Road on Haasna Rd east of Stagecoach Rd.
52A On Printz Road north of Arroyo Grande.
52B On Noyes Road north of Printz Road.
53 On Valley Road (Highway 1) about 7000 ft, south of 51A and just north of Halcyon Rd.
56 Near intersection of El Campo & Clarkway.
57 On Valley Road (Highway 1) about 7000 ft. South of 53 and 1 mile south of Halcyon Rd.
l 58 At end of Stanton Road South of Los Berros Road.
59 On Los Berros Rd between Stanton and Pomeroy.
60 On Pomeroy Road 1 mile south of Los Berros Rd.
near Camino-Perrillo.
61 On Willow Road at Black Lake County Club.
DC0118 32XI
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NUMSER EP EP-S ciAetC CANYCN PCWER PLANT UNIT NO(S) 1 AND 2 REVISION 4 DATE 10/28/83 PAGE 33 0F 38 Tirts EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES
(
TABLE 10 CONTROL ROOM EMERGENCY PLAN EQUIPMENT ITEM SURVEILLANCE TYPE /FREOUENCY
- a. Emergency Assessment and See GOAP W-302 Response System
- 1) 984SC Computer
- b. Manual Dose Projection Equipment Inventory by Emergency Planning / Quarterly (Use form 69-10766)
- 1) Base Map
- 2) Seven Overlays .
, c. Closed Circuit TV Cameras Refer to the Technical Support Center
- d. Consnunications See STP I-29
- 1) Radio
- 2) Telephone
- 3) Emergency Signal
- e. Radiological Display See STP I-44
- f. Radiation Monitoring Displ'ay See STP I-18 4-
- g. Portable Video Camera Inventory by Emergency Planning / Quarterly (Use Fonn 69-10766)
(
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NUMBER EP EF-5 OIABLO CANYON POWEA PLANT UNIT NQ($) I ggg g REVISICN 4 DATE 10/28/83 PAGE 34 0F 38 TITLE. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 11 TECHNICAL SUPPORT CENTER EMERGENCY PLAN EOUIPMENT ITEM SURVEILLANCE TYPE /FRECUENCY
- a. Nuclear Data Comunications System None-used normally
- b. Control Room Closed Circuit Operability Check by Emergency TV Monitors Planning / Quarterly' i c. Comunications OperabilityCheckgyEmergency Planning / Quarterly
~
, 1) Radio .
- 2) Telephone
- d. Emergency Assessment and Response See GOAP W-302 System Inventory / Quarterly 2
- e. Manual Dose Projection Equipment
- 1) Dose Map
- 2) Seven Overlays
- f. Computerized Records Inventory Equipment by 2 Management System Emergency Planning / Quarterly
- g. Documents Normal Document Control Practices. Inventory by 2
Emergency Planning / Quarterly
- 1) Plant Manuals Volume 2 - Operating Procedures Volume 3 - Emergency Procedure Volume 4 - Licenses & Permits Volume 7 - Radiation Control (
Standards & Procedures Volume 9 - Temporary Procedures (Curves & Misc Data)
Volume 11- Emergency Plans l
69-10767 I
lUseForm Use Form 69-10768*
ncniin 3arir .
49 e
1 DIABLO CANYON POWEA PLANT UNIT NO(S) 1 AND 2 fE(fff0N DATE 10/28/83 PAGE 35 0F 38 TITLE EMERGENCY EQUIPMENT INSTRUMENTS & SUPPLIES TECHNICAL SUPPORT CENTER EMERGENCY PLAN EQUIPMENT (cont.)
ITEM SURVEILLANCE TYPE /FREOUENCY TYPf7FTE00ENCY
- 2) Piping Schematics
- 3) Instrument Schematics
- 4) Electrical Diagrams, Logic Diagrams and Electrical Arrangements S) Operating Valve Diagrams
- 6) Drawing 102037 - Instrument Locations
( Drawing 102038 - Instrument g 7)
Reference
- 8) Complete Set of Drawings
- 9) Complete Set of Documents
- 10) Cypher Pad Code for San Luis 0'bispo Service Center Garage
- 11) Corporate Emergency Response Plan
- 12) Nuclear Emergency Response Communications Directory d
( -
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DC0118 3SXIf
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ciAsto CANYCN PChvEA PLANT (P44T NO(S) 1 AND 2 ON E
DATE 10/23/83 1 PAGE 36. OF 38 ;
TITLE EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 12 OPERATIONAL AND OPERATIONS SUPPORT CENTER EMERGENCY PLAN EOUIPMENT ITEM SURVEILLANCE TYPE /FRE0VENCY Operational Support Center (Security Building)
- a. Kits for Emergency Use
- 1) Emergency Kits (2) Refer to Section 1
- 2) Evacuation Kits (2) Refer to Section 2 l
- 3) Hospital Kits (2) Refer to Section 4
- b. Communications .
- 1) Radio Refer to Security Procedures i
- 2) Telephone A) Direct line to TSC/CR Operability Check gy Emergency Planning / Quarterly B) Rolm phone Operability Check by Emergency Planning / Quarterly'
- c. Emergency Desk
- 1) Emergency Comr.unications Directory
- 2) Workoook Operations Support Center (Access Control / Cold Machine Shop)
- a. Communications
- 1) Telephone A) Direct line to TSC/CR Operability Cht.'c gy Emergency Planning / Quarterly B) Rolm phone Operability Check gy Emergency Planning / Quarterly 1
Use Form 69-10769 l
I l DC0118 36XII O
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DIABLO CANYON AOWEA PUNT UNIT NO(S) 1 AND 2 h g3 f DATE 10/2S/S3 PAGE 37 CF 38 k TITLE- EMERGENCY EQUIPMENT. INSTRUMENTS & SUPPLIES TABLE 13 EMERGENCY OPERATIONS FACILITY EMERGENCY PLAN EOUIPMENT ITEM SURVEILLANCE TYPE / FREQUENCY
- a. Emergency Assessment See GOAP W-302 and Response System (EARS)
- 1) 9845T Computer
- 2) Chromatics Col.orgraphics Display
- b. Manual Dose Projection Equipment Inventory by Emerggncy Planning / Quarterly
- 1) Base Map
- 2) Seven Overlays
' c. Consnunications Operability Check gy Emergency' Planning / Quarterly
- 1) Radio .
- 2) Telephone
- d. Consumables
- 1) Emergency Foms InventorybyEmerggncy Planning / Quarterly
- 2) Office Supplies Check by Emergency y Planning / Quarterly I Use Fom 69-10770 2
Use Fom 69-10771-3
( Use Fom 69-10582 1
DC0118 37XI!
NUMBER EP EF-5 DiABLo CANYCN PCWER PLANT UNIT NC(s) 1 AND 2 REVISION 4 DATE 10/28/83 PAGE 38 0F 38 TITLE EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES EMERGENCY OPERATIONS FACILITY EMERGENCY PLAN EQUIPMENT (cent.)
ITEM SURVEILLANCE TYPE /FREOUENCY
- e. Documents
- 1) Plant Manuals Normal Document Control Practice, Inventory by Emergency 2 Planning /
Quarterly Volume 2 - Operating Procedures Volume 3 - Emergency Procedures (3 copies)
Volume 4 - Licenses & Permits Volume 7 - Radiation Control Standards and Procedures
- Volume 9 - Temporary Procedure (Curves & Misc Data)
Volume 11.- Emergency Plans (3 copies)
- 2) Piping Schematics
- 3) Instrument Schematics
- 4) Electrical Drawings
- 5) Operating Valve Identification Diagrams
- 6) Drawing 102037 - Instrument Locations
- 7) Drawing 102038 - Instrument Reference l
l 8) Corporate Emergency Response Plan l
l
- 9) Nuclear Emergency Response Connunications Directory l 10) Cypher Pad Code for San Luis Obispo Service Center Garage l
t I Use Form 69-10770 2
Use Form 69-10771
~
3 Use Form 69-10552 ,
DC0118 38XII e@ S
10/53 Page 1 of 1 PACIFIC GAS AND ELECTRIC CCMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CAhYON POWER PLANT UNIT NOS.1 AND 2
(
EMERGENCY FACILITY PHONE NUMBERS I
- 1. ESERGENCY OPERATIONS FACILITY: ,
Radiological Emergency Recovery Manager l
Raciological Monitoring Director l
UCAC l
l 2. TECHNICAL SUPPORT CENTER Emergency Radiological Advisor i
I 3. DCPP SECURITY Security Shift Supervisor !
/
Central Alann System i
Secondary Alarm System - i i
1
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69-9823-1 10/B3 (25) BOX A Page 1 cf 3 NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2
(
EMERGENCY KIT INVENTORY CHECX LIST KIT NO. KIT LOCATION OUARTER DATE PERFORMED BY BOX A- QUANTITY DEFECTIVE REQUIRED pRESENT OR MISSING REPLACED 4
- 1. Sampling Equipment
- a. Trowel 1
- d. Air Sampling Equipment 4 a. 12V Air Sampler + Sample Head (w/ Battery, Radeco H-8098)
- b. 12V Air Sampler + Sample i '
Head (w/o Battery, Radeco t
- H-809C)
- c. 120V Air Sampler + Sample Head (Radeco HD-2SB) -
- d. Air Cylinder Regulator 1 l
- e. Compressed Air Cylinders (at 1700 psi) 2
- f. Sample Head w/ Adapter to fit Air Cylinder 1
- g. Air Sample Particulate a Filters (pkg of 10) 10
~
i l
- )
i
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DC0118 40XI
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69-9823-1 10/83 (25)
B0x A Page 2 of 3 NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 EMERGENCY KIT INVENTORY CHECK LIST KIT N0. KIT LOCATION QUARTER
- DATE PERFORNED BY BOX A QUANTITY DEFECTIVE REQUIRED PRESENT OR MISSING REPLACED j h. Paper Envelopes for Parti-l culate Samples (Air Sample) 25
- 1. Smear Packets (5 smear /pkt) 50
- j. Plastic Envelopes for Iodine Cartridges (Ziploc Baggies) 30
- k. Forceps 1
- 3. Protective Clothing / Decontamination ,
- a. Radiacwash Decontamination
- Agent (1 Gal, or Equiv.) I
~
- b. Skin Decontamination Soap (1 pt. or Equiv.) I
- c. Hand Brush I
- d. Floor Scrub Brush
- e. Bucket (10qt)
- Check with appropriate inventory list located in information binder for kit requirements.
m l
i I
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A 69-9823-1 10/83 (25) BOX A Page 3 of 3 NUCLEAR PLANT OPERATIONS DIABLO, CANYON POWER PLANT UNIT NOS. 1 AND 2
( EMERGENCY KIT INVENTORY CHECK LIST KIT NO. KIT LOCATION CUARTER - DATE PERFORNED BY BOX A . QUANTITY ,
DEFECTIVE REOUIRED PRESENT OR MISSING REPLACED 4 Monitoring Equipment
- a. Pocket dosimeter (0-5R) 2
- b. Pocket dosimeter (0-200MR) 2
- 5. Miscellaneous
- a. Gummed Labels (sheet) 5
- b. . Flashlight w/ batteries
- c. Extra Batteries
- d. Roll of Dimes 1
~
- e. Stopwatch ' I
- f. Scissors 1
- g. Crescent Wrench (8") I
- h. Screwdriver ,
1
- 1. Grass Shear 1
- j. KI Tablets (bottle) 1
- k. Bolt Cutter
( .
DC0118 42XI 49 ,
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4
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69-9823-2 10/83 (25) BCX B Page I cf 4 NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2
(
EMERGENCY KIT INVENTORY CHECK LIST KIT NO. KIT LOCATION CUARTER . DATE PERFORMED BY BOX B -
QUANTITY DEFECTIVE REQUIRED PRESENT OR MISSING REPLACED
- 1. Instructions, Procedures, and Supplies
- a. Instruction Binder 1
- b. Tables of Contents I
- c. Sanford Marking Pens 2 )
- d. Red Marking Pens 2
- e. Black Marking Pens 2
\
g
- f. Ball Point Pens 2
- g. SLO County Map 1
- h. Equipment Location Drawings (Set) Unit 1 1
- 1. Corporation Key (3A 90909) I
- j. Infonnation Center Key *
- k. " Emergency Onsite Environment Montr. Prog.", RB-7 1 -
- 1. " Emergency Offsite Environment Montr. Prog.", RB-8 1
- m. "Dnergency Equip. , Instr. ,
and Supplies", EF-5 1
- n. Record of Potassium Iodide Distribution, Form #18-9395 1 I
DC0118 43XI .
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i 69-9823-2 10/83 (25) BOX B Pa9e 2 cf a NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 EMERGENCY KIT INVENTORY CHECK LIST KIT NO. KIT LOCATION CUARTER DATE PERFORMED BY BOI B ,
QUANTITY DEFECTIVE REQUIRED PRESENT OR MISSING REPLACED
- o. Emergency Environmental Monitoring Field Data Sheet (Form 18-9259) 100
- p. Computation Paper (Packet) 1
- q. Calculator S/N 1
- r. High Security Pin Tumbler Key (for PIC) 1
. Air Sampling Equipment I
- a. Iodine Filter Cartridges 3 pkgs of 10 filters each: , .
1 pkg-AgZ 1 2 pkg-TEDA 2
- 3. Sampling Equipment -
- a. Plastic Bags Approx. (18" x 24") 15
- b. Sample bottles (1 liter)
- 5
=
9 DC0118 44XI ,
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69-9823-2 IC/83 (25) BOX B NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 MERGENCY KIT INVENTORY CHECK LIST KIT NO. KIT LOCATION QUARTER . DATE PERFORMED BY BOX B QUANTITY DEFECTIVE REQUIRED PRESENT OR MISSING REPLACED 4 Protective Clothing / Decontamination
- a. Protective Clothing Sets (Coveralls, hood, booties, rubbers, gloves) 2
- b. Full Face Mask 2
- c. Type GMR-S Filters or GMH-1 (or equiv.) ,
for Face Masks- 2
' d.
- Smear Pads 8" x 8" cotton -
(Pkg of 10) ,
- e. PaperTowels(pkg) *
- f. Plastic Bags (38" x 65") 3 l
(
l l
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I 69-9823-2 10/B3 (25) BOX B Page 4 of 4 NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 EMERGENCY KIT INVENTORY CHECK LIST KIT NO. KIT LOCATION QUARTER DATE PERFORMED BY BOX B QUANTITY DEFECTIVE
- 5. Miscellaneous Equipment REQUIRED PRESENT OR MISSING REPLACED
- a. First Aid Kit (Size 10) I
- b. Masking Tape (2" wide rolls) 2
- c. Battery Powereq Lantern (w/6V Battery) 1
- d. " Kwik-kold" Packs 4
- 6. Signs + Barriers -
- a. Radiation Signs (w/3 inserts) *
- b. Radiation Barricade Tape (100' Rolls) 2-
- Check with appropriate inventory list located in information binder for kit requirements.
l 1 .
m S
DC0118 46XI eg &
59-9523-3 10/83 (25) BOX C Page 1 cf 1 NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2
( EMERGENCY KIT INVENTORY CHECK LIST KIT NO. KIT LOCATION QUARTER - DATE PERFORMED BY BOX C QUANTITY DEFECTIVE REQUIRED PRESENT OR MISSING REPLACED
- 1. Monitoring Equipment
- a. Dose Rate Meter Rad Ow1/RO-2 (orequiv.)
- b. Oose Rate Meter HPI-1010 (orequiv.)
4
- c. Survey Meter (Eber. E-140 -
ore-140/N) 1
- d. Standard G-M Probe (Eber.
'- ,. HP-240/HP-270 or equiv.) I i
- e. Pancake G-M Probe (Eber. HP-210 .
or HP-260) I
- f. Dosimeter Charger 1
' Check with appropriate inventory list located in information binder for kit requirements.
Y f .
I I
OC0118 47XI .
49 g I --- - - . . --- , .- . - - - .
l 4
18-9369 Rev. 10/83 (4) Page 1 cf 2 1 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 EVACUATION KIT INVENTORY CHECK LIST KIT NO. DATE PERFORMED BY CHECKED DEFECTIVE OR ITEM OUANTITY OK MISSING REPLACED
- 1. Binder Contents
- a. Emergency Procedures G-4, G-5 1 each [] [] []
- b. Form 69-9310 50 [] [] []
- c. Form 69-9311 100 [] [] []
- d. Form 69-9369 5-10 [] [] []
- 2. Ballpoint Pens 4 [] [] []
, 3. Calculator (I.D. No. ) 1 [ ]' [] []
I \
Battery 1 []
4 Flashlight 1 []* [] []
Batteries 2 []
- 5. Plastic Bags (14" x 24") 3 [] [] []
- 6. Bullhorn (I.D. No. ) 1 []
Batteries 1 [] [] []
- 7. Packages of 2" Filters (10 filters per package) 50 [] [] []
- 8. Barricade tape,100 ft. rolls 2 [] [] []
- 9. Dosimeter chgr. (I.D. No. ) 1 [] [] []
Battery .
[]
- 10. Dosimeter pencils, 0-200 mA 4 [] [] []
(
DC0118 48,X I
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- - - - _ _ _ _ _ - , , - . . _ ,.4 ,- _
18-9369 Rev. 10/83 (4) Pa9e 2 of 2 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 EVACUATION KIT INVENTORY CHECK LIST CHECKED DEFECTIVE OR
- REPL4CED ITEM OUANTITY OK, MISSING
- 11. Rad Owl 1 [] [] []
(Replacement Inst. No. )
- 12. Eberline E-140 Survey Meter or E140N 1 [] [] []
(Replacement Inst. No. )
- 13. HP-240 GM Probe or HP-210 (I.D. No. ) 1 [] [] []
- 14. Corporation Key (3A90909) 1 [] [] [ J.
- 15. Information Center Emergency Room Key 1 [3 [] []
REMARKS 6
APPROVED DATE e
e I
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DC0118 49XI .
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-. _ _ __ _.- __ _ _ _ _ __ .___ __ _ =_ _ _ _ . _ _ _ _ _ - - _ _ _ _ _ __
69-10598 Rev. 10/83 (10) Page 1 of 3 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 HOSPITAL KIT INVENTORY CHECK LIST l 1
KIT NO. DATE PERFORMED SY
! CHECKED DEFECTIVE i OR
- ITEM OUANTITY E MISSING REPLACED
- 1. Full Face Respirator w/ Type H or equivalent filters 2 [] [] []
- 2. Disposable Coveralls 4 [] [] []
i 3. Hood 4 [] -[] []
4 Disposable Shoe Covers (pr.) 4 [] [] [] l S. Surgical Latex Gloves (box) 1 [] [] []
- 6. Rubbers (pr.) 4 [] [] []
. 7. Masking Tape, 2" width (roll) 2 [] [] []
- 8. Duct Tape, 2" width (roll) 2 [] [] []
- 9. " Radioactive Material Area" sign 5 [] [] []
- 10. " Surface Contamination Area" sign 5 [] [] []
- 11. "High Radiation Area" sign 2 [] [] []
- 12. " Radiation Area" sign 5 [] [] []
- 13. Barricade tape,100 yd. roll 2 [] [] []
- 14. Ty-wraps 30 .[ ] [] []
- 15. " Radioactive Material" labels, 4"x6" 10 [] [] []
- 16. " Radioactive Material"' labels, 1"x3" (roll) 1 [] [] []
- 17. E-140/N w/HP-210T 1 -[] [] []
- 18. HP-260 1 [] [] []
I
( .
0C0118 50XI
--,.,,-.-...-,----.--%.w-
4 69-10598 Rev. 10/83 (10) P2ge 2 of 3 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 HOSPITAL KIT INVENTORY CHECK LIST l KIT NO. DATE PERFORMED BY CHECKED DEFECTIVE OR ITEM OUANTITY OK MISSING REPLACED
- 19. Spare Detector 1 [] [] []
- 20. Allen Wrench, 1/16" 1 [] [] []
- 21. HPI-1010 or equivalent 1 [] [] []
- 22. 0-200 mR Pencil Dosimeters 2 [] [] []
- 23. 0-5R Pencil Dosimeters 2 [] ,
[] []
- 24. Oosimeter Charger w/ Battery ,
1 [] [] []
i '5. 2" Smears w/ packet (5 smears / packet) 50 [] [] []
26, 2" Air Sample Filter w/ envelopes 50 [] [] []
27, 38m Air' Filter for Bendix BDX-60 (box) 1 [] [] []
- 28. Plastic Envelopes, 3" x 5" 30 '[] [] []
- 29. Gumed Labels 40 [] [] []
- 30. Plastic Bags, 38" x 65" 6 [] [] []
- 31. Grease Pencil 2 [] [] []
j 32. Ballpoint / Felt Tip Pens 3 [] [] []
! 33. Waterproof Pen -
2 [] [] []
l 34 Personnel Decon, Records (69-9392) 6 [] [] []
- 35. Contamination Survey Sheet (69-9315) 6 [] [] [] ,
- 36. Radiation.50rveySheet(69-9316) 6 [] [] []
f OC0118 51XI I . . .
69-10556 Rev. 10/83 (10) Page 3 of 3 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2
{
HOSPITAL KIT INVENTORY CHECK LIST KIT NO. DATE PERFORMED BY CHECKED DEFECTIVE OR ITEM OUANTITY g MISSING REPLACED
- 37. Forceps 1 [] [] []
f 38. Smear Pads 8" x 8" cotton (Pkg. of 10) 2 [] [] []
i l 39. Medical Referral Form (69-6015) 3 [] [] []
- 40. Light Duty Letter 3 [] [] []
- 41. Plastic Bag, 18" x I4" 12 [] [] ,
[]
]
- 42. BCX-60 Air Sampler 1 [] [] []
i i
I REVIEWED BY DATE i
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- 527.
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69-10507 Rev. 10/83 (S) Page 1 of 2 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 POST-LOCA SAMPLING KIT INVENTORY CHECX LIST l KIT NO. DATE PERFORMED BY
! CHECKED DEFECTIVE OR ITEM QUANTITY E MISSING REPLACED INSTRUCTION BINDER I
Sanford Marking Pens Red Marking Pens 2
2 ll l, ll Black Marking Pens 2 ,, ,, ,,
Ballpoint Pens 2 ,, ,, ,,
EP-EF-5 " Emergency Equipment.
Instruments. Supplies" 1 [] [] []
CAP-G-1 " Access to IPLSS Area, Post Accident Sample Preparations,
- Handling and Analysis" 1 , [] [] []
CAP-G-2 " Interim POST LOCA Sampling
,'l ll System" 1 ll l Emergency Phone Directory 1 ,, ,, ,,
i Adhesive Backed Sample Labels 20 ,, ,
MONITORING EQUIPMENT Teletector (Eberline 6112) 1 Pocket Dosimeters (0-5R) 2
PocketDosimeters(0-200mR) 2
l Desimeter Charger 1
l Finger Rings 12
Dose Rate Meter (HPI-1010 or R0-2) 1 Survey Meter (Eberline E-140/N) L ll
Pancake G-M Probe (Eberline HP-210 or
Hp.260) 1 Bendix BOX-60 Air Sampler 1 'l
, 'l
, AIR SAMPLING EQUIPMENT Tongs 1 1 Forceps 1 Silver Zeolite (AgZ) Cartridges 12 5cc Shielded Syringes 5 (',
l' DC0118 53XI ,
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l 69-10507 Rev. 10/53 (5) Page 2 of 2 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 I i POST-LOCA SAMPLING KIT INVENTORY CHECKLIST KIT NO. DATE PERFORMED BY CHECKED DEFEiTIVE OR ITEM OUANTITY OK. MISSING REPt. ACED Glass vials (14cc) w/ rubber stoppers 12 ll ll ll l Air Sample Filter Cartridge Assembly 2 ,, ,, ,,
Surgical Tubing (1/4") 5ft Duct tape 3 '
,J
,],
Air Sample Particulate Filters (Pkg of 10)
~ Compressed Air Cylinders 3
2 ll l,
- l Air Cylinder Regulator 1 ,, ,, ,,
Plastic Bags (15" x 30") 20 ,. L , l S-D Hypodemic Needles (LUER-LOK pkg of 12) 4 ,; ;; . ,3
" Radioactive Material" labels iroll ,, ,, .] *
'1 quid Sample Vessel Adapter Tubing (plastic tubing w/ male adapters) 2 [] [] []
38arn Air Filters for Bendix BDX-60 ,
air sampler 1 box [] [] []
HISCELLANEOUS EQUIPMENT Protective clothing sets 2 [] { J' []
(coveralls, hood, booties, shoe covers, ,
gloves)
Stopwatch 1 ,l ll l}
Calculator 1
Crescent Wrench (8")
Screwdriver 1
1 ll 'l Allen Wrench (3/32") 1 Masking Tape (2" wide rolls)
Flashlight w/ batteries 1
1 ll
',l Extra batteries 2
Allen Wrench (5/64")
Key to East Gates Outside Elevation 115' 1
1 ')
I,'
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- 69-9043 10/83 (S) Page ! cf 3
- UEPARTMENT Of NUCLEAR PL/ST OPERATIONS
. DIABLO CANVON POWER PLANT EMERGENCY PLAN Pai0NE ttuMBER VERIFICATION CHECKLIST
- CHEt.KtD BY DATE PROCEDURE NO. PAGE NO. AGENCY COPMENTS (Note How Checked) t EP OP-S p. 8 TSC Operator, dedicated shutdown panel, 480V i vital switchgear area, 4 KV vital switchgear area l EP R-1 Attachment 7 Safe,ty, Health & Claims Personnel (Injuries)
- p. 1 & 2
- p. 9 San Luis Aneulance and French Hospital
- p. 15 Supervising Nuclear Generation Engr.
i "
EP R-3 p. 3 State Executive Officer, Calif. Regional Water Quality Control Board, Central Coast Region EP R-7 p. 8
- Supervising Nuclear Generation Engr.
i
- p. 9 Los Padres District Manager
) EP M-1 p. 5 Supervising Nuclear Generation Engr.
Attachment 7 List of physicians, hospitals & ambulances serving the f aunediate area of Diablo Canyon.
Attachment 8 List of physicians, hospitals, and ambulances
. serving the leanediate area of Diablo Canyon
. Attachment 9 Safety Health and Clales. ,
- DrAIIR SSVI I
J , . . .
4 69-904'2 .0/83 ' (5) .P _. 2 of 3 DEPARTHENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT EMERGENCY PLAN PHONE NUMBER VERIFICATION CllECKLIST .
CllECKED BY DATE e
. PROCEDURE NO. PAGE NO. AGENCY CON 4ENTS (Note How Checked)
EP M-2 Appendix Z Supervising Nuclear Generation Engr.
Division Field C1 sins Investigator EP M-4 P. 4, 7," and UC Berkeley Seismograph Station
- Attachment EP M-6 p. 3 Security Extensions
- p. 8 Fire Assistance Communications List .
EP M-7 P. 2 PGandE Law Department, Mr. David Williamson
- p. 2 Organizations to.be notified in the event of
' an oil spill
- p. 2 California State Office of Emergency Service
- p. 3 California State Land Commission -
- p. 3 State Executive Officer California Regional Watet Quality Control Board Central Coast Region EP OR-1 Attachment 2 Table 1 - Offsite Emergency Support Organization 4
EP OR-2 Attachment i Media Notification List DColl'8 56XI
n - n 69-904,i 10/83 (5) , ;Ptge 3 of 3 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT EHERGENCY PLAN Pil0NE NUMBER VERIFICATION CllECKLIST e CllECKED BY DATE PROCEDURE NO. PAGE NO. AGENCY CDPetENTS (Note flow Checked)
EP EF-1 p. 2. Attachments llot shutdown panel, dedicated shutdown panel, 1, 2, 4 Control Room. E0F, CIRC, Dosimetry personnel EP EF-4 Attachment 1 PT&T and PGandE EP EF-5 Attachment 1 EOF, UDAC. TSC, DCPP
. EP RB,-8 p. 3 DCPP, EOF, TSC EP G-2 Attachment 1 Emergency Organization Call List- -
- p. 1-28 EP G-3 Attachment 2 Emergency Offsite Organization Call List Attachment 3 Mobile Phone and Pager Instructions EP G-4 p. 4 Emergency Conference Line
- p. 6 Emergency Conference Line
- p. 7 Control Room. TSC, Cold Machine Shop, Access Control
- p. 8 Security Building. Temp Training Building, Security Training Trailer 9
DC0118 57XI
69-10766 (12) 7/83 Page 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATI0h5 DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2
( TITLE: CONTROL ROCM CHECKLIST DATE PERFORMED BY
- 1. Dose #rojection Equipment (1). Base Map (7) Overlays (Stability Class A-G)
- 2. Portable Video Camera (in Shift Foreman's Office) l l
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DC0118 58XI
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l 59-10767 10/83 (12) Page 1 of 3 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2
( T!TLE: TECHNICAL SUPPORT CENTER CHECKLIST DATE PERFORMED BY
- 1. Radios Check functioning of the following: (Use Operating Procedure K-9 " Instructions for Operation of DCPP Radio Systems")
Operations Modules Check functioning of the Repeater / Local, Backup and Remote modules by receiving available selecting onecalling traffic or by and check module functioning the Information Center by(encode 22 on F1) or Morro Bay (encode 33). []
g: Transmitter functioning is checked by operations using STP I-29 Security Modules Check function of the Repeater / Local Backup and Remote modules by selecting one and check module functioning by receiving Local Traffic. []
( _, : g: Transmitter functioning is checked by Security.
Division Radio Check module functioning of the divis1ori radio modules by selecting each and receiving available Traffic, g: Transmitter functioning is checked by operations using STP I-29.
g: If no Traffic is available note that below.
H/P Radio Check functioning of the Repeaters, Local and HP Remote modules by selecting one at a time and activating an Emergency Organizat19n pager unit. []
g: Pager must be outside the TSC to receive the signal. ,
5 DC0118 59XI
69-10767 10/83 (12) Page 2 of 3
, PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON PCWER PLANT UNIT NOS. 1 AND 2 TITLE: TECHNICAL SUPPORT CENTER CHECKLIST Note any problems with the radio console:
- 2. Telephones bgTE: CSX Telephones are in routine use and need not be checked.
Check fur.ctioning of t ROLM Console by turning on, calling the plant emer.9ency number 595-733 from any phone and receiving the call at the console. tend the all to any extension and verify '
connections Litween,the originating phone and the ringing phone. []
. TURN OFF CONSOLE AFTER CHECKING Verify the ATL to San Luis Obispo County Sheriff's Dispatch Center ,
by verifying the phone is answered at that office and two-way connunication can be maintained. ,
Verify the ATL to the State Office of Emergency Services by verifying
.. the phone is answered at that office and two-way communications can -
be maintained. Check both extensions (Site Emergency Coordinator's desk and EARS office) []
Check functioning of the following ATL's by verifying they ring when selected. Allow to ring long enough so someone in the vicinity can answer, if available: []
OFFICE OPERATIONS CENTER EARS OFFICE CR-1 [] [] []
CR-2 [] , [] []
OSC [] []
EOF -[ ] [] []
i OC0118 60XI
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69-10767 10/83 (12) )
Page 2 ef 3 PACIFIC GAS AND ELECTRIC CCMPANY DEPARTMENT OF NUCLEAR PLANT OPEPAT!ONS k
DIABLO CANYCN PCWER PLANT UNIT NOS. 1 AND 2 7?TLE: TECHNICAL SUP:0RT CENTER CHECKLIST Verify functioning of cre f# etmise xtension by calling any plant extension usin Office Operations Center '1 EARS Office 'i
- 3. l)
Verify functioning of The Black Net Telephone by calling any extension.
4 []
Check functioning of the Control Room Closed Circuit TV's as follows (Refer to operating instructions in the TV desk drawer):
Color menitors 1 - 5 receive pictures from cameras 1 - 7
()
Black and White monitor f6 receives pictures from cameras 8 and 9.
[]
Pan, zoom and focus controls on cameras 1 - 7 function
[]
NQT[: _Close the iris on cameras 1 - 7 followino check.
5.
4, Equipment Quantities - Check per Form 69-10752 Note Discrepancies Below:
OC0118 61XI
69-10768 ~10/83 (12) Page 1 of 2 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON D0iiER PLANT UNIT NOS. 1 AND 2
( TITLE: TECHNICAL SUPPOR . ITER EQUIPMENT OUANTITY CHECKLIST OFFICE
. 1 Rolm Telephone Console with Handset 1 Emergency Equip. Cabinet: Status Boards (6) and I telephone numoer board 2 Headsets '
Box of Office Emergency Supplies Telephone (Verify7)(ample stationary supplies)
Directory 16 Nameplates Emergency Classification Diagram Emergency Forms per form 69-10582 4 TI-1750 III Calculators 1 Case of KI ,
OPERATIONS CENTER Emergency Forms per form 69-10582 Closed Circuit TV Monitors - 5 color 1 Black and White Tape drive & disc Harris Processor,- Computer
( Harris Teminal
\._ Harris Key Stations - 2 (Teminals) I f Harris Line Printers (2)
Nicolet Zeta Plotter *
, TI ONMI 800 Printer, EARS OFFICE EARS Computer and Operating Terminal Emergency Telephone Directory (3)
Emergency Forms per form 69-10582 1 Status Board 1 Set Dispersion Overlays and Map in Holder RECORDS OFFICE Aperature Card Viewer Aperature Card Files with Cards Microfilm Printer / Viewer with Reels Teledyne Geo Tech' Auto Met V Computer l
I DC0118 62XI, l
j 1
69-10768 10/83 (12) Page 2 of 2 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS O!ABLO CANYON POWER PLANT UNIT N05. 1 AND 2 TITLE: TECHNICAL SUPPORT CENTER EOUIPMENT CUANTITY CHECKLIST RECORDS OFFICE (CONTINUED)
Construction DWG Index Books I and 2 7 Phone Books 18 MSA SCBA's Panafax Document Transmitter - MV1200 Micro-fiche Printer / Viewer Hewlett Packard Computer Terminal (1)
Instruction Manuals - Hard Copy in Cabinets (2)
Plant Manuals Volume 2 Operating Procedures'A-F, G-0, #67 Volume 3 Emergency Procedures, #66, 67, 79 Volume 3A Emergency Procedures, #66, 67, 79 Volume 38 Emergency Procedure, #66, 67, 79 -
Volume 4 Licenses & Permits, #67 Volume 7 Radiation Control Standards, #67 Volume 9 Temporary Procedures & Instructions, #67 -
Volume 11 Emergency Plans, #66, 67, 79 Volume 16 Annunciator Response, #67 Volume 1-14 Final Safety Analysis Report RMS Handbook - TSC ,
Equipment Record Number Index Corporate Emergency Response Plan, Control #271-272 Diablo Canyon Emergency Response Communications Directory (2 binders)
Emergency Response Manual - !NPO RP/EP-19/80 -
Report on Small Break Accidents for Westinghouse NS$$ System Vol. I, II, !!!
Reference Dwg. 102037, 102038 - Instrument Locations Reference Owg. 101876 Main Annunciator Input List 101900 - List of Equipment Location Codes - Unit 1 i Uncontrolled Emergency Procedures Volume - (there are 6 binders all the same)
Operating Valve Identification Diagrams, Control Copy #31 - Unit 1 Instrument Schematics, Control Copy #24 Electrical Diagrams, Logic Diagrams & Electrical Arran~gements, Control Copy #27 Unit 1 and 2 Piping Schematics, Control Copy #3 NRC 0FFICE NRC Red " Hot Line" Phone .
NRC Blue HPN Phone NRC HPN Phone Directory (1)
O DC0118 63XI - .
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l 69-10769 7/83
- Page 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERAT!CNS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2
( TITLE: OPERATIONAL SUPPORT CENTER AND OPERATIONS SUPPORT CENTER CHECK LIST DATE PERFORMED BY 0:erational Supoort Center (Security Building Lunchroom)
- 1. Check CBX extension by calling Unit 1 Control Room .
Verify the Control Room answers. []
- 2. Check ATL to CR/TSC by lifting receiver, verify Control Room answers. []
- 3. Operational Support Center Workbook.* []
Procedure Rev. No. '
G-4 l EF-2 Form 69-9639, Date , Quantity (12)
- Check procedure revision number and form date against a controlled copy of the emergency procedure (Plant Manual Volume 3A). Note any discrepancies below and provide updated material.
t 0:erations Support Center (Access Control / Cold Machine Shop Area)
- 1. Check emergency CSX extension by calling Unit 1 Control Room.
Verify the Control Room answers. []
- 2. Check ATL to CR/TSC by lifting receiver, verify Control Room answers. []
s W I
( .
DC0118 64XI ,
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l 69-10770 2/84 -
Page 3 of 3 l
l TITLE: EMERGENCY OPERATICNS FACILITY EQUIPMENT FUNCTION CHECKLIST PHONE LIST
{
TITLE PHONE
- GOOD ~
210 l
spos [] []
ESE . [] []
LAW [] []
MET [] [] i RM3 C] []
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- ucAc [] [] ,
ucAc [] [] !
ucAc [] []
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ocPP [] [] ,
1 LAW [] [] l l MET C] [] l
- MD [] [] l l coAc [] []
l ELRM [] []
l i RM [] []
! 0 ARM [] [] i
- RERM [] []
.l EARS [] []
PIRM [] []
l l ELRM [] []
l RM C] [] :
cAPM [] []
RERM [] [] ;
EARS [] [] l l PIRM [] [] i i sPos [] [] !
l ESE [] []
l SEC -
[] []
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I DC0118 67x1 l
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Page 2 of 3 69-10770 2/84 (12)
TITLE: EMERGENCY OPERATIONS FACILITY EOUIPMENT FUNCT:0P: CHECKL:57 LIGHTS Make sure that all lignts turn on and off. (Second floor only)
Note any pr:Diems below:
Y
- CD:EUS
'he e s're 2 Savin 5C40 copy machines in the EOF. One is located in tne EL:M office.
tre :tNer is in tre UCAC office. Tu n on main ocwer switch Iccated at rign: s'ce Of ma:N'ne. In c a. ;usn 'On" button on ::o of the ma: hine. Wait 'or ::cier :: .a-m 20.
a :eectng scunc .1'1 :all anen machine is ready. Also, tne acrc "REA3Y" **ll a:: ear
- n _ED disaisy. Iet number of copies at 30. Place original in auto-feed. Li;ntec s* gr .111 <e-1'y nat original is inserted. Press PR:NT. C:cier snouic ac:e::
i Original, r n: 30 c:oies, and return original. Turn c: pier off wnen finisned.
Cneck for su: plies of c0py paper (at least 6 packages). Check for copy macntne sis;eesant and ::ner (at least 2 bottles of eacn).
Note any pr00lems or ccmr.ents belcw:
DANAEAX Turn on pcwer. Call Admin, operat:r and ask operator for sceecce to hei:
test Panafax System. Transmit 1 message from EOF to office. Receive 1 message fr:m of# ice.
Note any or:olems or ccaments belew: .
CC0 13 66XI ,
69-10770 2/84 (22) Page 1 of 3 PACIFIC GA5 AND ELECTRIC COMPANY CEPARTMENT OF NUCLEAR PLANT OPEUATIONS
(, DIABLO CANYON PC'aER PLANT UNIT N05. 1 AND 2 7 TLE: ewe 23ENCY CPERATIONS FACILITY ECUIPMENT TUNC*!CN CHECKLIST PHCNES Check cnly : nose phones :na: exist on the sec:nd floor of the building. Check by using the multi-line pnene on the Engineering and Logistics Recovery "anager's cesk.
Lift tne receiver, push each button, I ce light and listen '- --
dial t:ne. New push the butten labele Otal all of n numoers. Then cusn the butt:n lacelee ni all of *e num:ers (31a1 jus: :ne last 4 digits). For eacn o :ne nue:ers cta!ec sten :r a c'nging ::ce in tre ear;iece. NOTE: not all of the pnenes have an auci:le tete:ncre tell so listen only for tne ringing tone in the earpiece. Check :na* eacn ;nene can maintain twc-.ay c:mmunications, using the pnene enecklist on : age 3.
Check the pnenes in the NRC Of' ice and in the_ 5 tate / FEMA Of' ice follcwing :ne same
'o rma : as stated aceve.
Note an/ problems' or comrents below:
(
UADIOS Cnect :ne " adios in the OARM Office, ELRN office, and in the Radiological Menit: ring Otrect:r' "4=.. Check handie-talkies in RMD's Office. Call Diaolo Canyon Uni: 1 by ;nene to let control ocerators knew you are going to cneck the radios.
Turn radio on. ror the CARM and ELRM office radios with frequency selection, selec:
F2. Pick up handset (radios in CARM Offic:?. Use enc: der to call 014:1c Canyon c:ntrol recm: code 41, push button 4 and inen butten 1. Pusn transmt: butten on nandse or desk too microchene. Transmit message, "Diablo Centrol, this is the ECF.
Radio CNeck, please." Release it;9 smit L.tt0n and wait for respense. If there is no res:cese within 20-30 sec:nds, repe.: et ade and message. Make sure pewer is turnec off wren finisned. For handie-talkies .. lect F5 and call the Radiological Monitoring 01 rec:or's of' ice, receat using F6 to check the local receiver.
Note any pr:blems or c:mments below:
OC0118 65X!
69-10771 2/84 (4) #5' l Of S PACITIC GAS AND ELECTRIC CCMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2
( TITLE: EMERGENCY OPERATIONS FACILITY INVENTORY CHECKLIST OFFICE SUPPLIES Check contents of all desks and file cabinets for ample quantities of
, stationary supplies, such as: ball point pens, erasers, felt pens (various colors), rubber bands, paper clips, pencils, scissors, rulers, ruled note paper, stapler removers, scotch tape, carbon paper, assorted plain paper, etc.
OPERATIONS AND ANALYSIS RECOVERY MANAGER
, 1 Chair 1 1 desk 1 50 mile map 1 10 mile map 2 Motorola radio sets with encoder 1 multi-line phone Emergency Procedures Vol 3A &38 (3 binders)
Emergency Plans Vol 11 (2 binders)
Corporate Emergency Response Plan (1)
Nuclear Emergency Response Connunications Directory (1) i 3 clipboards ENGINEERING AND LOGISTICS RECOVERY MANAGER
( 6 chairs 3 desks 1 table 1 half-table 2 Motorola radio sets with encoder 3 multi-line phones 2 single-line phones 1 IBM Selectric III 1 Panafax machine 1 Savin 5040 copier 1 bookcase 2 SPDS video monitors with display generators (A&B) 2 SPOS switchboards (A&B) 1 Tektronix 4631 Hard Copy Machine 1 IT Intermediate Terminal ADM-31 1 Tanberg TOC 3000 digital cartridge recorder 1 Tektronix 4006-1 terminal 1 Digital Deewriter III 1 Recall Recorder (plus Giltronix Selectro switch)
I contrack 15-drawer file 2 clocks 3 status boards (Significant Events, Plant Status, Radiological Status)
Operating Procedures Vol 2 (S binders)
Drawing 102037 -- Instrument Locations (1 binder)
Drawing 102038 -- Instrument Reference {1 binder)
( Emergency Procedures Vol 3A & 38 (3 binders) .
Licenses and Permits Vol 4 Radiation and Control Standards and Procedures Vol'7 DC0118 68XI 49
- 69-10771 2/84 (4) Page 2 of 4 TITLE: EFERGENCY OPERATIONS FACILITY INVENTORY CHECKLIST f
ENGINEERING AND LOGISTICS RECOVERY MANAGER (Continued)
Chemical and Radiochemical Procedures Vol 8 (3 binders)
Temporary Procedures and Instructions Vol 9 (2 bincers)
Emergency Plans Vol 11 (2 binders)
Electrical Drawings Units 1 & 2 (2 binders, green)
Operating Velve Indentification Diagrams Units 1 & 2 (2 binders, black)
Piping Schematics Units 1 & 2 (2 binders, orange)
Instrument Schematics Units 1 & 2 (2 binders)
Hosgri Seismic Evaluation (7 binders)
Nuclear Emergency Response Communications Directory (6)
Corporate Emergency Response Plan (1)
State of California Nuclear Power Plant Emergency Response Plan (7 binders) 3 clipboards RECOVERY MANAGER'S OFFICE 11 chairs '
1 desk 1 8' table 1 white board ,
1 50 mile map 1 10 mile map 1 multi-line speaker phone 1 Black-Net phone ,
1 Yellow-Net phone ,
1 bookcase
- 1 5-drawer file 1 coatrack 1 clock Emergency Procedures Vol 3A & 38 (3 binders)
Emergency Plans Vol 11 (2 binders)
Corporate Emergency Response Plan (2)
Nuclear Emergency Response Connunications Directory (1) 4 clipboards .
PG&E LAW OFFICE 1 chair .
1 desk 1 multi-line phone 1 clock .
3 clipboards l
l e
. DC0118 69XI l
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i 69-10771 2/84 (4) Page 3 of 4 2
TITLE: EMERGEN'CY OPERATIONS FACILITY INVENTORY CHECKLIST
( pG&E PUBLIC INFORMATION 4 chairs
'; 2 desks I table 4
2 multi-line phones
, 1 single-line phone i
1 Yellow-Net Phone
- 1 50 mile map
] 1 10 mile map 1 IBM Selectric !!!
l 1 Remington manual typewriter 1 IBM Electric typewriter dedicated to Media Center (older model) 1 Sanyo AM-FM cassette radio i 1 AIWA multi-band cassette radio (Model CS-360, Serial #P30509248)
. 2 TI Silent 700 portable data terminals 3 typewriter stands '
I white board 5 clipboards l RA0!0 LOGICAL MONITORING O! RECTOR l 3 chairs 1 desk
! 1 table
( 1 Motorola radio set i
1 2 Motorola Handi-Talkies 3 Motorola Handi-Talkie Chargers 15-drawer file 1 50 mile map
- 1 10 mile map
! 1 Radeco Particulate Air Sampler
! 1 County Health Team Radio (Motorola Series 90)
I 1 Speedcall Motorola 434 Display I 4 C11pboards
! UNIFIED DOSE ASSESSMENT CENTER 17 chairs 6 desks , ,. L
^
6 tables -
10 multi-line phones 6 50 mile maps 6 10 mile maps i 5 modular shelves with lights
( 1 Overlay Base Map with 7 Overlays (Stability Classes A-G)
I coatrack i 2 clocks -
l l' Savin 5040 copier .
1 Rapidorint Time Clock 1 IBM Selectric !!!
( 1 Aerovironmental Model 322A Chart Recorder 1 Aerovironmental Model 324 Telephone Line Receiver DC0118 70XI .
og *
--,--,---,n-.---n . - , - - ~ .-, - - , - , -, , - , , , - _ - - - - . . . , - - , . . . - - , ,,,---,re, - - , - , - - - . - - - - - . . . ~ , - . , --
3 69-10771 2/84 (4)
Page 4 of 4' TITLE: EMERGENCY CPERATIONS FAC!LITY INVENTORY CHECKLIST 4 UNIFIED DOSE ASSESSMENT CENTER (Continued)
~
1 Hewlett-Packar'd 2621P Terminal 1 Texas Instruments OMNI ECO Terminal 1 Hewlett-Packard 9845C Desk-Too Computer
. 1 Hewlett-Packard 98041 Disc Interface
'l Hewlett-Packard 7906 Disc Drive 1 Hewlett-Packard 13037C Disc Controller 3 5-drawer files
- Emergency Procedures Vol 3A & 38 (3 binders) -
i Emergency Plans Vol 11 (2 binders)
Nuclear Emergency Response Comunications Directory (5) 4 status boards (Significant Events, UDAC Duty Roster, Field Monitoring Data, Radiological Status)
I 16 clipboards LUNCH ROOM 27 chairs 7 tables i 1 kitchenette -
- I clock i 1 100-cup coffee' pot Misc. supplies (coffee, cups,etc.)
STATE / FEMA 5 chairs 4 desks .
I table 4 multi-line phones 1 single-line phone t 2 Yellow-Net phones *
! 2 status boards (STATE, FEMA)
' 1 50 mile map 1 10 mile map 1 easel
! MS -
l 12 chairs 2 desks
! 3 tables j 1 10' table 4 multi-line phones 1 Red phone i 1 Blue phone 1 Black-Net phone 1 Yellow-Net phone 1 white board 1 50 mile map .
1 4
1 10 mile map ,
1 clock DC0118 71XI l - . _ _
I i
69-10582 2/84 (12) Page 1 of 2 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 I TITLE: EMERGENCY FACILITY FORMS FILE LIST
, APPROX! MATE QUANTITY CURRENT i FORM j DAlt NUMBER TITLE T-1 T-2 T-3 E-1 E-2 69-9221 Emergency Notification Record 20 20 20 20 20 4
69-9230 Work Sheet for Determination of X/Q 5 20 5 10 i 69-9248 Post-Earthquake Evaluation Sumary 5 69-9249 Post-Earthquake Level Indication Checklist 5
. 69-9250 Post-Earthquake Area Inspection 5 69-9251 Post-Earthquake Surveillance Test Check List 5
' 69-9252 Electrical Power Check List -
5
' 69-9259 Emergency Environmental Monitoring Field Data Sheet 20 10 10 20 20 69-9250 Work Sheet for Determination of Release Rate or Total Release from Plant Vent i Monitoring 5 5 20 5 10 -
li 69-9283 Data Sheet for T-G Peak Recording Accolograph 5
- 69-9284 Work Sheet for Estimation of Curie Release 5 5 20 5 20 -
' t 69-9310 Post-Evacuation Vehicle Monitoring Data 10 10 10 5 69-9311 Evacuee Monitoring Data 10 10 10 5 69-9313 Controlled Area and Airborne Area Entry Log .
. 10 20 5 5-
! 69-9315 Contamination Survey Record 10 10 5 3
69-9316 Radiation Dose Rate Survey Record 5 5 5 5 69-9320 High Radiation Area Entry Log 10 5 5 1 69-9321 Containment Entry Log -
5 5 5 69-9370 Site Emergency Organization Assignment 10 5 5 j 69-9371 Environmental Monitoring Data Sumary 5 5 5 5 69-9392 Skin and Clothing Decontamination 10 10 5 I
69-9395 Record of Distribution of Potassium Iodine 10 10 10 10 69-9510 Special Work Permit Request 10 20 5 5 j 69-10059 Individual Accountability Record 20 t
1 69-10060 Sumary of Personnel Accountability 10 69-10262 Radiological Emergency Status Form 20 5 20 20 20 69-10295 Plant Status Emergency Form 20 20 5 20 20 69-10296 Onsite/Offsite Rad. Field Monitoring.
) and PIC Status Form 20 5 20 20 20 j 69-10297 5 5 5 69-10298 Emergency Organization Emergency Organization Call Call List (On-site))
List (Off-Site 5 5 5 69-10554 Emergency Exposure Permit 10 10 10 1
69-10555 Work 'iheet for Release Rate Estimation i from Containment High Range Area Monitors 5 5 20 5 10 4
69-10556 Release Rate Sumary 5 5 20 5 10 69-10566 Worksheet for Manual Off-Site Dose Calculations 5 5 5 5 69-10581 Initial Emergency Notification Form 5 5 5 -
1 DC0118 72XI l .
I 69-10582 2/84 (12) page.2 of 2 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON P0iiER PLANT UNIT NOS. 1 AND 2 TITLE: EMERGENCY FACILITY FORMS FILE LIST APPROXIMATE QUANTITY CURRENT FORM
- DATE NUMBER TITLE T-1 T-2 T-3 E-1 E-2 69-10582 Emergency Facility Forms File List 2 2 2 69-10766 Control Room Checklist 2
. 69-10767 Technical Support Center Checklist 2 4
69-10768 Technical Support Center Equipment 4 Quantity Checklist 2 i 69-10769 Operational Support Center and Operations
- Support Center Checklist 69-10770 Emergency Operations Facility Checklist 2 2 69-10771 Emergency Operations Facility Equipment Quantity Checklist 2 2 None Personnel List Diablo Canyon Power Plant .
Department of Nuclear Plant Operations 2 2
- R-2 Appendix 2 - Instructions for Estimating ,
2 Noble Gas Release Rate Using Plant Vent Monitors RE-14 or RE-29 5 5 5 5 5 R-2 , Appendix 3 - Instructions for Estimating lodine Release Rate Using Plant Vent' Monitor RE-24 -
5 5 5 5 5 R-2 Appendix 4 - Use of Containment Air Sample Data % Estimate Release Rate -
5 5 5 5 5 l R-2 Appendix 5 - Use of RCS Coolant Sample During S/G Tube Rupture Accident 5 5 5 5 5
- l. File Locations:
l T-1 = TSC-1 = Office Area File T-2 = TSC-2 = Operations Area File
,~ T-3 = TSC-3 = Computation Area File ,
E-1 = EOF-1 = ELRM Office File E-2 = EOF-2 = EARS Office File
)
e l ,
DC0118 73XI l \ . l l
. 1
PACIFIC GAS AND ELECTRIC CCMPANY CORPORATE EMERGENCY RESPONSE ptAN s
IMPLEMENT!NG PROCEDURE LIST Revision Date Title Number 02 07/14/83 Activation of the Corporate E=ergency 1.1 Response Organi:ation 02 07/15/83 Activation of the Corporate Incident 1.2 Response Center 2.1 02 07/25/83 Plan Maintenance Emergency Preparedness Training Program 2.2 01 01/13/84 3.1 02 07/29/83 Governmental Relations 03 08/25/83 Corporate Communications Department 3.2 02 07/29/83 Law 3.3 3.4 02 07/26/83 Insurance 3.5 02 07/22/83 Safety Health and Claims 3.6 02 07/20/83 Security 3.7 01 09/06/83 Personnel 4.1 02 07/25/83 Materials 4.2 02 07/14/83 Telecommunications 4.3 03 08/30/83 Radiological Analysis and Protection 4.4 02 08/05/83 General Construction 4.5 02 08/30/83 Engineering and Technical Support 4.6 02 09/16/83 Computer Systems and Services 03 07/29/83 Nuclear Plant Operations 4.7 4.8 02 07/28/83 Division Support 4.9 02 07/22/83 Quality Ass"*ance IP - i Revision 02.,07/15/83 Change 02,01/13/54 M e
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f IP - 11 Revision 02,07/15/83 Change 02, 10/12/83 4
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NUMBER: 2.2 PACIFIC GAS and ELECTRIC COMPANY g {:,9], CORPORATE EMERGENCY RESPONSE PLAN REVISION: 1 CATE: 01/13/SA O l!!
IMPLEMENTING PROCEDURE PAGE 01 0F 08
, TITLE f E."ERGENCY PREPARECNESS TRA!NING PROGRAM Y
SIGNATURE RESPONSIBILITY DATE TITLE PREPARED BY gg
/
SR. NUCLEAR GENERATION ENGINEER /
eueccr vv-et w .m REVIEWED AND .
CCNCURRED BY ,
fAM PEPflSIffG huCLEAR GENERATION ENGINEER
[ PERSONNEL &ENVIPCa. MENTAL $AFETY CCf U R D BY MANA R. NUCLE hLANTOPERATIONS APPROVED BY f VICE RESIDENT, NUCLEAR POWER GENERATION APPROVED BY _- M q ,/ / 7 h CHI!RMAN. PRESIDENT'S Nt$tIAR Ad/LS6RY/
COMMITTEE /
/
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....=>...
PACIFIC GAS and ELECTRIC COMPANY conPomATE EMERGENCY RESPONSE PLAN NUMBER' W REviSicN: 1 IMPLEMENTING PROCEDURE DATE: 01/13/84 TITLE EMERGENCY PREPAREDNESS TRAINING PROGRAM PAGE 02 0F 08 ORGANIZATION AL OUTLINE
- 1. SCOPE
- 11. DISCUSSION lit. RESPONSIBILITIES IV. INSTRUCTIONS V. REFERENCES VI. ATTACHMENTS 9
9 E
e
, 49 9
v ee ene is,esi nov en PACIFIC gas and ELECTRIC COMPANY -
Z' l CORPORATE EMERGENCY RESPONSE PLAN
""'S"
( IMPLEMENTING PROCEDURE I CATE: 01/13/84 EMERGENCY PREPAREDNESS TRAINING PROGRAM PAGE 03 0F 08 I, , SCOPE The scope of this Implementing Procedure is to describe the responsibilities and requirements for the Corporate Emercency Response Plan training program as required by 10CFR50.47(b)(15).
II. DISCUSSION A. General This Implementing Procedure provides instructions for the implementation of a coordinated annual training program for Corporate Emergency Respense Organi:ation (CERO) personnel with assignments under the Corcorate
_Emercency Response Plan (CERP). CERO training should be accompitsned in three pnases witn activities in both a classroom atmosphere and participation in drills and exercises.
B. Definitions of Terms
- 1. Training activity:
A training activity is the process by which the skills of individual personnel are improved and refined to meet or exceed prescribed qualification standards for the performance of their specified duties and responsibilities under the CERP.
- 2. Drill:
A drill is a supervised instruction period aimed at developing and maintaining required skills for a particular task / assignment.
- 3. Exercise:
An exercise is an event which tests a major portion of the basic elements within the CERP and demonstrates the capability of the CERO to respond to an emergency.
C. Corporate Emergency Response Organization Training Program
- 1. Program Description in order to maintain emergency preparedness training requirements as required by NRC regulation 10CFR50.47(b)(15), CERO personnel training may be accomplished in three training activity phases, as described below:
O 4
f OO 1
- s. u. ,...a> .a, ea PACIFIC gas and ELECTRIC COMPANY NUMBER *- 2.2 CORPORATE EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE DATE: 01/13/84 EMERGENCY PREPAREDNESS TRAINING PROGRAM PAGE 04 0F 08 Phase Activity Description I General introductory course to explain the purpose and function of the CERP in support of the Diablo Canyon Power Plant Emergency Plan.
!! Courses designed to provide CERO personnel with specific training instruction for executing assigned duties and responsibilities as identified in Procedure Attachment 1. "CERO Training Program Courses".
III Drills and exercises designed to provide CERO personnel with " hands on" experience using appropriate facilities, equipment, and procedures.
NOTE: CERO training, drills, and exercises will be conducted in coordination with DCPP training activities.
- 2. Program Objectives The training program objectives are to provide for the follwing types of training:
- a. Corporate emergency preparedness management training for those individuals assigned to perform the principal and alternate functions of the CERO Departmental / Functional Group Coordinators and Recovery Manager,
- b. Corporate emergency preparedness procedure training for those individuals assigned specific duties and responsibilities as identified in the implementing procedures,
- c. Corporate emergency preparedness refresher training courses for all emergency response personnel activated under the Corporate Emeroency Response Plan.
- 3. Program Requirements
- a. Initial training
- 1) General Office personnel should complete the courses designated for their assigned CERO emergency plan title (s) as specified in Procedure Attachment 2. "CERO Personnel Classroom Training Requirements" for each CERP Implementing Procedure..
1 l
t p .. .
es-eue ,, rem en es PACIFIC gas and ELECTRIC COMPANY CORPORATE EMERGENCY RESPONSE PLAN NUM8ER. 2.2 PGwE "E" S ' "
' IMPLEMENTING PROCEDURE CATE: 01/13/84 EMERGENCY PREPARECNESS TRAINING PROGRAM PAGE C5 0F C8
- 2) Non-General Office personnel may complete the required course training for their assigned CERO emergency plan title (s) as specified in Procedure Attachment 2, "CERO Personnel Classroom Training Requirements" by completing Procedure Attachment 3, " Certification of Self-Training Completion".
- b. Refresher training CERO personnel maintain their " trained on an annual basis" status by participating in either of the following activities:
- 1) Scheduled (announced or unnanounced) drills throughout the year, the Annual Emergency Preparedness Exercise Dress Rehearsal or Exercise; or
- 2) Applicable phase II training courses as specified in Procedure Attachment 2. "CERO Personnel Classroom Training Requirements".
- 3) Completion of Procedure Attachment 3. " Certification of Self-Training Completion", as requested.
D. Program Conduct & Documentation
- 1. CERO emergency preparedness training program will be conducted and coordinated with other Departments.
- 2. Training courses should be conducted in accordance with hPO Administrative Procedures.
- 3. Approved lesson plans for CERO training courses should be used in the conduct of all classroom training activities.
4 All CERO classroom' training activities should be documented with the following records: ,
- a. Attendance Records.
- b. Correlation of attendance with training requirements.
- c. Maintain status of training completed by individuals.
III. RESPONSIBILITIES Personnel with assigned responsibilities under this Procedure, as identified below by their non-emergency titles, should perform their assignad tasks as ,
detailed in the Procedure Instructions section below.
99 ,
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!Y. INSTRUCTIONS A. Supervising Nuclear Generation Engineer, Personnel and Environmental Safety
- 1. Schedule, coordinate, and implement specialized training programs to instruct and qualify those personnel responsible for implementing the Corporate Emergency Response Plan. The scope, nature, and frequency of snose programs snall ce specified for all CERO personnel.
- 2. Ensure that all drills are supervised and evaluated by a qualified drill instructor and that the basic objective (s) of each drill are met.
- 3. Ensure CERO participation in the scheduled monthly connunications drills between DCPP and the San Luis Obispo County Sheriff's Office, State Office of Emergency Services and NRC. Such participation shall range from:
- a. Limited alerting and notification of key CERO personnel and Departmental / Functional Group Coordinators; to
- b. Full connunications alerting / notification of all CERO personnel and possible activation of selected emergency response facilities.
B. Manager, Nuclear Plant Operations Department
- 1. Remain cognizant of Corporate emergency preparedness training i courses, drills, and exercises to ensure that effective and efficient interfaces between the Site and Corporate emergency response organizations will be maintained during an emergency.
I
- 2. Direct the Supervising Nuclear Generation Engineer, P&ES Section, to schedule, coordinate, and implement the CERP Training Program.
- 3. Ensure that critiques of Corporate emergency preparedness drills and exercises are conducted as soon as possible after their performance to ensure'that the emergency response actions of the various l Departments / Functional Groups within the Corporate Emergency Response Organization are properly evaluated, and any corrective action, if required, is implemented.
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( IMPLEMENTING PROCEDURE I OATE: 01/13/84 EMERGENCY PREPARE 0 NESS TRAINING PROGRAM PAGE 07 0F 08
, C. Vice President, Nuclear Power Generation Department
- 1. Provide overall coordi. nation of required emergency orsparedress training programs and drills for Company emergency response eersennel involved in any way with the Corporate Emergency Response Organization during an event requiring the activation of the Corporate Emergency Resoonse Plan.
D. Departmental /Functionai Group Coordinators
- 1. Participate in the applicable CERP Emergency Preparedness Training Program activities to maintain familiarity with the CERP, its Implementing Precedures, and the Nuclear Emergency Response Comunications Directory.
- 2. Ensure that respective CERO Departmental / Functional Group perscnnel participate in and maintain training requirements.
E. President's Nuclear Advisory Cemittee The President's Nuclear Advisory Comittee will oversee reouired emergency preparedness drills and exercises.
V. REFERENCES A. Diablo Canyon Power Plant Emergency Plan.
B. Corporate Emergency Response Plan.
C. Nuclear Power Generation Manual. Volume 3 " Nuclear Plant Operations Department Procedures Manual". Chapter II.
VI. ATTACHMENTS
- 1. CERO Training Program Courses.
- 2. CERO Personnel Classroom Training Requirements.
- 3. Certification *of Self-Training Ccmpletion.
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CERO Training Program Courses Training. Course Applictble Phase Number Course Title CERP IP I. Gecerel Emergency Preparedness Program Overview Course EPG-201 Corporate Emergency Response Plan and Diablo Canyon Power Pl ant Emergency Pl an 0ve rvi e" . . . . . . . . . . . . . . . . . . . . . ALL II. Departmental / Functional Group Courses EGP-210 Governmental Relations Dept. CERP IP Review.............. 3.1 EPG-215 Corporate Communications Dept. CERP IP Review 3.2 EPG-220 Law Dept. CERP IP Review................................. 3.3 EPG-225 Insurance Dept. CERP IP Review 3.4 EPG-230 Safety, Health, and Claims Dept. CERP IP Review.......... 3.5 EPG-235 Security Dept. CERP IP Review 3.6 EPG-240 Personnel Dept. CERP IP Review........................... 3.7 EPG-245 Materials Dept. CERP IP Review 4.1 EPG-250 Tel ecommunications Dept. CERP IP Revi ew. . . . . . . . . . . . . . . . . . 4.2 EPG-255 Radiological Analysis and Protection Group CERP IP Review 4.3 EPG-260 General Construction Dept. CERP IP Review. . . . . . . . . . . . . . . . 4.4 EPG-265 Engineering and Technical Support Group CERP IP Review 4.5 EPG-270 Computer Systems and Services Dept. CERP IP Review....... 4.6 EPG-275 Nuclear Plant Operations Dept. CERP IP Review 4.7 EPG-280 Divisi on Support Group CERP IP Revi ew. . . . . . . . . . . . . . . . . . . . 4.8 EPG-285 Quality Assurance Dept. CERP IP Review 4.9 EPG-290 CERO Management Personnel Responsibi11 ties. . . . . . . . . . . . . . . 1.1 Miccel-laneous Courses <
t EPG-202 SLO County Nuclear Power Plant Emergency Response Plan 0v e rv i ew . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . NO N E
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EMERGENCY PREPARECNESS TRAINING PROGRAM PAGE 01 0F 18 CERO Personnel Classroom Training Requirements
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- INSURANCE DEPARTMENT (CERP IP 3.4)*
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- TELECOMMUNICATIONS DEPARTMENT (CERP IP 4.2)*
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- RADIOLOGICAL ANALYSIS AND PROTECTION GROUP (CERP IP 4.3)*
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DATE: 01M84 EMERGENCY PREPAREDNESS TRAINING PROGRAM PAGE IB 0F 18 CERO Personnel Classroom Training Requirements
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CERP IP NUMEER: 2.2 REVISION: 1 ATTACHMENT: 3 DATE: 01/13/84 PAGE 01 0F 01 CERTIFICATION OF SELF-TRAINING CCMPLETION The Corporate Emergency Response Plan Implementing Procedure 2.2, " Emergency Preparedness Training Program" makes provision for personnel with responsibilities assigned to them in the Corporate Emergency Response Organi:ation to comply with the required training by certifying tnat they have:
- 1. Familiarized themselves with the " Nuclear Emergency Response Communications Directory" and its contents, and
- 2. Read their applicable CERP Implementing Procedure (s).
This " Certification of Self-Training Completion" is provided to document my ccmpletion of the above training requirements and that I have reviewed and understand the following CERP Implementing Procedures:
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CERP IP REVISION NUMBER CERP IMPLEMENTING PROCEDURE TITLE
_ NUMBER SIGNATURE DATE NAME (PRINTED)
CERO IITLE Return to T. A. Mack, Rm. 1403, 77 Beale St.
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