ML20069P517
| ML20069P517 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 11/03/1982 |
| From: | Thornberry R PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML16341B878 | List: |
| References | |
| PROC-821103-01, NUDOCS 8212080071 | |
| Download: ML20069P517 (55) | |
Text
..
CURRENT
N EMERGENCY PLAN IMPLEMENTING PROCEDURES j
TABLE OF CONTENTS l
j Volume 3A TITLE REV f
OP-O Reactor Trip With Safety Injection 3
OP-1 Loss of Coolant Accident 5
OP-2 Loss of Secondary Coolant 2
OP-3A Stena Gen Tube Failure 4
OP-3B Minor Steam Gen Tube Failure 1
OP-4 Loss of Electrical Power 3
OP-5 Reactor Trip Without Safety Injection 5
OP-6 Emergency Boration 5
OP-7 Loss of Condenser Vacuum 2
OP-8 Control Room Inaccessibility 5
OP-9 Loss of Reactor Coolant Pump 3
OP-10 Loss of Auxiliary Salt Water 2
OP-ll Loss of Component Cooling Water 2
OP-12 Malfunction of Auto Reactor Control 1
s System OP-12A Failure of a Control Bk to 2
Move in Auto OP-12B Cont Withdrawal of a Control Rod Bank 3
OP-12C Cont Insertion of a Control Rod Bank 2
OP-12D Control Rod Pos Indication Sys Malfune 3
OP-12E Control Rod Misalignment 2
OP-12F Dropped Control Rod 2
OP-13 Malfunction of Reactor Press Control System 2
OP-14 High Activity in Reactor Coolant 2
OP-16 Nuclear Instrumentation Malfunctions 3
OP-17 Malfunction of RHR System 2
OP-18A Loss of Charging 0
OP-18B Loss of Normal Letdown 0
OP-19 Malfunction of Reactor Makeup Control 2
OP-20 Excessive Reactor Coolant System 2
Leakage t
i t
8212080071 821202 PDR ADOCK 05000275 F
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-a TITLE REV OP-21 Loss of A Coolant Loop RTD 2
OP-22 Emergency Shutdown 1
OP-23 Natural Circulation of Reactor Coolant 2
OP-24 Loss of Containment Integrity 1
OP-25 Tank Ruptures 1
OP-26 Excessive Feedwater Flow 1
OP-27 Irradiated Fuel Damage 1
OP-28 Startup of an Inactive Reactor Coolant Loop 1
4 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
l OP-33 Loss of Instrument Air 1
OP-34 Generator Trip - Full Load Rejection 1
OP-35 Loss of Vital or Non-Vital Instr AC Sys 1
i OP-36 Turbine Trip 1
OP-37 Loss of Protection System Channel 1
OP-38 Anticipated Transient Without Trip (AIWT) 3 OP-39 RCP Locked Rotor Accident 1
OP-40 Accidental Depressurization of MS System 1
OP-41 Hydrogen " Explosion" Inside Containment 1
OP Gaseous Voids in the RCS 2
R-1 Per Injury (Rad Related) And/Or Overexp 8
R-2 Rel of Airborne Radioactive Materials 3
R-3 Rel of Radioactive Liquids 3
r R-4 High External Radiation 3
R-5 Radioactive Liquid Spill 3
O i
R-6 Radiological Fire 5
R-7 Transportation Accidents 2
M-1 Employee Injury (Nonradiological) 7 M-2 Injury to Nonemployee (Third Party) 6 M-3 Chlorine Release 5
M-4 Earthquake 6
M-5 Tsunami Warning 5
M-6 Nonradiological Fire 6
i M-7 011 Spill ISO and Clean Up Procedure 3
M-8 Containment Emergency Personnel Hatch 0
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TITLE REV G-1 Accident Classification and Em egency Plan 2
Activation G-2 Establishment of the On-Site Emergency 2
Organization G-3 Notification of Off-Site Organizations 1
G-4 Personnel Accountability and Assembly 2
G-5 Evacuation of Nonessential Site Personnel 0
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NUM8ER EP OP-18A 7.a G s,_-43 Pacific Gas and Electric Conipany REV1SiON 0 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DAM 10/11/82 DIABLO CANYON POWER PLANT UNIT NO'S) 1 AND 2 PAGE 1 OF 13 EMERGENCY OPERATING PROCEDURE hl TITLE: LOSS OF CHARGING APPROVED:
PLANT MANAGER %
DATE SCOPE This procedure provides instructions for loss of charging flow to the reactor coclant system due to charging pump trouble or charging line failure.
Section A Charging Pump Trouble - pg. 1 Section S Charging Line Failure - pg. 4 Section C Charging Line Failure on RHR - pg. 9 A.
CHARGING PUMP TROUBLE SYMPTOMS 1.
Charging Pump Trip (blue light) 2.
Charging header low pressure 3.
Charging header flow indicator, FI-128A (CC2) indicates low flow.
4 Possible Annunciator Alarms:
1 a.
RECIP CHARGING PUMP 13 (PK 04-16) 1)
Chargir.g pump trouble alams b.
CENTRIFUGAL CHARGING PUMP (PK 04-17,18) 1)
Charging pump trouble alams c.
LETDOWN PRESS /FLO TEMP (PK 04-21) 1)
Regen Hx Temps Hi I
l l
d.
RCP No.
(PK 05-1, 2, 3, & 4) i 1
1)
RCP Seal Wtr Flo Lo O
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1 AND 2 NUMBE P OP-18A OtA8LO CANYON POWER PLANT UMT NO(S)
DATE 10/11/82 PAGE 2 OF 13 LOSS OF CHARGING 7
e.
PZR LEVEL HI/LO CONTROL (PK 05-22) 1)
Pzr lo Lvl Charging Flo Demand f.
PZR LEVEL HI/LO (PK 05-21) 1)
PZR Lvl Lo From Ref.
VOLUME CONTROL TK PRESS /LVL TEMP (PK 04-24) g.
1)
Volume Cont TK Lvl Lo-Lo AUTOMATIC ACTION 1.
Letdown line isolation valve closes and pressurizer heaters trip on low pressurizer level (17%).
OBJECTIVES 1.
Return charging flow to RCS.
ACTIONS / EXPECTED RESPONSE RESPONSE t0T OBTAINED
(
l IMMEDIATE ACTIONS 1.
Start the standby 1.
Start any other charging pump.
available charging pump.
2.
Verify PZR level control in AUTO.
a.
Pressurizer Level a.
Place charging being (naintained or pump flow centrol returning to in the to MANUAL.
l prograinned band.
- 1) Increase charging ficw to return pressurizer level to the progracred bano.
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P OP-18A 1 AND 2 OLASLO CANYON POWER PLANT UNIT NO(S)
OATE 10/11/82 O'
PAGE 3 OF 13 LOSS OF CHARGING 7g ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED SUBSEQUENT ACTIONS 1.
Verify adequate RCP seal 1.
Adjust HCV 142 as water injection flow 6 necessary to provide to 8 gpm per RCP.
adequate seal water injection flow.
2.
Verify adequate VCT parameters being maintained in AUTO, a.
VCT LEVEL (14-87%)
b.
If level is <14%
b.
Take MANUAL verify Auto liiakeup control of occurring.
VCT makeup system to return VCT level to the prograntned band.
c.
VCT Pressure c.
If VCT pressure (18 to 65 psig) outside of band.
- 1) Open CVCS-8101 as necessary to return pressure to normal band.
- 2) Dispatch operator to VCT Room to verify H2 makeup is proper if pressure
<20 psig.
3.
Refer to Technical Specification, Sections 3.1.2.3, 3.1.2.4, 3.5.2 and 3.5.3 for charging pump operability i
requirements.
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1 AND 2 NUMBER EP OP-18A DIABLO CANYON POWER Pt. ANT UNIT NO(S)
REWS80N 0 DATE 10/11/82 LOSS OF CHARGING B.
CHARGING LINE FAILURE SYMPTOMS 1.
Possible charging Hi flow.
2.
Low charging header pressure.
3.
Charging header flow indicator, F1-128A (CC2) indicates low flow.
4.
Possible Annunciator Alarm:
a.
LETDOWN PRESS /FLO TEMP (PK 04-21) 1)
Regen HX Temps Hi b.
RCP No.
(PK 05-1, 2, 3, & 4) 1)
RCP Seal Wtr Flo Lo c.
PZR LEVEL HI/LO CONTROL (PK 05-22) 1)
Pzr Lo Lvl Charging Flo Demand d.
PZR LEVEL HI/LO (PK 05-21) 1)
PZR Lvl to From Ref.
e.
VOLUME CONTROL TK PRESS /LVL TEMP (PK 04-24) 1)
Volume Cont TK Lvl Lo-Lo f.
HIGH RADIATION (PK 11-21) 1)
Aux Bldg Rad Alarm 2)
Charging pp Rcom Rad Alarm AUTOMATIC ACTION 1.
Letoown line isolation valve closes and pressurizer heaters trip on low pressurizer level (17",).
2.
Possible charging pump suction swap from VCT to RWST (5".).
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OP-18A DIA81.0 CANYON POWER PLANT UNIT NCKS)
DATE 10/11/82 PAGE 5 OF 13 LOSS OF CHARGING OBJECTIVES 1.
Determine location of failure and isolate.
2.
Provide alternate charging path, if possible.
3.
Restore RCP seal water flow, if necessary.
4.
Restore RCS (Pressurizer) level.
5.
Restore Volume Control tank level.
ACTIONS / EXPECTED RESPONSE RESPONSE NOT OBTAINED IMMEDIATE. ACTIONS.
CAtJTION:
If at any time during the course of this procedure the reactor trips 60 TO EP OP-5.
1.
Verify the VCT makeup 1.
Place the reactor control system is in makeup system in AUTO AUTO.
and go to START on the Makeup Centrol Switch.
2.
CLOSE letdown orifice isolation valves CVCS 8149 A, B and C and letdown isolation valves LCV-459 and LCV-460.
l 3.
CLOSE CVCS-8146, nonnal charging line stop valve.
SUBSE0 VENT ACTIONS 1.
Monitor Pressurizer Level and pressure throughout the procedure.
a.
DECREASING OR STEADY a.
Continue with
- GO TO EP OP-20, Subsequent Excessive RCS Actions.
i Leakage.
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DATE 10/11/82 g
PAGE 6 OF 13 I y LOSS OF CHARGING ACTIONS / EXPECTED RESPONSE RESPCUSE NOT OBTAINED SUBSEQUENT ACTIONS CON'T 2.
Monitor Charging Header Pressure.
a.
Pressure returned to a.
Continue with no mal.
Subsequent Actions.
- 1) OPEN CVCS-8147
- 2) Reestablish letdown
- 3) GO TO STEP 7 of Subsequent Actions NOTE: Perform Step 3 and 4 simultaneously.
3.
CLOSE HCV-142.
4 Place charging pump flow 4.
If adequate flow to l
h control to MANUAL and each RCP cannot be reduce flow while maintained the leak is maintaining adequate upstream of HCV-142.
flow to each RCP seal.
Take the following steps:
a.
If centrifugal charging pump is operating swap to the reciprocating charging pump.
1
?
l b.
CLOSE FCV-128.
c.
If charging j
pressure and seal j
injection rate returns to nomal I
}
perfom the following steps:
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4 i
e 1 AND 2 NUMBER P OP-18A OtABLO CANYON PCNE PLANT UNIT NO(S) i DATE 10/11/82 PAGE.
7 OF 13 LOSS OF CHARGING ACTIONS /EXPECTdD RESPONSE
_ RESPONSE NOT OBTAINED SUBSE0 VENT ACTIONS Continued
- 1) OPEN HCV-142
- 2) OPEN CVCS-8146
- 3) CLOSE CVCS-8388 B, downstream isolation of FCV-128
- 4) Establish nonnal letdown
- 5) GO TO Step 7 of Subsequent D
Actions.
d.
If injection flow is not reestablished by perfoming the w
above steps "a" and "b", the leak is down stream of FCV-128. Perform the following steps:
- 1) STOP i
reciprocating charging pump.
- 2) Start one centrifugal
{
charging pump
- 3) Maintain FCV-128 in the closed position.
10TE:
It is necessary to establish communications between the kniliary IEiTding and the Control Room to coordinate charging operations for PZR level control through BIT Bypass, CVCS-8969 DCG072 711 l
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DATE 10/11/82 I
LOSS OF CHARGING 7,
ACTIONS / EXPECTED RESPONSE RESPONSE NOT OBTAlfE SUBSEQUENT ACTIONS Continued
- 4) Open Boron Injection Tank bypass valve (CVCS-8969) to establish a means of inventory control of Primary System coolant.
CAUTION: Excess letdown flow to the VCT through HCV-123 should be controlled slowly due to the effect on backpressure on the RCP seals.
- 5) Establish l
l excess letdown as required after pressurizer level is restored to at least 22%.
- 6) Since seal water to RCP was secured verify CCW to RCP Thermal Barrier and closely monitor RCP bearing temperatures.
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DATE 10/11/82 O
PAGE 9 OF 13 LOSS OF CH/.RGING ACTIONS /EX ECTED RESPONSE RESPONSE NOT OBTAINED SUBSE00ENT ACTIONS Continued 5.
Place Excess Letdown Heat exchanger in service as follows to control pressurizer level in programmed band:
a.
Check CVCS-8143 in a.
Place CVCS-8143 in NORMAL (return to NORMAL.
VCT).
b.
Open FCV-361 c.
Check HCV-123 CLOSED c.
CLOSE HCV-123 d.
OPEN CVCS-8166 and 8167 e.
SLOWLY Open HCV-123 f0TE: 00 NOT exceed 190*F as indicated in TI-122. Since there are no FLOW indicators, an increase in pressure and temperature indicates flow.
f.
Adjust HCV-123 as l
necessary for letdown flow, l
l 6.
Minimize lead changes and increase the I
frequency of the l
reactor coolant gross activity analyses to every 4 hou rs.
7.
Ensure the requirements of Technical Specifications 3.1.2.3 l
or 3.1.2.4 and/or 3.5.2 or 3.5.3 are satisfied.
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1 AND 2 NUMsE P OP-laA DIABLO CANYON POWER PLANT UNIT NO(S)
DATE 10/11/82 LOSS OF CHARGING ACTIONS /EX CTED RESRFSE RESPONSE NOT OBTAINED SUBSEQUENT ACTIONS Continued 8.
Refer to Emergency Procedure R-5, Radioactive Liquid Spill, to combat any uncontrolled radioactive leakage.
C.
CHARGING LINE FAILURE ON RHR SYMPTOMS 1.
Possible charging Hi flow.
2.
Low charging header pressure.
3.
Charging header flow indicator, FI-128A (CC2) indicates low flow.
4 Possible Annunciator Ala-ms:
a.
LETC0WN PRESS /FLO TEMP (PK 04-21) 1)
Regen HX Temps Hi b.
RCP No.
(PK 05-1, 2, 3, & 4) 1)
RCP Seal Wtr Flo Lo c.
PIR LEVEL HI/LO CONTROL (PK 05-22) 1)
Pzr to Lvl Charging Flo Demand d.
PZR LEVEL HI/LO (PK 05-21) 1)
PZR Lvl Lo From Ref.
e.
VOLUME CONTROL TK PRESS /LVL TEMP (PK 04-24) 1)
Volume Cont TK Lvl Lo-Lo DC0072 1CII 46 6**
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1 AN 2 P OP-18A DIABL.O CANYON POWER Pt. ANT UNIT NCKS) i DATE 10/11/82 PAGE 11OF 13
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LOSS OF CHARGING Tm l
AUTOMATIC ACTION 1.
Letdown line isolation valves close and pressurizer heaters trip on low pressurizer level (17%).
2.
Possible charging pump suction swap from VCT to RWST (5%).
OBJECTIVES 1.
Determine location of failure and isolate.
2.
Provide alternate charging path, if possible.
3.
Restore RCP seal water flow, if necessary.
4 Restore RCS (Pressurizer) level.
5.
Restore Volume Control Tank level.
ACTIONS / EXPECTED RESPONSE RESPONSE NOT OBTAINED IMMEDIATE ACTIONS 1.
CLOSE CVCS-8146, normal 1.
CLOSE CVCS-8107, charging line stop charging line valve.
penetration isolation valve.
2.
STOP all charging pumps that are running.
3.
CLOSE HCV-133, RHR letdown.
4 Shutdown any Reactor Coolant Pumps which are in operation.
SUBSEOUENT ACTIONS 1.
Monitor Pressurizer l
Level and RCS pressure.
a.
DECREASING - GO TO EP OP-20, Excess Se RCS Leakage
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DATE 10/11/82 PAGE 12 OF 13 l
l LOSS OF CHARGING ACTIONS / EXPECTED PESPONSE RESPONSE NOT OBTAINED SUBSEQUENT ACTIONS Continued b.
STEADY - Maintain RCS pressure with pressurizer heaters.
2.
Increase the frequency of the reactor coolant gross activity analysis to every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
3.
Ensure the requirements of Technical Specifications 3.1.2.1 and 3.5.3 are satisfied.
4.
Refer to Emergency Procedure R-5, Radioactive Liquid Spill, to combat any
{
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P OP-18A otAaLo CANYON POWER PLANT UNIT NO(S)
DATE 10/11/82 O
LOSS OF CHARGING 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 a Notification of Unusual Event. Notify plant staff and response organizations required for this classification by implementing Emergency Procedures G-2
" Establishment of the On-Site Emergency Organization" and G-3
" Notification of Off-Site Organizations" in accordance with Emergency Procedure G-2 " Accident Classification and Emergency Plan Activation."
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1 NuusER EP OP-18B P G F4IE Pacific Gas and Electric Company REVISION 0 O
m DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 10/8/82 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 OF 12 EMERGENCY OPERATING PROCEDURE TrTLE: LOSS OF NORMAL LETDOWN
[
APPROVED:
~
PLANT MANAGER g DATE SCOPE This procedure provides instructions for loss of normal letdown from the reactor coolant system due to inadvertent valve closure or letdown line failure.
Section A.
Valve Closure Due To PZR Level Channel Failure - pg 1 Section B.
Inadvertent Valve Closure - pg 3 Secticn C.
Letdown Line Failure - pg 4 Section D.
Letdown Line Failure On RHR - pg 8 A.
VALVE CLOSURE DUE TO PZR LEVEL CHANNEL FAILURE SYMPTOMS 1.
Pressurizer level channels do not agree.
2.
Volume control tank level decreasing.
3.
Charging flow indicator, FI-128A indicates high flow.
4.
Letdown flow indicator, FI-134A indicates low flow.
5.
Letdown pressure indicator PI-135 incicates icw pressure.
6.
Possible annunciator alanns:
a.
VOLUME CONTROL TK PRESS /LVL TEMP (PK 04-24) 1)
Volume Cont. TK Lo-Lo b.
PIR LEVEL HI/LO (PK 05-21) 1)
PZR Lvi Hi from Ref.
2)
PZR Lvl to from Ref.
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NUMBEs EP OP-188 OtA8LO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISON O DATE 10/8/82 PAGE 2 or 12 4
g TITLE:
LOSS OF NORMAL LETDOWN e
c.
PZR LEVEL HI/LO CONTROL (PK 05-22) 1)
PZR Lvl Backup Htrs OFF AUTOMATIC ACTIONS 1.
Charging pump speed increase or decrease.
2.
Automatic makeup initiates.
3.
Letdown line isolation valves close on low pressurizer level (17%).
4 Possible transfer of charging pump suction from the VCT to the RWST on VCT low level.
OBJECTIVE 1.
Restore letdown flow from RCS.
ACTIONS / EXPECTED RESPONSE RESPONSE NOT OBTAINED IFNEDIATE ACTIONS 1.
STOP Unit Load Changes 2.
Place pressurizer level master controller to Manual.
a.
Reduce charging flow to minimum.
SUBSE00ENT ACTION l
1.
Switch Eressurizer level control channel to an operable channel.
2.
Place PCV-135 in Manual and l
open to 70% (allow at least 30 l
i seconds for the valve to stoke open).
3.
Open letdown valves LCV-459 3.
GO TO SECTION C Letdown Line i
and/or LCV 460.
Failure Subsequent Actions l
Step 4 I
4 Open one 75 gpm letdown crifice valve.
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1 AND 2 DATE 10/8/82 O,
PAGE 3 OF 12 TITLE:
LOSS OF NORMAL LETDOWN ACTIONS / EXPECTED RESFONSE RESPONSE NOT OBTAlfED SUBSEQUENT ACTION CONTINUED 5.
Adjust PCV-135 manually to establish approximately 350 psig on PI-135 (VB2).
6.
Place PCV-135 in AUTO.
7.
Return the pressurizer level controller to AUTO and verify normal operation.
i 8.
If the level transmitter has i
failed refer to EP OP-37 for bistable trip direction.
8.
INADVERTENT VALVE CLOSURE SYMPTOMS 1.
Pressurizer level and RCS pressure increasing.
2.
Volume control tank level decreasing.
3.
Charging flow indicator, FI-128A indicates low flow.
4.
Letdown flow incicator, FI-134A indicates low flow.
5.
Letdown pressure indicator PI-135 indicates low pressure.
6.
Possible annunciator alarms:
a.
VOLUME CONTROL TK PRESS /LVL TEMP (PK 04-24)
I 1)
Volume Cont TK Lo-Lo b.
P7.R LEVEL HI/LO (PK 05-21) 1)
PZR Lvl Hi from Ref.
c.
PZR LEVEL HI/LO CONTROL (PK 05-22) j 1)
PZR Lvl Backup Htrs On i
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NUMBER P OP-188 otAs;.0 CANYON POWER Pt. ANT UNIT WS) 1 AND 2 DATE 10/8/82 I
I PAGE 4 OF 12 Tm.E:
LOSS OF fl0RMAL LETDOWN AUTOMATIC ACTIONS 1.
Charging pump speed decrease.
2.
Automatic makeup initiates.
3.
Letdown line isolation valves close on low pressurizer level (17%).
4 Possible transfer of charging pump suction from the VCT to the RWST on VCT low level.
OBJECTIVES 1.
Restore letdown flow from RCS.
ACTIONS / EXPECTED RESPONSE RESPONSE NOT OBTARED IKMEDIATE ACTIONS 1.
STOP Unit Lead Changes I
I SUBSE00ENT ACTIONS 1.
Attempt to reestablish letdown.
1.
GO TO SECTI0ft C, Letdown Line Failure, Subsequent Actions 2.
If letdown is reestablished no Step 4 additional action is required.
i C.
LETDOWN LINE FAILURE t
SYt1PTOMS 1.
Pressurizer Level and RCS pressure decreasing.
2.
Possible Hi Area Radiation Levels a)
Containment j
b)
Auxiliary Bldg.
c)
Charging Pump Room 3.
Letoown flow indicator, FI-134A, indicates abnonnal flow.
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DIABL,0 CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER P OP-18B O*
DATE 10/8/82 PAGE 5 Op 12 LOSS OF NORMAL LETDOWN nng:
4.
Volume control tank level decreasing.
5.
Possible annunciator alanns:
a.
LETDOWN PRESS /FLO TEMP (PK 04-21) 1)
Letdn Flo Hi 2)
Letdn HX Outlet Press Hi 3)
Letdn HX Outlet Temp Hi Divert 4)
Letdn Regen HX 1-1 Temp Hi 5)
Letdn HX Outlet Temp Hi b.
VOLUME CONTROL TK PRESS /LVL TEMP (PK 04-24) 1)
Volume Cont TK Lo-Lo c.
PZR LEVEL HI/LO (PK 05-21) 1)
PZR Lvl Lo from Ref.
d.
PZR LEVEL HI/LO CONTROL (PK 05-22) 1)
PZR Lo Lvl Letdn Iso All Htrs Off AUTOMATIC ACTIONS 1.
Charging pump speed increase.
I 2.
Automatic makeup initiates.
3.
'.etdown line isolation valve closes on low pressurizer level (17*,).
4.
Possible transfer of charging pump suction from the VCT to the RWST on VCT Icw level.
OBJECTIVES 1.
Isolate failure.
2.
Provide alternate letdown path.
l 3.
Restore RCS (pressurizer) level.
4.
Restore Volume Control Tank level.
t l
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TITLE:
LOSS OF NORMAL LETDOWN ACTIONS / EXPECTED RESRESE RESPONSE NOT OBTAltED IMMEDIATE ACTIONS CAUT UN:
If at any time during the course of this procecure the reactor trips, go to EP OP-5.
1.
STOP unit load changes.
2.
CLOSE tne latdown orifice isolation valves CVCS-8149 A, B, and C.
3.
CLOSE the RCS letdown valves LCV-459 and LCV-460.
4 Monitor Pressurizer Level a.
DECREASING OR STEADY a.
GO TO Subsequent Actions go to EP OP-20 Excessive RCS Leakage.
l l
SUBSEQUENT ACTIONS 1.
Place the charging pump flow control in MANUAL and reduce charging header flow to minimum.
2.
Close charging header isolation valves CVCS-8107 and CVCS-8108.
3.
Adjust charging flow as necessary to maintain adequate RCP seal injection flow.
l 4.
Establish excess letdown flow to the VCT as follows:
a.
Check divert valve CVCS 8143 in nonnal position (to seal water heat exchanger).
I I
DC0070 6III 1
DIAsLO CANYON POWER PLANT UNIT NO(S)
REVISION 0 DATE 10/8/82 iO' PAGE 7 OF 12 mts.
LOSS OF NORMAL LETDOWN SUBSE00ENT ACTIONS CONTINUED b.
Cut in component cooling water to heat exchanger by opening return valve FCV-361.
c.
Verify HCV-123 closed, then open excess letdown isolation valves CVCS-8166 and 8167.
d.
Slowly open HCV-123 to warm up heat exchanger. Do not exceed 190*F as indicated on TI-122.
NOTE: Since no flow detectors are located on this line, an increase in pressure and temperature indicates flow.
)
e.
Adjust HCV-123 as necessary for letdown flow requi rements.
NOTE: Excess letdown system is rated at approximately 20 UlWat nomal operating pressure.
5.
Verify pressurizer level in 5.
Adjust charging and excess i
programmed band.
letdown to maintain:
a.
Pressurizer Level b.
Adecuate RCP seal injection i
I 6.
Increase the frequency of gross activity analysis to every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
7.
Refer to Emergency Procedure R-5, Radioactive Liquid Spill, i
I to combat any uncontrollea i
radioactive leakage.
4 e
000070 71;I i
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N R
OP-18B oiAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 10/8/82 PAGE 8 OF 12 l
l TITLE.
LOSS OF NORMAL LETDOWN D.
LETDOWN LINE FAILURE WHILE ON RHR SYMPTOMS 1.
Pressurizer level and RCS Pressure Decreasing 2.
Possible Hi Area Radiation Levels a)
Containment b)
Auxiliary Bldg.
c)
Changing Pump Room 3.
Letdown Flow Indicator, FI-134A, Indicates Abnormal Flow 4
Volume Control Tank Level Decreasing 5.
Possible Annunciator Alarms:
a)
LETDOWN PRESS /FLO TEMP (PK 04-21) 1)
Letdn Flo Hi 2)
Letdn HX Outlet Press Hi 3)
Letdn HX Outlet Temp Hi Divert 4)
Letdn Regen Hx 1-1 Temp Hi 5)
Letdn HX Outlet Temp Hi b)
VOLUME CONTROL TK PRESS /LVL TEMP (PK 04-24) 1)
Volume Cont TK Lo-Lo c)
PZR LEVEL HI/LO (PK 05-21) 1)
PZR Lvl Lo from Ref.
d)
PZR LEVEL HI/LO CONTROL (PK 05-22) 1)
PZR Lo Lvl Letdn Iso All Htrs Off i
DC0070 8III i
_ _,. _ _ _, _. _ -. _.. ~ _ - _ - -
NUMBER EP OP-188 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0
(~%
DATE 10/8/82 tj PAGE 9 OF 12 Tine:
LOSS OF NORMAL LETDOWN AUTOMATIC ACTIONS 1.
Automatic makeup system initiates.
2.
Letdown line isolation valves close on low pressurizer level (17%).
3.
Possible transfer of charging pump suction from the VCT to the RWST on VCT low level.
OBJECTIVES 1.
Isolate failure.
2.
Provide alternate letdown path.
3.
Restore RCS (pressurizer) level.
4.
Restore Volume Control Tank level.
ACTIONS / EXPECTED RESPONSE RESPONSE NOT OBTAlfE IMMEDIATE ACTIONS 1.
CLOSE HCV-133 2.
Verify RCS inventory is being maintained.
a.
Pressurizer level-STEADY a.
GO TO EP OP-2C Excessive or INCREASING RCS Leakage I
b.
RCS Pressure - STEADY or b.
Same as a.
INCREASING c.
MODE 6 - Refueling Cavity c.
Same as a.
level - STEADY cr INCREASING i
C DC0070 91'I m.
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N R P OP-18B DIABLO CANYON POWER Pt. ANT UNIT NC(S) 1 AND 2 DATE 10/8/82 PAGE 10 of 12 l
)
TITLE LOSS OF NORMAL LETDOWN ACTIONS / EXPECTED RESPCNSE RESR)NSE f0T OBTAINED SUBSEOUENT ACTIONS 1.
Shutdown any RCPs which are in operation.
2.
Maintain adequate RCP seal barrier heat exchanger, injection flow until RCS temperature is less than 150*F.
a.
Establish Excess Letdown if needed to maintain RCS pressure of pressurizer level.
b.
Verify the reactor makeup system in AUTO Control.
3.
Shutdown the charging pumps unless needed to maintain RCS 4
I pressure as outlined in Step 4 below.
a.
If charging pumps are a.
Place the reactor makeup needed verify reactor control system in AUTO makeup control system is in AUTO.
- 1) GO TO START on the makeup Control switch 4
Maintain RCS Pressure as follows:
I a.
FCDE 6 with reactor vessel head off or detensioned.
- 1) Run charging pumps only as necessary to maintain refueling cavity level.
b.
RCS Solid (No Pressurizer Bubble)
- 1) Establish Excess I
Letdown I
f0TE:
See Section C, Subsequent Actions Step 4 3C0070 10111
1 i
NUMeE P OP-18B otAsLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 DATE 10/8/82 PAGE 11OF 12 Tm.E:
LOSS OF NORMAL LETDOWN ACTTONS/ EXPECTED RESFONSE RESPONSE NOT OBTAINED SUBSEQUENT ACTIONS CONTINUED
- 2) Run charging pumps as necessary 5.
Refer to Ernergency Procedure R-5, Radioactive Liquid Spill to combat any uncontrolled radioactive leakage.
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DC0070 11111 T----
t NuueER EP OP-18B DIASLO CANYON POWER PWff UNIT N0(S) 1 AND 2 REVuhON O DATE 10/8/82 PAGE 120F 12 Tr7LE:
LOSS OF NORMAL LETDOWN APPENDIX Z NOTIFICATION INSTRUCTIONS 1.
When this procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
Designate this event a Motification of Unusual Event. Notify a.
plant staff and response organi:ations requireo for this classification by implementing Emergency Procedures G-2
" Establishment of the On-Site Emergency Organization" and G-3
" Notification of Off-Site Organizations" in accordance with
.. Emergency Procedure G-2 " Accident Classification and Emergency Plan Activation."
O l
DC0070 12111 e+s a
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NUMBER EP R-1 F(BE6 Pacific Gas and Electric Company REVISION g
)
DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 10/5/82 DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 PAGE 1 OF 15 EMERGENCY PROCEDURE TnLE:
PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY huf RELATED) AND/0R OVEREXPOSURE APPROVED:
-)'
PLANT MANAGER g' DATE SCOPE This procedure describes the actions which are to be taken in the event of:
l 1.
Personnel injury or illness (minor or serious) where the victim is radiologically contaminated.
2.
Overexposure (or suspected overexposure) from an external source.
3.
Overexposure (or suspected overexposure) from an internal source.
4.
A combination of the above.
l Injuries or illnesses which do not involve radioactive contamination or overexposure are handled in accordance with Emergency Procedures M-1 or M-2.
DISCUSS!ON
[ Any radiologically related injury or illness or potential radiaticn overexposure is a serious matter requiring prompt attention to the care of the patient and prompt appropriate corrective action to preclude re-occurrence.
In addition, followup investigation to quantify the extent of exposure to radiation requires care in the gathering and retention of samples, radiation readings and other evidence which may contribute to the understanding of the incident and assist both in care of the injured and in preventing re-occurrence.
IMMEDIATE ACTIONS 1.
The employee (s) who are at the scene shall:
a.
Render all necessary first aid.
b.
Notify the control room (Shift Foreman) as soon as practical, and provide a phone number for the patients I
location.
2.
Shift Foreman (Interim Site Emergency Coordinator) r0907 IV
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NL R
P R-1 OtABLO CANYON PCWER PLANT UNIT NO(S) 1 AND 2 d
DATE 10/5/82 PAGE 2 cy:
15 Tn1E:
PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/OR OVEREXPOSURE 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 first aid personnel.,such as the project construction EMT h.
jj to the scene of the injury or illness if required.
c.
jiotify Chemistry a.nd Radiation Protection personnel (ext.
L~.
a*
d.
Call an ambulance if the injury warrants it. Refer to Appendix 1 " Measures to be taken if Medical Care Is Required" for instructions.
SUBSEQUENT ACTIONS The Shift Foreman shall direct all subsequent actions until relieved by the long-term Site Emergency Coordinator if the situation warrants it.
1.
Actions Common to All Occurrences a.
Transport the patient to the first aid room, provided that this can be done without aggravating the injury, i
i b.
Take actions as specified in the following sections as appropriate for the particular occurrence.
Section 2: Minor injury when contamination is present.
Scction 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 Hotification 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.
AY7 t
DC0007 2V l
1
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i
NUMBER P R-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 O
DATE 10/5/82
(_/
PAGE 3 OF 15 TITLE:
PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/0R OVEREXPOSURE e.
Begin gathering infomation to assist the long-tem Site Emergency Radiological Advisor in his evaluation. Guidance on things which should be irvestigated is given in Appendix 2 " Factors to Consider in Making a Preliminary Evaluation."
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)
Fom 62-4587 " Report of Industrial Injury to Employee."
3)
Fom 62-4586 " Employers' Report of Occupational Injury or Illness."
4)
Nuclear Plant Problem Report.
(SeeNuclearPlant Administrative Procedure C-12.)
WTE: Reports to NRC and the Nuclear Plant Problem Report i
are not required for minor injuries or illness for which O
onsite first aid and decontamination is adequate.
I 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" Fom (Fom 69-9392).
1)
The wound prior to decontamination.
2)
The object causing the injury (if possible) ano any clothing penetrating or touching the injury. These items should be retained, if possible, until the long-tem Site Emergency Radiological Advisor has I
completed his evaluation so that detailed radionuclide j
analysis can be performed, if required.
3)
The wound during each decontamination and aftar final decontamination.
WTE: These personnel surveys are in addition to other radiological surveys (e.g., work area, equipment) which may be required by radiation protection management.
O CCC007 3V l
i
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e NUMBER EP R-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 8 DATE 10/5/82 I
Il PAGE 4 0F 15 TITLE:
PERSONNEL INJURY OR ILLNESS-(RADI0 LOGICALLY RELATED) AND/OR OVEREXPOSURE f
1 b.
Decontaminate the wound 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 1
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 RS-5 " Personnel UeH ntamination" in the event normal decontamination e
facilities are overloaded or unavailable.
c.
Complete any additional first aid measures, 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 na medical attention (beyond first aid) is required and that no lost time occurs.
If lost time beycnd the day of injury is likely, or if medical treatment (including doctor referral)
I I
is required, complete Form 62-4586, " Employers' Report of Occupational Injury of Illness" and foiward to plant clerk.
I 3.
Serious Injury or Illness When Contamination is Present l
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 patier.t 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 l
decontamination.
a.
Call San Luis Ambulance and French Hospital and have the patient transported to French Hospital. The detailed steps to be takan 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 l
l ambulance.
b.
During the interval until the ambulance arrives keep the l
i patient as comfortable as possible. Survey and decontami, ate the patient to the extent that time and conditions permit. Do not decontaminate the patient if it will aggravate his injury. Recoro survey resuits en the
" Skin and Clotning Decontamination" Fom (Fom 69-9392.)
)
OC0007 4V l
i
NUMER P R-1 D:AaLO CANYON POWER PLANT UNE NO(S) 1 AND 2 DATE 10/5/82 p
PAGE 5 OF 15 inug:
PERSONNEL INJURY OR ILLNESS (RAD 10 LOGICALLY RELATED) AND/0R OVEREXPOSURE 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-tem Site Emergency radiological Advisor has completed his evaluation so that detailed radionuclide analyses can be performed, if required.
3)
Decontaminate the patient using the standard procedures discussed in Raalation Control Proceduro G-4 In cases of severe contamination, where there is a realistic l
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.
WTE: Refer to Emergency Procedure RB-5 " Personnel Ue' contamination" in the event nomal decontamination Ci 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 team dispatched to th,e 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 applicable limit contained in Radiation Centrol Standard No. 1, and where the individual does not require promat medical attention for any other reason. Personnel suspected of overexposure shall net re-enter radiation controlled areas unless authorized by the Site Emergency Coordinator.
a.
Provide any first aid or medical attention which the patient i
may required.
I 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:
4 i!O U
i DC0007 EV i
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fPR-1 N
R OtA8LO CANYON POWER PLANT UNIT NCKS) 1 AND 2 DATE 10/5/82
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PAGE 6 OF 15 Tm.E:
PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/0R OVEREXPOSURE 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 feming organs, lens of eyes, gonads, head or trunk.
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 shows 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 warmth and itching.
Redness, blistering and other effects may not appear
{
}
for several days.
c.
If the patient requires transportation tc the hospital, during the interval until the ambulance arrives keep the patient comfortable. Survey the individual and perfom any decontamination which circumstances require and/or permit.
Do not aggravate any injury or unduly alarm the patient in perfoming these operations. Record survey results on tne
" Skin anc Clothing Decontamination" Fom (Fom 69-9392) and/or " Radiation Dose Rate Survey Record" (Form 69-9316).
In cases of severe contamination, handle as in Step 3.c to ihe extent practical.
d.
To the extent practical, save all vcmit, urine, feces or other samples which may assist the long-tem Site Emergency l
Radiological Advisor in evaluating the accident. This is l
i particularly important if internal deposition of raoicactive l
materials is suspected.
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.
I DC0007 6V
DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 RE p(j DATE 10/5/82 PAGE 7 OF 15 TrTLE:
PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/0R OVEREXPOSURE f.
Subsequent actions will be based upon the results of the evaluation of the external exposure.
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 nomal (40 hr.) maximum pemissible concentration, and PF refers to the protection factor the patient obtained 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 ard 4 above). The treatment of these effects should take precedence over the evaluation of internal exposure, p
b.
Remove and retain fcr subsecuent radiological analysis the Q
patient's clothing and respirator, c.
Survey the patient thoroughly and record the results on the
" Skin and Clothing Decontamination" Form (Form 69-9392).
l d.
Decontaminate individual to as low as practical without I
causing further injury.
If practical, save samples of the decontamination solutions, swabs, and other materials which may be of use in subsequent radiological evaluations.
e.
Count the patient on the whole body counter. The results of this analysis will, in large measure, detemine the necessity for further medical attention or surveillance.
f.
Collect and save any urine, feces, or vomit which is passed from the patient. The long-tem Site Emergency Radiological Advisor may request that special urine samples be collected for bioassay.
g.
Subsequent actions will be based upon the results of the evaluation of the internal exposure.
h.
If the patient is sent to the hospital, make arrancements to have all urine, feces or vomit samples retaineo for radiolcgical analysis.
lO G
DC0007 7V
- L-
fPR-1 DIA8LO CANYON POWER PLANT UNC NO(S) 1 AND 2 DATE 10/5/82 PAGE 8 OF 15 TntE:
PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/0R OVEREXPOSURE REFERENCES 1.
Radiation Centrol 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."
I I
9.
Emergency Procedure G-2, " Establishment of the Onsite Evergency Organization."
- 10. Emergency Procedure G-3, " Notification of Offsite Organizations."
- 11. Emergency Procedure R-4, "High Radiation (In Plant).
- 12. Emergency Procedure RB-5, " Personnel Decontamination."
l
- 13. Emergency Procedure OR-1, "Offsite Support and Assistance" l
ATTACHMENTS l
1.
Form 69-9221 " Emergency Notification Record."
2.
Form 69-9316 " Radiation Dose Rate Survey Record."
3.
Forn 69-9392, " Skin and Clothing Decontamination."
l 4.
Form 62-4587, " Report of Industrial injury to Employee."
l DCC007 8V i
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N R
R-1 otAsto CANYCN POWER PLANT UNIT NO(S) 1 AND 2 p
DATE 10/5/82 PAGE 9 OF 15 d
v TITLE.
PERSONNEL' INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/0R OVEREXPOSURE g
5.
Fom 62-4586, " Employers' Report of Occupational Injury or Illness."
6.
Fom 62-6015. " Medical Referral."
7.
Light Duty Program Letter.
G.
Safety, Health and Claims Personnel to Be Contacted for Reporting of Injuries at Diablo Canyon (6/81).
l 1
l l
l I
A t-DC0007 9V
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f 1. 4 NNER EP R-1 otAato cANYCN POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISION 8 DATE 10/5/82 PAGE 1@F 15 g
PERSONNEL INJdRY OR ILLNESS (RADI0 LOGICALLY RELATG' l
Tm.
AND/0R OVEREXPOSURE APPENDIX 1 1
APPENDIX 1 MEASURES T'O BE TAKEN IF MECICAL CARE IS REQUIRED The following are the procedural steps to be taken in the event a contaminated patient must he transported to the hospital fo'r medical treatment:
1.
Call San Luis Ambuiance (Phone.,
f,'and provide the fallowing information:
a.
Name of caller.
b.
Company affiliation.
Phone numbar of caller. (Where he can be reached.)
c.
r d.
Name of injured or. ill person, i
e.
Where the patient is located.
f.
Where the patiert is to be transported (French Hospital).
g.
Nature of injury or illness.
s bi h.
Patient'is contaminated.
i.
Any other medical infortra' tion which might be pertinent to transporting the patient.,
)
j Record this information on FrYm 69-9221. " Emergency Notification 4
f Record," or other suitable log.
i
/
,(
r.
Contact the Security Shift Supervisor g
]'andhavehimcall
?
,j<
thesecurityforceatthePortSanLuisentrance{lso] advisable and t
alert them that the ambulance is entering.
It is a to have an escort accompany therambulance from the Securfty
,i Building to the first aid room to minimize the delay in reachicg the destination.
a 3.
_The victim shall be transported to French nce 0.1.
Call ahead s
to the hospital (Phone 1 and prgvide t.ne following l'
in fotr.at' ion :
a.
Name of caller, lA OC0007 10V l
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.. _..l "uumE P R-1 DIAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 g
DATE 10/5/82 PAGE IDF 15 t/
PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED:
AND/OR OVEREXPOSURE APPENDIX 1 APPENDIX 1 (Cont'd)
MEASURES TO BE TAKEN IF MEDICAL CARE IS REQUIRED b.
Company affiliation, c.
Phone number of caller.
(Where he can be reached.)
d.
Name of injured 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.
Record this infornetion on Form 69-9221, " Emergency Notification l
Record", or other suitable log.
4 Prior to arrival of the ambulance, the patient should 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 NOTE: Two hospital kits and radios are storea in Access Control.
Additional equipment and radios are also available at the PG&E San Luis Obispos Service Center.
l 7.
Two additional 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, d
DC0007 IIV s.
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4 NUMBER EP R-1 OtA84.0 CANYON POWER Pt. ANT UNff NO(S) 1 AND 2 REVISION 8 DATE 10/5/82 m
1&
15 I
I PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED)
Tins:
AND/0R OVEREXPOSURE APPENDIX 2 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 tnis 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 Common to All Accidents a.
Date, time of occurrence.
b.
Basic reconstruction of events.
c.
Probable source (s) of radioactivity involved.
{
h d.
Names and addresses of all' witnesses.
2.
Considerations in Evaluating External Exposure a.
Exactly 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.)
t.
Exactly what was the time interval over which exposure occurred?
I DC0007 1EIV
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NUMBER EP R-1 OLASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 8 OATE 10/5/82 PAGE IDF 15 PERSONNEL INJURY OR ILLNESS (RADIOLOGICALLY RELATED:
TITLE:
AND/OR OVEREXPOSURE APPENDIX 2 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 l
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?
i b.
Exactly what was the time irterval over which exposure occurred?
c.
Can sample (s) of liquids which were internally deposited be l
obtained?
O d.
Can samples of airberne activity which were breathed be b
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, decontanination i
solutions, secretions, respirator filters, be saved?
l g.
Can the region in the vicinity of the occurrence be l
smear-tested, or can decontamination solutions be retained?
1 l
1 DC000
131V l
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R P R-1 DIABLO CANYON POWER PUNT UNIT NCKS) 1 AND 2 DATE 10/5/82 PAGE l'DF 15
(
)
PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) m LE:
AND/OR OVEREXPOSURE APPENDIX Z APPENDIX Z l
EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS i
1.
When this emergency procedure has been activated and upon
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direction from the Shift Foreman, proceed as follows:
I 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 event a significant event in a case of overexposure from an external source wnere the exposure (for the quarter) exceeds the following-5 Rem Whole Body 30 Ren Skin of Whole Body 75 Rem Extremities Notify the NRC Bethesda Operations Center using the red phone in the Control Room as a minimum within one hour.
Gather sufficient information frcm all sources prior to calling so that the phone call is meaningful. Refer to Operating Procedure 0-4 " Operating Order (One Hour Reporting Requirements to NRC)" for a suggested format for reporting.
Notify the NRC that your call is pursuant to 10CFR50.72 (Notification of Significant Events).
Notify the Directo.*, NRC Region 5, by telephone and telegraph, mailgram or facsimile within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the event.
Indicate the notification is pursuant to 10CFR20.403 (Notification of Incidents).
i Designate this a Notification of Unusual Event in any case i
c.
of an injury or overexposure requiring transportation of the patient to an offsite hospital or if extensive onsite decontamination is required (soap and water washings do not I
remove contamination or offsite decontamination assistance is required). Notify plant staff and response organizations required for this classification by implementing Emergency Procedures G-2 " Establishment of the Onsite Emergency Organization" and G-3 " Notification of Offsite Ornanizations" in accordance with Emergency Procedure G-1
" Accident Classification and Emergency Plan Activation."
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R P R-1 DIAsto CANYCN POWER PLANT UNIT NO(S) 1 AND 2 9
OATE 10/5/82 PAGE IBF 15 PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED)
TITLE:
AND/0R OVEREXPOSURE APPENDIX Z d.
In addition to the notifications performed under "c." above, for a Notification of Unusual Event, if the case involves an overexposure from an external source which exceeds:
25 Rem Whole Body 150 Rem Skin 375 Rem Extremities imediately not1fy the Director, NRC Region 5 by telephone and telegraph, mailgram and facsimile.
Indicate the notification is pursuant to 10 CFR20.403 (Notification of Incidents).
2.
In addition to notification performed above, also notify the following in any case where NRL notification is required.. -
a.
Supervising Nuclear Generation Engineer (Personnel and Environmental Safety) or his alternate in the Department of Nuclear Plant Operations:
Mr. W. H. Fujimoto PGandE:
Plant Ext.:
Home:
b.
Compensation Claims Representative in the Department of Safety. Health and Claims, per the att&ched list of personnel.
NOTE:
- 1) The System Dispatcher will handle the notification of General Office Personnel if they cannot be promptly reached.
') Nuclear Mutual Limited (NHL) holas the Company liability and property damage insurance for Company personnel and property. They should be i
notified under the same circumstances as the NRC.
Notification is made by the Company's Insurance Department. The Departm'ent of Nuclear Plant Operations should be requested to interface between the plant and the Insurance Department when required. American Nuclear Insurers / Mutual I
Atomic Ener';y Liebility Underwriters (ANI/MAELU) i holds third party insurance coverage and would be similarly notified in accidents involving a third i
party.
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DEPARTMEtii 0F NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT l
RADIATION DOSE RATE SURVEY RECCRD tiATE TIME SWP/RWP NO SURVEY NO.
AREA OR EQUIPMENT TYPE OF SURVEY 11:EET OF -
ITEM DESCRIPTION NO.
m rad /hridistance mR/hr' distanceirem/hr i distance O
SURVEYED BY SURVEY TYPE INSTRUMENT TYPE DETECTOR SERIAL NO.
DATE CALIB. DUE i-BETA j,
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SURVEY REVIEWED DATe SUFIRVIEN
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DIABLO CANYON POWER PLANT SKIH AND CLOTHING DECONTAMlHATION i
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82-48a7 Rev. Ins PACIFIC GAS AND ELECTRIC COMPANY Report of Industrial injury to Employee 1.
Name 6.
Division 2.
Address ZIP 3.
Telephone No.
7.
Department 4.
Social Security No.
8.
Date of Accident 5.
Occupation 9.
Time of Accident
- 10. Location of Accident
- 11. Nature of injury
- 12. What were you doing and how did accident occur?
- 13. Describe First Aid rendered:
- 14. Witnesses to accident:
1.
2.
3.
15.
Signatureof Employee
- 16. Date injury reported:
- 17. Date 30 days elapses:
? S.
- See Over Signature of Spervisor l
INSTRUCTIONS: This report (Items 1 thru 15) should be written and signed by the amployee person-a//y and countersigned by the supervisor. It is for all industrial Injuries and is in duplicate. The original is to be retained for Company records: the copy is to be detached after completion and given to the employee. Before signing in item 18, the supervisor should fill in the date of the report (Item 16) and compute and notate the date 30 days from the date the injury was reported (ltem 17).
If the employee later requires treatment by a doctor or becomes disabled, Form 62-4586 must be preparea and forwarded to the Safety, Health and Claims Decertment /MMEDIATELY accompanied by the original of this report.
I If the employee is unable to fill out or sign this report, it should be prepared, signed by the supervisor and the employee should be given a copy withiri 5 days as required by law.
If the injured employee cannot write English, the report may be made according to a verbal statement.
If necessary, the employee may sign by a mark and a witness to the report should sign below the em.
playee's mark.
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If you weh to amareas your rights ander iten gli of the infonnessen susseen, passes superses this seen.
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.d e-. y r - d phy 5 9788. Du.$as of the Emoseven Seeeased Pnysselen.The envecian or fesulty chosen try the empeeves uno uneartene to provide tresonant pureumat to L.aeor Code Seedon 4000 eness:
tel vnenin 3 werting devs eher undershing to provuse asen trustment nedfy the amosever of tne name and eserums of seen trusting anyelemn or feelsty and tal witari 5 working deys fono nne inities esammenon snel semana a wrttien reoart to tne om.
osover 3 inctuse:
(11 The name and meereas of injured emosoyee:
(2) The emosoyee's messent history a censined by the anyelaar:
(3) Findings on eserninerten:
(48 The mariesthe osmo 6asmo resorted Ipy the emseeves:
(El The peonned coures,seems and duruden of treatmet.
(el if oosroortste, the asetmammd reeurnwt dese:
(7) An opinion se to venetner ressmuss permanent diesellity is :o w anttoostas end, if poestde,en estimese of its enesnt:
El An oo4 neon en to whether the emotoves wall eventumly tse nose to engage in the oesume-tien hang performed et the time of injury.
(e) At rummonesee laturgens asuring native trustment matsmet proyese reporte to the enesever and, petsautetty.regert prernetty to the emseeyer iunent (11 The emeloves's concitten permets resurn to usert:
(2) The emeesven's eenedtten reeuire hern or her to leave vuort:
I (3) Hemmetesimalen er margery la andlemand orreemmmenced:
(41 The emotoyee's conettien bemomes permanent and stationary; (5) The emoseves's conditten undergoes e oroviouey enemoscted s6en(ficeret charige:(this resery snest common a statement of the prossend oeures of trustment resusred.if my, try that enagel;
($1 The emodeves is referred to another phyelesen for annes#enteen:
(7) The omoneyse rummennety requests essNttensi soproertete informeHen.
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PACIPiC GAS and El.ECThiC COMPANY Employer's Report of Occupational Irtpry or itiness CONFIDENTIAL-for use av Comoany Attornevs oivision G8feeRAL OP*ics om G8pegmAL ConsTSUCTIOed o...
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... No resort of inpery reguared to tuo flted lyy en err >
Te peove or nsurer av en.s esoimr meal tus _. -
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Date
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D r.
Kindiv give to bearer, Mr.lMs.
medical attention, and forward a complete detailed report immedi-ately to Manager, Safety. Health and Caims Dept. 245 Market Street, San. Francisco,94106. Your bills should be itemized and all bills and reports rendered in triplicate.
PACIFIC GAS AND ELECTRIC COMPANY By l*C" l
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'*** - Sat-PLEASE COMPLETE AND RETURN TO EMPLOYEE (EMPt,0YEE MUST HAVE COMPLETED CARO TO RETURN TO WORKl Pacific Gas and Electric Co.:
Date
,19 _
Mr./Ms.
Occupation Report e Employed By l **
- I Division.
Injured at
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,19 C Return to full work inwnediassey C Modified work until C Unab6e to work unal l
C Resencoons or finnemiens C Renarn Aset.
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Tiene:
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Tnank ycu for :eing cne of cur panel hysicians tha : ta: Our emcicytes.
Cur ;ricary g:a1 is to provida emolcyees wnc susuin incustrial injurdas
---recuiring mecical attan icn wita pre. :, first-class - ta= ant. Ycur assis.anca in :nts encaavor is a:;rtef atad.
Thers is an area of c:ncarn a us. 'Jhile the nummer of em:1cyees ca:
ascuire : tacant by a :nysician ras remained suele or in scue :asas caciir.sc, :32 nu::er of ::sa: ling inj 4 ries esquirir.; : ma away f :=.vcrt, i.e., ics: time injuries, has cramatically inc tasec.
He believe nat s:me cf =is time away from wort sign: ;cssibly be avoidad if :ne availabill:y of lign: (medified) duty or dask-type wort wert ecre Some pnysicians have s atad :nat in some cares the patient widsly known.
will res:ene more rapidly to t-satment if kect busy in a light-duty cacacity.
P-cuc--;ve, lignt-cuty assigrannts are almes always availa:Te for a=1cyass released f:r acrx witnin :he macical restricticas estaclisnad by the physician.
It our :alicy to have an injured ammicyee ac:=meanied by a sucarviser er c:nse roerssantative on Os firs: cec.:r's visit. Sheule taart be any :ur.s-
- n a:cu: ce availaoili:y cr :y:e of lign: cu:y ca: un :n pr:vi:ac,.
i or sne will be acts to ans-er fer us.
Cur emolayees' welfart is our main c:ncarn. Sheuld you nave any cuestiens a:cu: cur p-= gram I will be glac :n call on ycu a your c:nvenienca.
Si ncerely.
R. C. THORNSEKEY l
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6/82 PACIFIC GAS AND ELECTRIC COMPANY Page 1 of 2 1
DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2
~
Safety, Health and Claims Personnel to be 3
Contacted for Reporting of injuries at Diablo Canyon EMPLOYEE INJURIES In all cases of serious employee injuries (for example, injuries involving hospitalization, electric contact, hernia, amputation, fractures, or injuries expected to result in lost time from work beyond the day of injury) or death, which occur while on the job, report should be made as follows:
During Working Hours:
~1 T. B. Honey PGandE local g
(If flr. Honey is not available, the person answering tne telephene will take the message and notify Mr. Honey or any other parties necessary in the Safety, Health anc Claims Department).
Any Other Time:
Report to one of the persons on the following list, trying each in order until one is contacted:
1.
T. B. Honey 2.
C. B. Powell 3.
P. S. Benitez 4.
T. G. Scott j
5.
A. Thomas 6.
L. Lasagn-7.
C. W. Allen 8.
S. L. Wade 9.
J. A. Glimme 10.
J. C. Vocke 11.
W. A. Hutchison 12.
M. C. Dolan l
13.
A. L. Bechtold l
14.
M. W. Johnson 15.
R. W. Hall 1
l' I
16.
I. M. Crawford 17.
R. G. Schumaker l
18.
R. D. Fagg
,I 19.
P. C. Boettcher l
20.
H. W. Reynolds t
21.
B. P. Sadler L
]
IThis listing extracted from Safety, Health, and Claims memo regarding Personnel to be Contacted for Repcrting of Accidents, dated 4/19/82.
'.4 OCCC07 161V
Safety, Fralth and Claims Personnel to b2 Contacted for Reporting of Injuries at Diablo Canyon Page 2 of 2
\\
aqp Non-Empicyee Injuries C. O. Schreil, San Luis Obispo,p_.
office)
. (office)
(home)
If he cannot be reached, contact one of the following in order of preference:
Ouring working hours:
~l 1.
John C. Echols 2.
Doug G. Keeler 3.
George G. Perry (collection only)
_j Af ter working hours on Monday through.8:00 a.m. on Friday, except holidays:
1.
John C. Echols 2.
Doug G. Keeler 3.
John C. Vocke 4.
Amos L. Bechtold i
i 5.
William H. Bingaman l
6.
E. Anthony Giudici 7.
J. Alex McCorquodale i
8.
Bruce P. Sadler I
9.
George G. Perry I
(collecticn only) 10.
Stanley W. Jchnston
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Af ter 5:00 p.m. on Fridays to 8:00 a.m. on Mondays and holidays:
Contact the Investigator delegated to stay on call for all emergencies. He may be reached through the System Dispatcher.
If he is not available, the Dispatcher will follow the procedures for "After Working Hours."
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P'ROCEDURE ON-TliE-SPOT CHANGE
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EP M-7 Re.,. _. _ 3 ur a t.o. i O 2O iaa u Procedure Peo.
OIL SPILL ISOLATION & CLEANUP PROCEDURE m
Type of Crmgo @ PERMAt<NT (green >
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ong,nsio, Proposed Change: (Does this SAet the rNent of orignal procedure?
Yes U No)
(Ooas* it constitute an unreviewed safety /envircreental question? Q TE3 G NO)
CHANGE HOME _ PHONE NUMBE,R FOR MR. DAVID J. WILLIAMSON, P.G.&E. LAW DEPT. TO,L
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SEE SUBSEQUENT ACTION SECTION 1.b.5 5
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Authorua.ons:
'(ganagernent Starr)
(Plant (anagemers Staff w/SAO Ucensel Date
- Innediate distributtor' to the Contml Room and affected wort areas required? O YES O NO Initydist ion By:
Distributed To: Qll Control Roca K2 others SFM Office
/,, e Date Received by Docurert Control
[b PSAC Revww end Plant Managers approval no later than Este above 'pfus 14 days Reyww Dans
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69 9018 Rev. 11/81 (200)
Page 1 of 1
~ ~ ~ l DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: NEW/ REVISED / RESCINDED OFFICIAL PROCEDURE INSTRUCTION SHEET TO:
_For Plant Manual Copy No:
Date: I l(e fb 8
Responsiole Person NEWPROCEDUE Proc No.
Rev No.
Vol No.
Section Proc No.
Rev No.
Vol No.
Section
)
l.
Insert the attached new procedure into the designated volume.
2.
Enter the procedure title and revision on the Table on Contents.
3.
Sign and return this instruction sheet as soon as you have completed above.
REVISED PROCEDURE Proc No.
Rev No.
Vol N3.
Section Proc No.
Pev 90.
Vol No.
Section O
1.
Insert the attached revised procedure into the desionated volume.
2.
Remove and return the out-of-date procedure and 6ay ca-the-spot procedure changes essociated with the procedure.
Update the revision Gr ey on the Table of Contents.
3.
Sign and return this instruction sheet as soon as you have completed above.
4 RESCINDED PROCEDURE Proc No. Rev No.
Vol No.
Section Proc No.
Rev No.
Voi 'fo.
Section OP-ifs 9-8A OP 1.
Remove and return the cancelled procedure and any on-tM-spot procedure changes associated with the procedure.
2.
Line out the procedure entry on the Table of Contents.
3.
Sign and retum this instruction sheet once you completed the above.
l j
RtMARnS:
Reo(nind lav OF IdA E D P-I86 O
Date:
INSTRUCTIONS COMPLIED WITH:
Respons1ble Person RETURN SIGNED INSTRUCTION SHEET TO:
DEoARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT ATTENTION:
N fD/L ocument Control Clerk) i
......____.3