ML20085H390
| ML20085H390 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 07/15/1983 |
| From: | Thornberg R PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML16340D778 | List: |
| References | |
| PROC-830715-01, NUDOCS 8309080270 | |
| Download: ML20085H390 (483) | |
Text
.
1 O
CLERDE DfERGENCY FIAN J
IMPLDfENTING PROCHXRES TABLE OF C0tEENIS Voltane 3A TITLE REV OP-0 Reactor Trip With Safety Injection 4 OP-1 Ioss of Coolant Accident 6 OP-2 Ioss of Secondary Coolant 2 OP-3A Steam Gen Tube Failure 4 OP-3B Minor Steam Gen Tube Failtne 1 OP-4A Ioss of Electrical Pbwer 0 OP-4B Ioss of All AC Pbwer 0 OP-5 Reactor Trip Without Safety Injection 5 OP-6 Faergency Boration 6 O OP-7 OP-8 1oss of condenser vact x.
Control Rocan Inaccessibility 2
6 OP-9 Ioss of Reactor Coolant Pump 3 OP-10 loss of Auxiliary Salt Water 2 OP-11 Ioss of Couponent Cooling Water 2 OP-12 Malfunction of Auto Reacator Control System 1 OP-12A Failure of a Control Bk to Move in Auto 2 OP-12B Cont Withdrawal of a Control Rod Bank 3 OP-12C Cont Insertion of a Control Rod Bank 2 OP-12D Control Rod Pbs 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-15 loss of Feedwater 4 OP-16 Nuclear Instrumentation Malfunctions 3 OP-17 Malfunction of RIR System 2
- OP-18A Ioss of marging 0 OP-18B Ioss of Normal letdown 0 OP-19 Malfunction of Reactor Makeup Control 2 OP-20 Excessive Reactor Coolant System Isakage 2 l
l l .
O 8309080270 830831 DR ADOCK 05000 k 2
1 O
i TITLE REV OP-21 Ioss of A Coolant loop RID 2 OP-22 Faergency Shutdown 1 OP-23 Natural Circulation of Reactor Coolant 3 OP-24 Ioss of Con r aimt Integrity 1 OP-25 Tank Ruptures 1 OP-26 EKcessive Feedwater Flow 1 OP-27 Irradiated hel Damage 1 OP-28 Startup of an Inactive Reactive Coolant loop 1 OP-29 Excessive Ioad Increase 1 OP-30 Inadvertent Ioad Fuel Assly Inproper Pos 1 OP-31 System Under Frequency 1 OP-32 Rod Ejection 1 OP-33 loss of Instrunent Air 1
, OP-34 Generator Trip - W11 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 mannel 1 OP-38 Anticipated Transient Without Trip (A1Wr) 3 OP-39 RCP Iockeci Rotor Accident 1 O OP-40 OP-41 Accidental Depressurization of MS System Hydrogen " Explosion" Inside Contalment 1
1 OP-44 Gaseous Voids in the RG 2 R-1 Per Injury (Rad Related) And/Or Overexp 10 R-2 Re1 of Airborne Radioactive Materials 4 R-3 Re1 of Radioactive Liquids 3 R-4 High External Radiation 3 R-5 Radioactive Liquid Spill 3 R-6 Radiological Fire 6 R-7 Transportation Accidents 3 M-1 Fmployee Injury (Nonradiological) 10 M-2 Nonenployee Injury or Illness (Third Party) 9 M-3 Glorine Ralease 5 M-4 Earthquake 7 M-5 Tsunami Warning 5 M-6 Nonradiological Fire 8 M-7 Oil Spill ISO and Clean Up Procedure 5 G-1 Faergency Classification and Faergency Plan l Activation 3 G-2 Establishment of the On-Site FaerBency Organization 3 ;
G-3 Notification of Off-Site Organizations 2 '
G-4 Personnel Accountability and Assembly 2 G-5 Evacuation of Nonessential Site Personnel 0 O
i l
~ NWBEp EP ONO 3D G55.#E Pacific Gas and Elect,ric Company REVISION 4 A DATE 7/5/83 DEPARTMENT OF NUCLEAR PLANT OPERATIONS
- OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE I OF 20 EMERGENCY OPERATING PROCEDURE TITLE: REACTOR TRIP WITH SAFETY INJECTION 4 ,
-f APPROVED: Yb PLANT MANAGER C/ DATE SCOPE This procedure covers the initial operating steps to be taken in the event of a reactor trip with safety injection signal. The safety injection signal may occur at some time after the reactor trip has taken place. If this is the case, the operator will cease using OP-5 (Reactor Trip Without Safety !
Injection) procedure and will use this procedure to control and analyze the ,
l plant condition.
SYMPTOMS I
The following symptoms are typical of those which may arise in a plant which is undergoing a loss of reactor coolant, loss of secondary coolant or steam generator tube rupture (one or more symptoms in each category may appear in any order)2:
LOSS OF REACTOR COOLANT Lo Pressurizer Pressure Lo Pressurizer Water Level Hi Pressurizer Water Level Letdown Isolation / Pressurizer Heater Cutout Increased Charging Flow Hi Containment Pressure Hi Containment Temperature Hi Containment Humidity Hi Containment Radiation Hi Containment Recire. Sump Water Level 1The process variables referred to in this Instruction are typically monitored by more than one instrumentation channel. The redundant channels should be checked for consistency while performing the steps of this Instruction.
2The pressurizer water level indication should always be used in conjunc tion with other specified reactor coolant system indications to evaluate system response and to initiate manual operator actions.
O
1 l
NUMBER EP OP-0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2
~
DATE 7/5/83 PAGE 2 OF 20 TRIE: REACTOR TRIP WITH SAFETY INJECTION l
i i
LOSS OF SECONDARY COOLANT
.j 4
" Lo Pressurizer Pressure Lo Pressurizer Water Level Letdown Isolation / Pressurizer Heater Cutout Lo-Lo Reactor Coolant Tavg Hi Containment Pressure Hi Containment Temperature Hi Containment Retirc. Sump Level Steam Flow /Feedwater Flow Mismatch Lo Steam Line Pressure (one or all Steam Lines)
Lo Steam Generator Water Level Hi Steam Flow (one or all Steam Lines)
Lo Feedwater Pump. Discharge Pressure lh STEAM GENERATOR TUBE RUPTURE Hi Air Ejector Radiation Lo Pressurizer Pressure Lo Pressurizer Water Level Increasing Charging Flow Letdown Isolation / Pressurizer Heater Cutout i
Steam Flow / Feed Flow Mismatch Hi Steam Generator Blowdown Radiation Increasing Stem Generator Water Level AUTOMATIC ACTIONS
- 1. Reactor trip and turbine trip.
- 2. Safety injection initiated.
OBJECTIVES
- 1. To verify the reactor trip and safety injection.
O
NUMBER EP OP-0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 4 OATE 7/5/83 PAGE 3 OF 20 TITLE: REACTOR TRIP WITH SAFETY INJECTION NOTE: If the plant is in a condition which warrants a reactor trip .5 4 and safety injection and an automatic reactor trip and safety injection has not yet occurred, it is the reactor operators responsibility to manually initiate the reactor trip and safety injection.
- 2. To verify all SI equipment is operating and performing the intended function.
- 3. To monitor plant parameters and diagnose the initiating SI signal .
4 To mitigate the consequences of a valid SI signal by providing direction once the initiating signal is identified.
IMMEDIATE OPERATOR ACTIONS ACTION
- COMMENTS
- 1. Verify the following automatic actions.
If required, use manual control to satisfy the action.
- a. Reactor trip (all rods on bottom, DRPI -
Nuclear Instruments Decreasing.)
- b. Turbine trip (all four SV closed on EH panel.)
- c. Vital 4160 busses F, G and H transferred to startup power (breaker positions on VB-4.)
- d. Vital 4160 busses F, G and H voltage nomal (120 volts indicated on 480 volt vital busses F, G and H, VB-4.)
- e. Diesel generators running and voltage normal
( (diesel RPM and generator voltmeter on VB-4.)
- f. Auxiliary building' ventilation system in build-ing and safeguards mode (mode light on venti-lation section of VB-4).
- g. Control room ventilation system in mode 4 (mode light on VB-4).
- h. Both motor driven auxiliary feedwater pumps
, running and all 4 auxiliary feedwater LCV
( open. (Motor breaker position lights and LCV position indicators on VE-3).
NUMBER EP OP-0 DIABLO CANYON POWER PLANT UNIT NO(S) 1,AND 2
- OATE 7/5/83 PAGE 4 OF 20 TITLE: REACTOR TRIP WITH SAFETY INJECTION
^i ACTION COMMENTS l }
- i. Check the safeguards postage stamp monitor lights on VB-1.
I. F_ 2 steam loops have Hi steam finw in alam with any 2 loop Lo pressure in alam OR 2 steam locos have Hi steam flow in alam with any 2 loop Lo-Lo Tavg in alam THEN: Verify all 4 main steam isolation valves, bypass valves and all 4 steam generator blowdown stop valves IC closed (valve cosition indication lights on VS-3).
- j. ALL ECCS pumps have started and J. Verify minimum of one automatic valve operations have ECCS train operating (SI, charging and RHR occurred (all SI/FW ISOL/STM GEN pump).
LEVEL postage stamp monitor lights on VB-1 not in alann).
- k. Containment Phase A and containment ventilation isolation (all contain-ment Phase A postage stamp monitor lights on VB-1 not in alam).
SUBSEOUENT OPERATOR ACTIONS (PART A)
- 1. Verify the following pump flows.
If the flows are not occurring, attempt to operate equipment manually or locally to es+ablish the flows.
l Ih
NUMBER EP OP-0 1 AND 2 OtABLO CANYON POWER PLANT UNIT NO(S)
DATE 7/5/83 PAGE 5 OF 20 TITLE: REACTOR TRIP WITH SAFETY INJECTION v
ACTION COMMENTS .Iy
~
Minimum of one safety injection a. NOTE: If W.R. RC5 Pressure
.; a. is greater than the shut-pump running with flow indicated off head of the SI pumo, when W.R. RCS pressure is less than the SI pump shutoff heao continue on with this pro-(1465 psig). (VB-1) cedure to monitor W.R. RCS pressure and verify SI pump flow if pressure drocs be-low the shutoff head of the SI pump.
- b. Minimum of one charging pump running with flow via BIT indi-cated on FI 917. (VB-2)
- c. Verify both motor driven AFP running and flow indicated, to all 4 steam generators (VB-3),
OR Start the steam driven AFP by opening FCV 95 and establish flow to all 4 steam generators O (VB-3).
Maintain maximum AFW flow until c. Automatic Steam Generator the steam generator water icvels level control only applies are in the narrow range. When the to motor driven AFP's.
SG water levels approach 33% NR, verify automatic steam generator level control .
- d. Verify RCS heat removal by d. Atmospheric steam dumo will be blocked by an existing
- 1) Observing automatic " Turbine Tripped" condition.
dump to condenser or atmos- If condenser steam dumo has pheric steam dump via the 10% been blocked due to a steam dump valves (VB-3). control malfunction or loss of the " Condenser Available" AND 2) RCS Tavg decreasing to no-load condition, decay heat re-temperature 547'F (VB-2) moval will be effected by automatic actuation of the steam generator 10% atmos-pheric steam dump valves, or if l
l O
BER P OP-0 3 oN OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 7/5/B3 DATE PAGE 6 OF 20 TITLE: REACTOR TRIP WITH SAFETY INJECTION
- i!
COMENTS 3 ACTION 3 these prove ineffective, the steam generator code safety valves. In this event, steam pressure will be main-tained at the set pressure of the controlling valve (s) and reactor coolant average temperature will stabilize at aoproximately the saturation temperature for the steam pressure being maintained.
- 2. Monitor containment pressure (VB-1),
if containment pressure reaches or exceeds 22 psig, verify the .following actions. If required, use manual control to satisfy the action.
- a. Main Steam Isolation Valves and Bypass Valves closed. Phase B isolation postage stamp monitor lights not in alam (VB-1).
- b. Steam Generator Blowdown Valves IC closed. Phase B isolation postage stamp monitor lights not in alam (VB-1).
- c. Containment spray initiated (phase B isolation postage stamp monitor lights not in alam VB-1).
- d. Phase B isolation (phase B isolation postage stamp monitor lights not in alam VB-1).
Manually trip all 4 RCP's. e. CCW to the lube oil coolers
- e. will be lost on the phase B isolation.
- 3. Monitor the core exit themoccuple temperatures for indications of inadequate core cooling. If indications of inaaequate core cooling exist, perform Appendix 3 of this procedure.
l
N E ONO DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 E S ON ' ~
~ DATE 7/5/83 PAGE 7 OF 20 TITLE: REACTOR TRIP WITH SAFETY INJECTION
.5
}
. SUBSEQUENT OPERATOR ACTIONS (PART B)
ACCIDENT DIAGNOSTICS
- 1. Evaluate RCS pressure:
If W.R. RCS pressure falls below or a. Verify closed by observing
- a. position indication lights is below 1950 psig, close or verify and discharge pipe temp-closed the following valves.
erature indicators.
Pressurizer Spray Valve PCV 455A Pressurizer Spray Valve PCV 455B Auxiliary Spray Valves 8145 and 8148 Pressurizer Power Relief Valve PCV 474 Pressurizer Power Relief Valve PCV 456 Pressurizer Power Relief Valve PCV 455C
- b. If W.R. RCS pressure remains abcVe 1950 psig and is stable or increasing, go to Step 1 of Part C Subsequent Operator Actic ns .
If W.R.RCS pressure continues to decay .2. NOTE: The conditions for
- 2. stopping RCP must be con-below 1220 psig or is below 1220 psig tinuosly monitored through-and stable. out the transient.
- a. Again verify a minimum of one a. SI flow rate will increase with decreasing RCS press-charging pump delivering flow ano one SI pump delivering flow ure.
to the RCS
- b. Then, STOP all four reactor coolant pumps. Maintain seal water flow to the RCP seals.
- c. Close the centrifugal charging c. NOTE: When the W.R. RCS pump recirculation valves, 8105 pressure is restored above I 2000 psig, reopen valves and 8106. 8105 and 8106 to prevent pump damage.
- d. If component cooling water to the RCP's is isolated due to i
a containment phase B isolation,
' stop all RCP's within 5 minutes and maintain seal flow as above.
t
- s AND 2 REVISION 4 DIABLO CANYON POWER PLANT UNIT NO(S) 7/5/83 DATE PAGE 8 OF 20 9TLE: REACTOR TRIP WITH SAFETY INJECTION i
ACTION COMMENTS '.j i.
- 3. If condenser air ejector radiation monitor is reading abnannally high radiation AND containment pressure, containment area radiation monitor, and containment recirc.
sump level exhibit NORMAL readings, dis-continue this procedure and begin pro-cedure OP-3A, Steam Generator Tube Rupture.
l 4 If steam generator pressure is 4. This is indicative of a ABNORMALLY LOW in one steam gener- secondary break upstream of ator as compared to the other MSIV.
steam generators, discontinue this l
procedure and begin procedure OP-2, Loss of Secondary Coolant.
! 5. If containment pressure, containment area 5. NOTE: For very small coolant radiation monitor, or containment recirc. breaks inside the containment,
) sump level exhibit ABNORMALLY HIGH or the containment pressure and INCREASING levels, discontinue tnis containment recirc sump procedure and begin procedure OP-1, Loss level may increase very of Reactor Coolant. slowly and possibly not recognizable by the operator intnediately. Therefore, the operator should monitor these parameters throughout the transient.
- 6. If containment pressure, containment 6. This is indicative of a area radiation monitor and containment secondary break downstream recire. sump level remains stable in of MSIV.
the pre-event range, discontinue this procedure and begin procedure OP-2, Loss of Secondary Coolant.
F
NUMBER EP OP-0 l DtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 .
REVISION 4 DAT1E 7/5/83 PAGE 9 OF 20
)
y,/ TITLE.
SUBSEQUENT OPERATOR ACTIONS (PART Cl
)
ACTION COMMENTS }
4
- 1. This step is entered frcm
- 1. Assume the event is NON SPURIOUS Accident Diagnostics step safety injection until all of tne I b.
following items are verified NORMAL.
- a. Containment pressure.
- b. Containment temperature
- c. Containment recirc. sump level.
- d. Containment area radiation monitor.
- e. Condenser air ejector radiation.
- f. Auxiliary Bldg. control board area radiation.
- g. Reciprocal charging pump room area radiation.
- h. Plant ventilation particulate monitor.
- 1. Plant ventilation radio gas v monitor.
If the above items a. through 1. cannot be verified NORMAL, return to step 1 of Accioent Diagnostics.
If the above symptoms a. through 1. are normal, and when J. W.R. RCS pressure is greater 2000 psig.
NOTE On spurious SI recovery, if RCS pressure decreased below the shutoff head of the SI pumps (1520 PSIG) during the transient3 perform leak test (STP V-5) within 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> following the ECCS actuation on those valves listed in Table 3.4-1 of Tcch Spec 4.4.6.2.2 which actuated or if there was flow through the valve.
AND k. Pressurizer water level is greater than 22*..
RCS indicated subcooling is greater 1. If the RCS subcooling meter AhD 1. is inoperable or is than 35'F. suspected to be incorrect, use wide range Thot in conjunction with the attached RCS saturation curve (graph) to determine RCS subcooling.
j
)
J l
l
- . - - ~ _ - - -
i NUMBER EP OP-0 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) '
REVISION 4 -
DAM 7/5/83 PAGE 10 OF 20 TITLE: REACTOR TRIP WITH SAFETY INJECTION ACTION COMENTS j
. y
- f. AND m. Auxiliary feedwater flow to each -
steam generator is greater than 205 gpm or One steam generator wide range water level instrument indicates a level greater than 75".
THEN
- 2. Reset safety injection. 2. CAUTION: 1) Automatic rein-itiation of safety injection will not occur after this step since the reactor trip breakers are open. If the operator has indication that an SI is required after this step, he must initiate it manually.
CAUTION: 2) If loss of off-site power occurs after re-setting safety injection, it will be necessary to load the safeguards equipment onto f
the vital busses manually.
If safety injection is l reinitiated manually after the loss of off-site power the vital busses will auto-matically sequentially load the safeguard equipment.
If manual loading or auto-matic loading is performed, verify the equipment given in Appendix A is loaded onto the vital busses.
- a. Reset containment isolation phase A, train A and train B.
- b. Stop one charging pump at a time and evaluate RCS pressure. Maintain sufficient charging flow to supply adequate seal injection flow and to prevent RCS pressure from decaying.
If RCS pressure drops below 1850 psig, 0
N 1 AND 2 RE ON DIABLO CANYON POWER PLANT UNIT NO(S) , ,
DATE 7/5/83 PAGE 11 OF 20 TITLE: REACTOR TRIP WITH SAFETY INJECTION 2
ACTION COPHENTS reinitiate SI and return to Step 1 of the diagnostics.
- d. Verify AC turbine bearing oil pump and Hi pressure seal oil backup pump running after oil pressure decays to 11 psig and turbine bearing lift pump starts at 600 t RPM turbine speed.
i
- e. Establish normal charging.
- 1) Open instrument air valves
! FCV-584 and 682.
l
- 2) Check open or open nonnal charging valve 8146.
- 3) Check close or close charging to auxiliary spray valves 8145 and 8148 and alternate charging valve 8147.
I 4) Open charging line isolation valves MO 8107 and 8108.
- 5) Adjust HCV-142 and FCV-128 or reciprocal charging ptsnp speed to achieve RCP seal flow and charging flow as required to maintain pressurizer level greater than 225.
- 7) Close the BIT inlet and outlet valves 8803A and B, 8801A and B.
(
NUMBER EP OP-0 DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 DATE 7/5/83 TITLE: REACTOR TRIP WITH SAFETY INJECTION C0teENTS [.
ACTION i
f- 3. Verify the following:
- a. With normal RCS charging, the pressur-izer water level remains above 10%.
- b. W.R. RCS pressure remains above 1850 psig.
RCS indicated subcooling greater than c. CAUTION: Stopping and start-
- c. ing of the ECCS pumps can 35'F. cause pump motor overheating If item a., b., or c. above cannot or reduced motor life.
be verified MANUALLY, REINITTATTTAFETY INJECTION and return to diagnostic Step 1, subsequent action Part "B", of this procedure. ffthe.ECCSpumpsare restarted, add 15 F to item c. above.
- 4. Verify auxiliary feedwatcr flow and steam generator water levels approaching NO LOAD level (33% narrow range).
- 5. Establish normal letdown.
- a. Check open or open letdown valves LCV-459 and 460.
- b. Open letdown isolation valve 8152.
- c. Open one 75 gpm letdown orifice valve.
- d. Verify PCV-135 opening by observing letdown flow.
- a. Adjust VCT makeup blend to the existing baron concentration.
1
- b. Open VCT outlet valves LCV-112B and C.
- c. Close RWST to charging pump suction valves 8805A and B.
I
- d. Verify divert valve LCV-112A in AUTO.
- e. Verify charging flow normal. i )I ,
NUMBER EP OP-0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 4 DATE 7/5/83 FAGE 13 OF 20 TITLE: REACTOR TRIP WITH SAFETY INJECTION O ACTION COMMENT
- 7. If RCP's are not running, establish 7. Start RCP 1 or 2 if i conditions for starting RCP's and start possible to provide d Pressurizer Spray l i
at least one RCP. capability.
~
~
- 8. With pressurizei level controlled in manual, verify pressurizer pressure control in AUTO and pressurizer sprays and heaters controlling pressure.
- 9. Stop all 3 diesel generators, place diesel generator control switches in AUTO.
- 10. Insure the main and feedpump turbines on ,
turning gear once O RPM speed is reached.
'll . IF after securing safety injection and 11. CAUTION: Do not reset the transferring the plant to nonnal pressur- reactor trip breakers until izer pres:ure and level control, the reactor authorized by the Plant coolant pressure does not drop below the Superintendent.
low pressurizer pressure setpoint for safety injection actuation AND the pressur-izer water level remains above 10%, AND the reactor coolant indicated subcooTTiig is d greater than 35'F, then consider the event a spurious safety injection. Continue to monitor these parameters closely; if any parameter fails to remain above the limit, manually reinitiate Safety Injection and return to Step 1 of the Diagnostic section.
SPURIOUS SI SIGNAL RECOVERY
- 1. Proceed to a normal Hot Standby condition as follows:
- a. If steam line isolation has occurred:
- 1) Close or check closed all 35 and 40% steam dump valves.
- 2) Prepare or verify main condenser i available for service. ,
- 3) Equalize or attempt to equalize 3) A steam line break down-and open all 4 MSIV's. Monitor stream of MSIV's will steam generator pressure closely prevent equalizing.
I during this operation. Inunediately
! close all MSIV's if steam pressure
,, rapidly drops during this operation.
I x 4) Establish steam dump to condenser using steam pressure mode set at 1005 psig.
NUMBER EP OP-0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2
- - AEVISION 4 OATE 7/5/83 PAGE 14 OF 20 Tnu; REACTOR TRIP WITH SAFETY INJECTION ACTION C0tttENTS ,
i 6 5) If steam dump to the condenser is established, verify all atmospheric steam dump valves closed.
- b. Open the main generator motor operated disconnect switch and reenergizt: the unit auxiliary transformers by back-feeding from the 500 KV yard. Transfer all station auxiliary busses (12 and 4 KV busses) to the unit auxiliary trans-fomers.
- c. Return the auxiliary building ventilation system to nomal by resetting the "S" signal on both POV cabinets and selecting building only mode on VB 3.
- d. Reset both Units 1 and 2 control room ventilation systems on Unit 2 radiation control board and verify both Units 1 and 2 ventilation systems return to the nomal mode of operation.
- e. When directed by the SFM, shutdown the following:
- 1) One auxiliary saltwater pump.
- 2) Steam driven auxiliary feedwater pump after steam generator levels are greater than 337. and motor driven pumps are controlling level.
- 3) Close CFCU maxi flow valves then shutdown 1 CCW pump.
- 4) Remove 2 CFCU's from service and place the running CFCU's on fast speed.
- f. Verify BA transfer pump running and open the BIT recire. valves to begin increasing BIT concentration. Call Chemical and Radiation Department to begin sampling the BIT and BAT.
l
- g. Reset containment ventilation isolation trains A and train B.
O :
l 1
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REV S ON 4 DATE PAGE 157/5/8}0
~
oF TITLE. REACTOR TRIP WITH SAFETY INJECTION ACTION COMENTS i 1) Open containment rad. Gas monitor valves FCV-681, 678 and 679.
- 2) Verify nomal readings on containment air particulate and radio gas monitors on RMS board.
- h. Reset radwaste isolation valves reset switches.
- 1. Open fire water valve FCV-633 and primary water to containment valve 8029.
J. Open valve 8045 N2 to PRT.
- k. If the incore chiller has been in service prior to the SI, open incore chiller valves FCV 655, 657, 654 and 656.
- 1. If the gross failed fuel detector has O been in service prior to the SI, open Hot Leg sample valves 9356A and B.
- 1) Verify flow returns on the GFFD flowmeter.
- 2) Verify the GFFD countrate returns on scale and stabilizes at a value below the post SI countrate on the recorder.
- m. Open the pressurizer steam space sample valves 9354A and B
- n. Open pressurizer relief tank gas analyzer valve 8034A.
- 2. Maintain Hot Standby conditions until authorized to proceed with a normal startup or infom the plant superinten-dent that the unit is proceeding to Cold Shutdown.
--r, -- . . - - - - - , . . _ _ ,,. , .- - - . - , - ,
I l
NUMBER EP 0P-0 1 AND 2 REvtSION 4 DIABLO CANYON POWER PLANT UNIT NO(S)
DATE 7/5/83 PAGE 16 OF 20 I
1 TITLE: REACTOR TRIP WITH SAFETY INJECTION I - . _
. . L-] . . .
"- * ~
=.:..._-_W " * ^^ " "* " ""
~
! ,,?
.. . 1
.~ .+n ;_=:=
. r- -.
- .-- :- --u._..
2'00 ' . b.
- = - .
- instrument errot5. .
, - . . . .;g -- . ,
2200 - .@.j~ :
-=..
'r~ ;. . . . . - . . - -.. -. .: - .._ ".. "' "
' " " f*--::~=
. :c =::.: _
. :: . :.:: ..:.:. . . . . ~ . . . . . . :.: # .. "~~.
\
. ~'.; *-'** ' :'W'." . en-F' ' ' .^" L .'L:. -
== = .m I
2100? . "- = .- ..
- 7- "= = : = - : ~ = == = == W .
I a : .m= :1E* C.:=4 W An 1 N %WA- _: z.; : . ..-..: ~ :: . -.
=- *=9:~~C.=.
1 .
"=='
?. ^
-t ::: -..--T...
' ~~ . = :-
"- .' ' = - " - ~ ~ ~ -" : .. . . , . = . m =.=.. . = . 3: --
'..==".=z_-
2000 .: ,: -=.-u.. . . .: . . :.: . . . :=:-9..
- =- - --=.~.- - . . .
- :. g . =: . ==: :.
_ . . : ;=.: . .-
.: u_ ...:p: :
. . .~ == : :- n, ::-:= - - . . . .
- .=.:.; ,
. .t: -. .:=; -:. .. _,. = _ =: _ : ..: .: L s.- : - = :- = n = - t =.~ ~: . =--:.~_ ="
w+ - - ==:- - =. =:~ . ._-. . .:: ===
- =:... a:.=.:= M
- - - .- : . ::.~.=::.: = = _ . : : : =: :-.==--
=-===...=--=.=-=-=e;:==,_..=-=:.:.=..-
3 qgg:-
- = .=- = . = = : 7
=:...~. ~
. :: = u =..t= == : . :.- . . : = === '
-== "~~ ~~"==- = ~
=": -+ .= , =-==:= :---. :==~~~==----".."
10 00- .'-t==,"g== =-=:==r.: .= - : :-===- =.=:::===== = = =.:.: . -;.=.;= - . -.- .- -~- -=.= = . ..: :=:=: v--= c.- -- - - == =. : ". -.
.:--_.=.=..=.:: :=: :-- _-
.= . = . -=. u:=. - - - - ..=._
- - - .: ; = - . . . / . : .- --- r_=- : 2 --==. .. . = = = =
-x
=:..===.=-
- "_" ;'"- i.= =- ==.
'. =-'......=.::_= . ': =:. . =. . . .
.== -
1 7 0.. 0'_ ': :.' '.._....=-:c-===-e-._.=--
.=_"_.'".TUD
- -.-..:- #UM *NW--"== .' ,': =- . .=5=' _.
= = =: . - - = = . . .
_ ::; =_ . - - .=.
. - = . = . = . = =- -. . .. . .... -. -_... .:- .=._ = -s. .::u.=.
.==.:.=. .= _=_= =. -=. : . . .. .. =. . :. : ._;,-= =. :. . .i==t _- ..-
1 6 0 0 ;.
=
..=....= t. - _m-....~ _ .= _; . :.:.:_.. .=_.c.
=_
,= . _ e . .~== .
c =--=_=_ 3. =. .. . : _.: . = == . :- r -* . .== . := :
..-===-_
- -- . =. .=: .=;7. . .= _ .u
< .--=:-_=.._,-.
=: =- = -~ ~ .=: == - .
=~===.:. ~ ~. .'= -. - "= = -
- = = = = a.: . .. =:. - - .= t: = = . :
m = . : . r:-= - - - =~ = .~.== ..
" =- ==_ = _ = . . ~i====.=.=.-.:=.=._u.._-
- " - ~ * - " - -
" = --
. : ..=- -
1 5 0 0.'
.. 'r .- =.;. =.=' == - . : _. ==_:. -- =.:. ==._ = .=:--__=...___:::-..-.."-'""~'.._=_=
w a ..-
$l4g.=_.=_.a..=_..=...=....=._.=...=_=.=s.._.=;.=.....-==
)
'==r :
===E= '==sW :M M_-=^."i=WJ =- E i E E-a= 2=$ #i- " '.= =U r ~ s.=f ="~ -l
.=....-.=..:.:s.=...."M....._
w t.= ,. : : =:.= . .
.=..==..: . = . . . .. _. -
g . = . . - - = = . . . .. . = . -= . . . . . = . - _ . . .. . : : . : . . =~ -- .
=.
- c:..
s_- M. . :.-..=. = = .: =-r=---.. G- .- .:.=======a..
..=..===..=.==.......=.;. _ :..-:=..=_=._==..- .:. :.:
= =:=.= .:.: -
- -. . . . .. . .-.:=.===.. .
- .- --. . ~.:
-NE=~if._.= - - - - x.
m .-- - - - - - ~ ~ - ' - " -
- ~ ~ -
-i ==?=~~ ='N -::- . 2==.
u
" 12 00"= -
=.p.-=: .: .-- - .: =.. -X= -5b'W::=.=2#.=====L ='~=M:-Rt= 5E"?# ;E ::'.:- -
==-
.= = ==- - -. ... =: .g - :- = . . . = = = : :-
. . .ta. litwr. m - .. - - =-=
1100 .==a. . . ...- . = .Kcm.
=t /.*=Ef.4_=4:'s.~1& M"-i.5E -
-1i S :Sn55-1:0:h:hh=3EM.Uf th5f=E= ""+. =-f.-? : - - = - . a#' :. . =-=
=
' ==== := =gu. g w = - =: = . = s. . : . = Im .
= =.== =: . - ===== ..:. -
1000=.: - e :=:
=.-=:.-=-
-- = ===- ==_= = = =:
=.u-:.-...-==....:=.=-_=-..=:-.
u.= -
. = . . . . . . - . . .
- ..=. .= . ..=-..=.=.: = .= .-.===. =. _
= .. =- .p=. - -_--. [E9EEf === ---
. . - =... ._
9 0-. :=.o. .=.= m_= : =.c a,_._- _==_=..== =_ . a --_=. =. .==. .. . =_= .-=. _- .-
. = :....=.=.=-=.=. w- m c..-
,....=.:
; = .- ; -= = = . == _ ==. .==.-
. . . : n.;-- =.
. . . . = =. . . . . - :-=- .:.= : -:.= . = .. = :.:--= ==
= .:=. - _ ----.
- =.
..= .. :==. =- =-
g 9q= == : ==== .:. - .u . . - .===-= : t : - == - -?.-.= = : . - --. ... == .- := -=.:=. :. = .=-
==.==: === - --..=.u .. - . . . _ .==- .- .-. .- . . ..EEEEW =:
_.======.=m:-===_---
- - - = - - . .=.- . . . . . . ..
=. . .=.
- - , - -.- x=
- - - = : =::;"_ .,, _ t :: :.=~ _- _ _ _
==. .= : ,_ . _ :
-...==u -- - Dzal .- ==s=. =.- = . - - -. - . . .
===.=....====.-=.--.......:=-=..=-=..---==.-...~==.
7 0--====.:.--: 0==:=: :. =-- -= .. .. . -= . ==.- .
- . . . ~ . . = . = . = . =..
, . ,., = . ~
=._: . - -=:-:=. .= .. .:- . .
=-. ...:: . . . .
vm t 6O :== C. - ==. = . -.
= . ._ =_- _;_ .: -= . :... . ..=. .=:2
. : . : . ; == :. . r.== =. c - . . L==.n - ==- .. -
~
.=. .. .; .==.. . =-==
=. = _.$m . . = .:.m c
=. -
= =:.; .= = 2. = n.
us - .=::=== . -
. :.= . .
..- -=. ~ = ==
.=: :.
- . = g .
ZEM: = -. . I=-=5:E = ==":5 = ==E-50E - " 9 ---J+='f ~#*==="P 3 Z5'=M @:23 is E- ~_~ ~ 5in ~- -G-J.J ME-==.=====-r-~r rw _-i: =='M=5-== u?==. u - _. .".#'M25 r =.-~ _=.:=-W_-=*
===: = =: = ==-~ ==- ~: -
--- ===_r--.c------===2= = "= i -
.-:.- == :==. -
.: =.: . -. .. = ==.=.==-~=.=:===:r.
4 0n- =- =- -- -- = t - - = --
==. = = = :s;. =s:: = n.=- == --
=- -. :-. -==. - -.=- ..- - .=..
i - - - - -
+ :.
- ==.=. =r : - - . : ,==: = .= ==.=.-~~-r=..=.==.==:,=..=-r.
t
**-%-~~?-=-
. .- = * * * /W4 *L M '.=~ ;* -^:-. -
a e.-::. = ;...=
.:. - . = ; . - . =. :. = . t===n :- .. .:.
} Q f:. ,: =- .=: --=.-==.u- "-=*-= .= =-' .= = -_- c -. -.=- ==.=: . .=. ====l lb l
=. ~. u . : . =. . -: an - - - .. : . . .- s.. . . . , _ . . .
..=.
- - : . p_.---- =:. =_. - =- -= ..
. =. ..t= . _
.~ . . . a. : ; . =~ =- . .
-= .= : . --p' ' -- - = . -
. :. . = .
- .t.
- re - =
-- c - == = -.z -' ~
200 500 600 700 200 300 400 l 0 100 RCS Temoerature (*F) 1 i
NUMBER EP OP-0 - DIABLO CANYON POV.ER PLANT UNIT NO(S) 1 AND 2 DATE 7/5/83 PAGE 17 OF 20 TITLE: REACTOR TRIP WITH SAFETY INJECTION O APPENDIX A ,, BLACKOUT WITH SAFETY INJECTION EMERGENCY LOADING OF VITAL BUSSES
~1. If the vital busses lose voltage prior to resetting the safety injection signal, the vital busses will automatically load'the vital equipment given below. Verify the equipment has been loaded by observing breaker lights on the control board.
- 2. If the vital busses lose voltage after the safety injection signal has been reset, load or verify loaded tne equipment given below onto the vital busses manually. Allow approximately 4 seconds between loading cf each pieca of, equipment onto a given vital bus. Load or verify that the CFCU are running in Low Speed.
VITAL BUS VITAL SUS VITAL SUS G H F D/G l-3 D/G 1-2 D/G 1-1 MCC 1-G MCC 1-H MCC 1-F CC Pp l-1 CC Pp 1-2 SI Pp 1-2 V SI Pp 1-1 RHR Pp 1-1 RHR Pp 1-2 CFCU 1-2 CFCU 1-3 CFCU 1 4 CFCU 1-1 CFCU 1-5 CCW Pp 1-3 CCW Pp 1-1 ASW Pp 1-1 CCW Pp 1-2 AFW Pp 1-2 AFW Pp 1-1 ASW Pp 1-2
- 3. Load the containment spray Pumps only if they were running prior to the blackout.
VITAL BUS VITAL BUS G H Cent Spray Pp 1-1 Cont Spray Pp 1-2 O O
NUMBER EP OP-0 otABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 _ DATE' 7/5/83 PAGE 18 OF 20 TITLE: REACTOR TRIP WITH SAFETY INJECTION APPENDIX B 3 DETERMINATION OF ADEQUATE CORE COOLING This appendix provides the guidance to detemine adequate core cooling if inadequate core cooling is suspected. adequate core cooling is presented. COPHENTS ACTION
- 1. Monitor the core exit themoccuple 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 themocouple readings exceed 1200'F, notify the Shift Foreman that inadequate core cooling exists and go to step 5.
If there are not 5 or more that exceed 1200*F, discontinue this appendix but centinue to monitor the themoccuple readings.
- 3. At the thermocouple incore board in the control room, Monitor 10 care-center'd thermocouples. If any 3 of the 10 thermocouples exceed 700*F (pegged hi) proceed to step 4.
If there are not 3 themocouples that exceed 700'F, discontinue this appendix but continue to monitor the themocouple readings.
- 4. If SI flow to the RCS and AFW flow to the steam generators cannot be verified, notify the Shif t Foreman that inadequate core cooling may exist and go to step 5.
If both SI flow to the RCS and AFW flow to the steam generators can be verified, discontinue this Appendix but continue to monitor the themoccuple readings.
- 5. The Shift Foreman will verify if inadequate core cooling exists using the appropriate steps above. If inadequate core cooling l In exists the Shift Foreman will direct operations as follows:
. NUMBER EP OP-0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 4 OATE 7/5/83 PAGE 19 OF 20 TRLE: REACTOR TRIP WITH SAFETY INJECTION
}
APPENDIX B (Cont.) f COMMENTS ACTION
- a. Declare a General Emercency Inplement the instructions given in Emergency Procedure G-1 regarding on and off-site 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 condense.r 1) THIS IS THE PREFERRED METHOD.
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 pro-pumps are running and available vide a drop in RCS pressure to deliver water to the RCS. sufficient to allow the SI flow required to cool the THEN core.
Open the pressurizer PORV's. This method is to be used cnly if 1; (above) is inef-
- e. If no means of depressurization are fective.
Available, or if the depressurization did not result in decreasing core e. Attempt to establish CCW and seal exit thermocouple temperatures, water flow to the pump; however, if CCW and/or seal water flow THEN cannot be established, proceed to start a RCP. The pump must be . START one RCP if possible. Started to move coolant thru the ( core. If the RCP fails after starting, replace i the lost RCP with any remaining RCP. (Q)
~- ,
t 4
, . - - , -v. - ,
NU BER EP OP-0 DLABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 E DATE 7/5/83 PAGE 20 OF 20 TITLE. REACTOR TRIP WITH SAFETY INJECTION l 3 APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been implemented, and upon direction from the Shift Foreran, proceed as follows:
- a. Designate this event a Nofification of Unusual Event if ECCS flow is indicated. Notify plant staff and response organizations required for this classification by implementing Emergency Procedure G-2
" Establishment of the On-Site Emergency Organization" and G-3 "Not-ification of Off-Site Organizations" in accordancr. with Emergency Procedure G-1 " Accident Classification and Emer' .1cy Plan Activation".
- b. Reclassify this event according to the Appendix Z instructions in OP-3A " Steam Generator Tube Rupture" or OP-1 " Loss of Coolant Accident", if the accident diagnostics require implementation of either these procedures.
- c. In the event inadequate core cooling is verified per Appendix B reclassify this event as a General Emercency. Notify plant staff and response organizations requirec by EP G-2 and G-3 in accorcance with EP G-1.
e l
NUMBER EP OP-1
}GE43 Pacific Gas and Electric Corppany REVISION 6 DATE 07/05/83
)
DEPARTMENT OF NUCLEAR PLANT OPERATIONS
, I and 2 PAGE 1 OF 49 DIABLO CANYON POWER PLANT UNIT NO(S)
TITLE: g EMERGENCY OPERATING PROCEDURE 1 LOSS OF COOLANT ACCIDENT
$ APPROVED: T[ '
DATE PLANTMANAGEP) SCOPE This procedure covers the operating steps to be taken in the event It is assumed that reactor trip and of a Loss of Coolant Accident. safety injection actuations have occured. The operator should have already performed the immediate operator actions and diagnostics of Emergency Operation Procedure No. OP-0. SYMPTOMS _ (See OP-0 Symptoms / Diagnostics) AUTOMATIC ACTIONS (See OP-0) OBJECTIVES
- 1. Verify and establish short term core cooling to prevent or minimize damage to the fuel cladding and release of radioactivity.
- 2. Maintain long term shutdown and cooling of reactor by recirculation of spilled reactor coolant, injected water and containment spray drainage.
- 3. In the case of the small break LOCA, to reduce plant conditions to the cold shutdown condition for repairs.
IMMEDIATE OPERATION ACTIONS
- 1. Perform tne imediate operator actions in the reactor trip wi+.h Safety Injection Emergency Precedrue OP-0.
SUBSEQUENT OPERATOR ACTIONS COMMENTS ACTION
- 1. Initiate the site Emergency alarm
- 2. Monitor the RWST level If the level decreases slowly, proceed a. A small break LOCA l a. is indicated.
'- to step 3.
1
l NUMBER EP OP-1 OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6 07/05/83 ) OATE PAGE 2 OF 4g TITLE: LOSS OF COOLANT ACCIDENT COMMENTS $ ACTION
- b. If the level decreases rapidly such b. A large break LOCA is
- e. indicated. The RCP seal that the low level alarm is eminent, verify ECCS flow from at least one water flow should be charging and one SI pump, and after maintained when the pumps W.R. RCS pressure decreases to <1220 are tripped.
psig, stop all 4 reactor coolant pumps The recirc. valves (8105 & and cicse the Centrifugal charging pump 8106) shall be reopened if recirc. valves (8105 & 8106). Proceed pressure is restored to to Appendix A LOCA Injection / >2000 psig to protect the Recirculation changeover procedure. pumps from damage. Monitor the RWST -level closely throuchout 3. In the worst case, with
- 3. RCS near 0 psig and this procedure. If RWST_ level is de- minimum Tech. Spec. level creasing, such that the low level RHR pump trip setpoint 33% appears iminent, in RWST with all ECCS go directly to Appendix A, LOCA Injection / equipment discharging Recirculation Changeover Procedure, including containment attached. When Appendix A is completed, spray, the Operator has return to this procedure and continue. 14 minutes from time of break to RWST lo level.
Verify containment sump level increasing. 4. CAUTION: In the case of
- 4. the samil break, the sump If no increase is evident as the RWST level m3y rise slowly as the decreases, return to OP-0 diagnostics, step 3, 4, 5 and 6, to reevaluate the RWST level decreases sl owly. Monitor the accident. containment sump along with the RWST. If the containment sump fails to increase with decreas-ing RWST, the accident I
may have been misdiagnosed. I Verify steam generator levels being 5. Steam generator tube
- 5. ruptures may be indicated.
maintained and flow approximately equal to all steam generators. If any steam generator level increases in an ur. expected manner, go to OP3A (Steam Generator Tube Rupture).
- 6. Monitor the condensate storage tank 6. If the lo lo level alarm and upon reaching approximately 10% occurs on the CST, the level, perform a. or b. below operator has approximately 25 minutes to perform items
- a. or b.
- a. Verify a level in the raw water storage reservoir; then open I FCV 436 and 437 (reservoir supply I I to AFW pumps). Allow the AFW pumps to run during the transfer.
L \ N OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND,2 , E S N oATE 07/05/83 PAGE 3 OF 49 TITLE: LOSS OF COOLANT ACCIDENT COMMENTS '3 ACTION f Monitor the AFW flow closely. If flow is lost, trip 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 C (AFW Pump Suction Supply from Fire Water Tank Procedure).
Allow the AFW pumps to run during the transfer. Monitor the AFW flow closely. If flow is lost, trip all three AFW pumps until the transfer is complete, then restart the pumps.
- 7. Monitor the core exit thennocouole temperature for indications of inadequate core cooling. If indications of inadequate core cooling O exit, perfonn Appendix F of this O procedure.
- 8. Verify the following:
- a. PORV PCV 474 closed a. Verify by position PORV PCV 456 closed indication and dis-PORV PCV 455C closed charge pipe tempera-ture indicators.
- b. PORY Backup Valve 8000A open b. Verify, by position indication lights, FORV Backup Valve 80008 open PORY Backup Valve 8000C open valves open and power available.
- c. If any PORY opens during this procedure, verify closure. If the valve fails to close, close the backup valve. -
- d. Monitor W.R. RCS pressure. If RC3 pressure remains <2000 psig and stable-or decreasing, go to step 15.
~
* , t ' q s
g '
'\ '
*l %
+
,[ .
}- %
l
, 8 1 6
_ 22 - , , , , - - - - - - , , . . - . _ , - _
i o EP OP-1 OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 MB[R DATE ( PAGE 4 07/05/83 0 49 TITLE. LOSS OF COOLANT ACCIDENT COMMENTS , ACTION 1 If W.R. RCS pressure begins to increase 9. If the centrifugal pump
- 9. recire, valves (8105 & 8106) after step 8. above, maintain full SI flow were closed due to low RCS until the SI Termination Criteria below prcssure (1220 psig), reopen is met. Continue to monitor throughout this procedure for the below SI the valves when the RCS Termination Criteria, pressure increases above 2000 psig. NOTE: Pressure rising indicates the problem could
- a. W.R. RCS pressure >2000 psig and have been a stuck open FORV.
increasing It may take a minute or two after step 8 for the pressure
- b. M . PZR level 250t change.
- c. AND, RCS indicated subcooling >35'F
- c. If at any time the subcooling Margin Monitor becomes inoperable or is suspect, use the saturation curve to detemine subcooling.
- d. AND, All 4 steam generator NR water levels are greater than 33%
CR Flow to all lo level steam generator is greater than 205 gpm per lo level steam generator.
- 10. If the SI temination criteria in step 9 CANNOT be met, go to step 15.
- 11. If the above SI temination criteria IS 11. CAUTION 1: Automatic rein 1tiation of safety met, RESET SAFETY INJECTION and proceed as below:
injection will not occur after this step since the reactor trip breakers are open. If the operator has indication that an SI is required after this step, he must initiate it manually. CAUTION 2: If loss of offsite power occurs af ter resetting safety injection, it will be l necessary to load the safe- ! guards equipment onto the vital-buses manually. If safety i injection is reinitiated ' manually after the loss of offsite power, the vital buses % will automatically sequentially . load the safeguard equipment., l
NUMBER EP OP-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2
- DATE 07/05/83 PAGE 5 OF 49 TITLE: LOSS OF COOLANT ACCIDENT ACTION COMMENTS ,
If off-site power is lost N after the SI signal is reset, go to Appendix G (Blackout with SI Emergency Loading of Vital Buses).
- a. Reset containment isolation phase A.
- b. Stop both RHR and SI pumps.
- c. Stop one charging pump at a time and evaluate RCS oressure. Main-tain sufficient charging flow to maintain RCS pressure and seal water injection flow. If W.R. RCS pressure drops below 2000.psig or PZR level droos below 50 or RCS subcooling drops below 35*F, reinstate sufficient charging flow to maintain RCS pressure. If W.R. RCS pressure drops below 1850 psig return to step 1 of the Accident O- Diagnostics in OP-0. If charging pumps are restarted after this step, add 15'F of subcooling to the SI termination criteria every time the pumps are restarted.
- d. Verify AC turbine bearing oil backup d. Verify the unit goes on pump and hi pressure seal oil pump turning gear at 0 RPM.
running after oil pressure decays to 11 psig and turbine bearing lift pump starts at 600 RPM turbine speed.
- e. Establish charging flow to maintain e. Charging at a rate RCS pressure, greater than normal might be required in
- 1) Open instrument air valves order to maintain PZR FCV-584 and 682. pressure and level.
- 2) Check open or open normal charging valve 8146.
- 3) Close or check closed charging to auxiliary spray valves 8145 and 8148 and alt. charging valve 8147,
- 4) Open charging line isolation i valves 8107 and 8108. :
i
NUMBER EP OP-1 1 AND 2 DIABLO CANv0N POWER PLANT UNIT NO(S) OATE 07/05/83 PAGE 6 OF 49 i TITLE. LOSS OF COOLANT ACCIDENT i COMMENTS , ;. ACTION
- 5) Automatic PZR level i
-' 5) Adjust HCV-142 and FCV-128 or recipro control may not be cal charging pump speed to achieve RCP seal flow and charging flow as possible at this required to maintain pressurizer time due to the level greater than 22%. TAVG signal inaccura-cies (if RCP's are tripped), or TAVG ; being out of the nomal control band.
- 6) Open RCP seal return valves, MO 8100 and 8112. Check seal return flow nomal .
- 7) Close the BIT inlet and outlet valves 8803A and 8 and 8801A and B.
- f. Continue to menitor the Primary System.
If W.R. RCS Press drops below 1850 psig or PZR water level drops below 22". or l I RCS indicated subcooling drops below 35'F, reinitiate SI manually and return to OP-0 diagnostics unless this has already been perfomed. If SI is reinitiated add 15*F to the SI TERMINA-TION criteria prior to the second termination of the pumps.
- g. Establish nomal letdown
- 1) Verify containment area radiation 1) Containment area hi monitor reading approximately post- radiation may mean accident level. fuel damage. If cont. hi radiation exists, do not estab-lish letdown out-side containment.
Establish letdown to the PRT if let-down is required.
- 2) Open letdown valves LCV-459 and 460.
- 3) Open letdown isolation valve 8152.
- 4) Open one 75 gpm letdown orifice valve.
I I
NUMBER EP OP-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND* 2
- REVISION 6 _
DATE 07/05/83 PAGE 7 CF 40 TITLE: LOSS OF COOLANT ACCIDENT ACTION COMMENTS ] i
- 5) Verify PCV-135 opening by observing 5) Monitor PZR level and letdown flow. W.R. RCS Press to ensure they remain >22%
and 1850 psig during this step.
- h. Establish VCT makeup and transfer charging pumps suction to VCT.
- 1) Adjust VCT makeup blend to the value 1) This assures the indicated on the boron measurement primary system will system. not be diluted during the recovery actions.
- 2) Open VCT outlet valNes LCV-112B and l C after VCT level normal.
- 3) Close RWST to charging pump suction O valves 8805A and B. l
- 4) Verify oivert valve LCV-112A in AUTO.
- i. Verify at least one RCP running or i. The criteria given in verify a bubble in the PZR and estab- OP-0 for stopping the lish conditions for starting at least RCP's on low pressure one RCP. If conditions for starting a still apolies: Check SI RCP exists, start at least one RCP. pump flow and stop RCP's Attempt to start RCP 1 or 2 so that at W.R. RCS pressure 1220 pressurizer spray will be available. psig. Also, if pressure drops below 1220 psig close the centrifucal charging pump recirc.
J. Stop all 3 diesel generators if off- valve (8105 & 8106). The site power is available and place recire. valve shall be diesel generator control switches reopened if pressure is in AUTO. restored above 2000 psig.
- k. With pressurizer level greater than 22".,
verify pressurizer heaters controlling pressure.
- 1. Continue to monitor the condensate storage tank level and transfer the AFW pumps to an alternate source if p low level is approached.
i%)
[g OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 07/05/83 PAGE 8 OF 49 TITLE: LOSS OF COOLANT ACCIDENT COMMENTS ,.j ACTION _ i
- 12. ' Verify. using the RCS subcooling monitor that 50*F subcooling is present.
- 13. The criteria tripping
- 13. If 50*F subcooling is present and can be reactor coolant pumps maintained, proceed witha normal cool- on low pressure will down using Operating Procedure L-5, if not apply if a cooldown required, to perform repairs. If repairs using Operating pro-are not required, maintain hot standby cedure L-5 is performed.
conditions until authorized to proceed by the Plant Superintendent. If 50*F subcooling is not indicated, attempt to establisii 50 3T subcooling by steam dump from the steam generators to the condenser or atmosphere. \ a. If steam dump at the ' a. If steam dump is necessary, reduce reduced pressure the steam generator pressure to setting is used to maintain a RCS cooldown rate of less maintain subcooling, than 50*F/HR, consistent with the proceed to cooldown CVCS makeup capability. the plant using Operating Procedure L-5 (Plant Cooldown from Minimum Load to Cold Shutdown).
- b. If 50*F subcooling can be achieved with steam dump, proceed with the cooldown using L-5. If 50*F sub-cooling cannot be maintained go to step 15.
- 14. If 50*F RCS indicated subcooling cannot be established, REINITIATE SAFETY INJECTION and return to OP-0 Diagnostics, step 1.
- 15. If this is the case,
- 15. If closing the PORV's in step 8 failed to then we probably have recover the RCS pressure, maintain MAX SI flow and proceed to step 16. an unisolatable break in the primary system.
If SI tennination criteria in step 9 could not be met, maintain MAX SI flow and proceed to step 16. If 50*F subcooling cannot be maintained in step 13 above, REINITIATE SI and proceed to ( )n step 16.
NUMBER EP OP-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 r.EvtSION 6 DATE 07/05/83 PAGE 9 OF 49 TITLE: LOSS OF COOLANT ACCIDENT ACTION COMMENTS j u
- 16. If any SI equipment has failed, attempt to operate the equipment locally or from the control room. Effect repairs if necessary.
- 17. If wide range RCS pressure is above 165 17. Restart the RHR pumps if RCS pressure decays to psig, stable or increasing, reset safety 165 psig after this step.
injection and stop both RHR pumps.
- 18. If the RCP's are operating, stop all 4 RCP's after: 18. If CCW is lost to the RCP's, stop all pumps within 5 minutes and maintain seal water flow. Monitor the conditions for stopping RCP's throughout this
- procedure. Conditions for stopping RCP's should l continually be monitored '
l during this procedure.
- a. Verifying at least one charging and SI pump are delivering flow and
- b. W.R. RCS pressure decreases to less than 1220 psia.
- 19. If W.R. RCS pressure decreases below the 19. A large break LOCA is steam generator's pressure, verify indicated.
RWST level decreasing rapidly. Main-tain maximum SI flow until the RWST Lo Level RHR Pump Trip occurs (trip the RHR pumps at 33". if the automatic pump trip fails to occur), then perfom Appendix A.
- 20. If W.R. RCS pressure is decreasing or 20. A small break LOCA is stable and is above 1065 psig, con- indicated. The instruc-tinue with the steps belcw. tions given in step 20 will aid in the cooldown and depressurization.
- a. Reduce steam generator pressure to 865 a. Reducing steam psig using steam dump by methods b or c pressure will lower below. the RCS oressure and temperature.
'O
NUMBER EP OP-1 otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6 OATE 07/05/83 PAGE 10 OF gg TITLE: LOSS OF COOLANT ACCIDENT ACTION COPHENTS 3 5
- b. Continue to monitor 3
- b. If the condenser is available, open the }
main steam isolation valves and dump steam RWST level. As RCS to the condenser using the steam header pressure decreases pressure mode. SI flow will increase and RWST level decrease will accelerate. If l pressurizer level has ( been lost, monitor PZR level indication for its return.
- c. If the condenser is not available, use the 10% atmospheric dumps,
- d. Maintain a RCS cooldown no greater than 50*F/HR.
1 21 . Monitor RWST level closely. If the RWST 21. The cooldown should 1 Lo Level Alann is iminent, perform increase SI flow and step 24.e. If the alann is not imminent, decrease RWST level. j continue with step 22.
- 22. If containment Hi-Hi pressure has initiated containment spray:
- a. Verify the additive tank level is decreasing and that the entire tank is discharged.
- 23. Periodically check the auxiliary building radiation monitors for ECCS leakage if I Appendix A has been perfonned. If leakage is found, attempt to isolate the leakage; I however, do not interrupt ECCS flow at any time.
- 24. If Appendix A, LOCA Injection /Recircula-tion Changeover Procedure, has not yet been perfonned, continue to monitor the RWST level and prepare for Appendix A in the following manner,
- a. At the 480 volt vital load centers a This will allow F and H, close the breakers for the operation of valves following valves: during Appendix A.
DO NOT make any 8980 RHR pump supply from RWST va'1ve operation at 52-lF-31. this time. 8976 SI pump supply from RWST 52-lH-20.
NUMBER EP OP-1 DIABLO CANYON PCWER PLANT UNIT NO(S) 1 AND,2 , REVISION 6 DATE 07/05/83 PAGE 11 OF 49 D TITLE; LOSS OF COOLANT ACCIDENT ACTION COMENTS -
- b. Reset the SI, Phase B isolation and b. Reset only. Do not containment spray isolation signals. start or stop any SI equipment.
Close (CUT IN) the series contactors for c. This will allow oper-
- c. ation of valves during the following valves using the toggle switches in the control room. (VB-2) Appendix A. 00 NOT make any valve oper-
- 8809A and B, RHR pumps. Injection to cold ations at this time.
legs. 897/,A and B, S.I., Pump Recirc. 8982A and B, RHR pumps suction from containment sump.
- d. If the RCS pressure is greater than 1500 d. During cold leg recir-psig (shutoff head of the SI pumps), culation, no recirc. path shutdown these pumps prior to trans- is available to these ferring to cold leg recirculation. pumps.
- e. Maintain maximum SI flow until the RWST low level RHR pump trip occurs. (Trip the RHR pumps at 33% RWST level if the automatic trip fails, then perfom Appendix A.)
DO NOT PROCEED BEYOND THIS STEP UNTIL APPENDIX A HAS BEEN PERFORMED.
- 25. If containment spray has been initiated, 25. Containment spray should prepare to provide RHR spray as follows continue for 2 hours in steps 26 through 31. using RHR for iodine removal. If an RHR Train has failed, temi-nate containment spray.
DO NOT use the operating RHR Train for containment spray.
- 26. Check that the entire content of the spray additive tank has been injected.
- 27. Stop both containment spray pumps on receiving the RWST level lo lo alarm.
Verify tank empty on RWST indicators.
- 28. Close the No. 1 RHR to Cold Leg Injection Valve (8809 A).
-y , -
NUMBER E OP-1 otAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 07/05/83 TITLE: LOSS OF COOLANT ACCIDENT
~
- i COMMENTS ACTION e
~
- 29. Open the RHR Pump 1-1 to Spray Ring Valve (9003A).
l
- 30. Close the Co.'tainment Spray Pump Discharge Valves (9001A and B).
31 . Containment spray may be terminated after f the 2 hour period when the containment pressure has been reduced to approximately 0 psig.
- 32. To tenninate spray, proceed as follows:
i
' a. Close the RHR Pump l-1 to Spray Ring Valve (9003 A)
- b. Open the No.1 RHR-to Cold Leg Injection Valve (8809 A).
- c. Regulate No.1 RHR pump flow using its hand control valve (HCV-638) to maintain pump motor current less than 57.5 amps. (VB-1)
- 33. The systems are now lined up for the cold leg recirculation phase. Continue to operate in this manner for 19-1/2 hours.
During this period, make the following 33. DO NOT make any valve motor operated valves available by closing changes after making their 480V breakers at the vital load the valves available. centers. 8802A SI pump No. I discharge to hot legs 52-lF-48. 8835 SI pump comon discharge to cold legs 52-lG-24. 8703 RHR pumps comon discharge to hot legs 52-lG-56. 8802B SI pump No. 2 discharge to hot legs 52-1H-26.
NU B E OP-1 OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 RE 07/05/83 DATE l PAGE 13 OF 49 l TITLE: LOSS OF COOLANT ACCIDENT l COMMENTS ACTION 1 T
- 34. During the cold leg recirculation phase, the Shift Foreman will fann the plant operators into critical plant systems and equipment assesment teams. The systems or equipment to receive the greatest attention will be detennined by the Shift Foreman and will be based on knowledge of past system /
e',uipment reliability and service. This assesment function may be perfonned inside or outside the control room as conditions warrant. The critical parameters to be assessed will be detennined by the Shift Foreman. The Shift Foreman.will consider the following list of critical systems which may require assesment.
- a. ECCS systems
- b. AFW systems
- c. Safeguards Vent. systems
- d. Off site power availability
- e. Diesel Generators
- f. Instrument air systems
- g. Liquid and Gas Radwaste systems
- h. Containment Fan Coolers
- 1. Component Cooling Water system
- j. Auxiliary Saltwater system
- k. Condenser and Circ. Water System
- 1. Steam dump system
- m. Makeup water system
- 35. Continue to operate the ECCS systems in the Cold Leg Recirculation MODE for 19-1/2 hours, then perform Appendix B, Cold Leg Recirculation /
Hot Leg Recirculation Changeover Procedure. Continue to operate in the Hot Leg Recirculation Mode until authorized by the Plant Superintendent to tenninate hot leg recirculation. A i ! WJ
NUMBER EP Op-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6 DATE 07/05/83 PAGE 14 OF 49 TITLE. LOSS OF COOLANT ACCIDENT 5 APPENDIX A
~
i LOCA INJECTION / RECIRCULATION CHANGE 0VER PROCEDURE SUBSEOUENT OPERATOR ACTIONS COMMENTS l ACTION
- 1. All steps listed below must be 1. CAUTION: If a loss of carried out expeditiously, in a off-site power has precisc orderly sequence. Do occurred in coincidence not interrupt the operation until with the LOCA and all 3 all actions are completed. When diesel generators are both ECCS trains are initially running and supplying the vital busses, continue available and a valve fails to with these instructions respond or to complete its de-manded operations, postpone any as written. If a diesel corrective action until the sub- generator has failed, go sequent operational steps are to Appendix E (Loss of Off-Site power During perfomed.
LOCA with Loss of Diesel Generator) for additional guidance before proceeding
- 2. Monitor RWST level closely. If the RHR pumps do not trip at 33", trip them manually.
- 3. If during this opcration the RWST approaches L-Lo 11 vel, stop all pumps taking suction from the RWST.
Restart pumps after the RHR system is aligned to provide suction. f
- 4. This step may be delayed
- 4. At the vital 480 volt load centers until time permits, F and H, close the breakers for the following valves H not already perfomed.
i 8980 RHR pumps supply from RWST 52-lF-31. 8976 SI pump supply from RWST l I 52-lH-20
- 5. Reset SI, Phase B isolation and containment spray signals g not already reset.
O o
NUMBER EP OP-1 1 AND 2 REVIS;ON 6 DIABLO CANYON POWER PLANT UNIT NO(S) . .
~
DATE 07/05/83 PAGE 15 OF 49 m LE: LOSS OF COOLANT ACCIDENT
\
- APPENDIX A (cont.)
ACTION COMMENTS
- 6. If off-site power is available, shutdown all 3 diesel generators and leave them in Auto if this has not been performed.-
l
- 7. Close (cut in) the series contactors for the following valves from the toggle switches in the control room if not already CUT IN.
8809 A & B RHR pumps injection to cold legs. 8974 A & B SI pumps recirculation. 8982 A & B RHR pumps suction from sump.
% 8. With the SI, charging and possibly the spray pumps still taking suction from the RWST and the RHR pumps tripped at 33% in the RWST, proceed to transfer RHR suction to the containment sump as follows in steps 9 thru 29.
Monitor RWST level, trip all pumps taking suction from the RWST upon reaching Lo-Lo Level in the tank. Restart pumps after RHR suction supplied.
- 9. Check that the containment recirc-ulation sump level indicato.s read at least 40% to provide adeouate NPSH to the RHR pumps.
- 10. Close the two RHR heat exchanger outlet crosstie valves (8716A & B).
- 11. Close the No. 2 RHR pump nomal suction valve (8700B).
(3 V t e
N 1 AND 2 E' S ON otABLO CANYON POWER PLANT UNIT NO(S) OATE 07/05/83 PAGE 16 OF 49 l ) TRLE: LOSS OF COOLANT ACCIDENT APPENDIX A (cont.) COMMENTS ACTION
- 12. Open the No. 2 RHR pump suction valve from the containment recirc-ulation sump (8982B).
- 13. Open the component cooling water outlet valve from No. 2 RHR heat exchanger (FCV-364.)
- 14. Restart No. 2 RHR pump and check flow to the reactor vessel (VB-1).
- 15. Close the safety injection pump recirculation valves (8974A & B).
- 16. Open the safety injection pump suction from RHR pump no. 2 (8804B), Check for increased safety injection pump flow and pressure.
- 17. Close the safety injection pumps 17. This step may be delayed if breakers normal suction valve (S976) from in step 4. have not the RWST.
been racked in.
- 18. Open the alternate suction valves for the centrifugal charging pumps (8807A & B). Check for increasing charging pump flow and pressure.
- 19. Close the no. 1 RHR pump norral suction valve (8700A).
- 20. Open the no.1 RHR pump suction valve from the containment recirc-ulationsump(8982A). .
- 21. Check the level in the recircu-lation sump again for adequate NPSH.
- 22. Open the component cooling water outlet valve from no. 1 RHR heat exchanger (FCV-365).
l l
( NUMBER EP OP-1 OtABLO CANYON DOWER PLANT UNIT NO(S) 1 AND 2 - REVISION 6
- DATE 07/05/83 PAGE 17 OF 49 TTTLE: LOSS OF COOLANT ACCIDENT APPENDIX A (cont.)
e ACTION COMMENTS
- 23. Restart the no. 1 RHR pump and check for flow to the reactor vessel.
- 24. Open the centrifugal charging pumps alternate suction valve from RHR pump no. 1 (8804A). Check for increased charging pump flow and pressure.
- 25. Close the charging pumps nomal suction valves from the RWST (8805A & B).
- 26. Close the RHR pumps nomalcsuction 26. This step may be delayed supply valve from the RWST (8980). if breakers in step 4 have not been racked in.
- 27. When the lo 10 level point is 27. Trip any other engineered t reached in the RWST, trip both safeguard pumps that are containment spray pumps. still taking suction frem the RWST. This will only be necessary if the preceeding steps have not been compleied prior to reaching the lo lo level set point.
- 28. If step 4, 17 and 26 were delayed, perform these steps at this time.
- 29. If either RHR pump failed, either containment sump to RHR suction valve failed to open (valves 8982A or B) or either RHR Train to centrifugal charging pumps or SI pumps suction valves 8SO4A or B failed to open, go to Appendix D (RHR Train Failure).
- 30. If W.R. RCS pressure is less than 1065' 30. Large Break LOCA psig, return to step 25 of the LOCA ,
procedure. Small Break LOCA If W.R. RCS Dressure is creater than 1065 ! Og psig, return to LOCA procedure step that gQ was lef t to perfom this appendix. l
)
NUMBER EP OP-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 ANO 2 DATE 07/05/83 PAGE 18 OF 49 m LE: LOSS OF COOLANT ACCIDENT APPENDIX B .j j COLD LEG RECIRCULATION / HOT LEG RECIRCULATION CHANGE OVER PROCEDURE COMMENTS ACTION Hot Leg Recirculation Phase
- 1. Approximately 19-1/2 hours after the injection phase, the recirc-ulation flow path is changed from the cold legs to the hot legs.
- 2. It is important during this phase to insure that two separate and redundant trains of both RI:R and safety injection pumps are estab-lished.
- 3. Close the no. 1 RHR pump cold leg injection valve (8809A).
- 4. Close the RHR pump no. 1 valve to the containment spray header (9003A) if it is open.
- 5. Check open the RHR pump no. I valve to the safety injection pumps and centrifugal cha ging pumps (8804A).
- 6. Shut down both centrifugal charging pumps and close both BIT inlet valves (8803A and B).
- 7. Shutdown no. 1 safety injection pump.
- 8. Close no. 1 safety injection pump discharge crosstie valve (8821A).
l 9. Open the no. I safety injection pump hot leg injection valve (8802A).
- 10. Start no. I safety injection pump and check for rated flow of approximately 650 gpm.
- 11. Close the no. I safety injection pump nonnal suction valve (8923A).
NU BE ' DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 E ON 6 DATE 07/05/33 PAGE 19 OF 49 TITLE: LOSS OF COOLANT ACCIDENT APPENDIXB(contd I
; ACTION COMMENTS
- 12. Close the no. 2 RHR pump cold leg injection valve (88098).
- 13. Check closed the no. 2 RHR pump valve to the containment spray header (90038).
- 14. Check open the no. 2 RHR pump to the safety' injection pumps alternate suction valve (88048).
- 15. Shutdown no. 2 safety injection pump.
- 16. Close the no. 2 safety . injection pumo discharge crosstie valve (8821B).
^ 17. Close the safety injection pumps com.on discharge valve (8835) to the cold legs.
- 18. Open the no. 2 safety injection pump hot leg injection valve (88028).
- 19. Start the no. 2 safety injection pump and check for rated flow of approximately 650 gpm.
- 20. Close the no. 2 safety injection pump normal suction valve (8923B).
- 21. The systems are now set up in two completely separate and redundant trains with each RHR pump supplying .
a separate SI pump. No containment spray or direct RHR recirculation are utilized.
- 22. If desired, direct RHR recircula-tion to the hot legs may be used simultaneously as follows:
1 ! a. Open the No. 1 RHR train
- p discharge crosstie valve (8716A).
l O t
i i NUMBER EP OP-1 I and 2 REVISION 6 DIABLO CANYON POWER PLANT UNIT NO(S)
- DATE 07/05/83 PAGE 20 OF 49 TITLE LOSS OF COOLANT ACCIDENT 4
APPENDIX B (cont.) l 3 l COMMENTS ACTION
- b. Open the comon RHR hot leg injection valve (8703).
- c. Adjust the RHR train No I flow (HCV-638) to insure adequate suction to the SI pump and to maintain RHR pump motor current less than 57.5 amps.
- 23. If containment spray is desired for any reason (such as loss of fan cooler unit) it may be accomplished as follows:
- a. Open the No. 2 RHR Train valve to the containment spray header (90038).
- b. No flow control is available in this operation, so SI pump suction pressure and RHR pump motor current must be closely watched.
Divide the auxiliary saltwater system into two separate 24. If Accendix
- 24. E was used to trains: correct a failed Ooen idle CCW heat exchanger outlet valve (FCV-430 diesel generator
- a. problem, do not or FCV-431). separate the two
- b. Open saltwater inlet valve on idle heat exchanger FCV-602 or FCV-603).
trains.
- c. Open stop valves of idle heat exchanger in the water box vent lines to air removal tank (el.119').
- d. Verify CCW heat exchanger saltwater outlet valve (SW-65 or SW-66) throttled at 56' to maintain water box volume,
- e. Verify that operating standby ASW pump discharge valve is open (SW-54 or SW-55).
- f. Close motor operated pump discharge crosstie valves (FCV-495 and FCV-496).
- g. Verify approximately equal motor current on each ASW pump motor and equal flow through each heat ex-change.
Line up the component cooling water system for long tenn 25. Same note l 25. as 24 above.
- recirculation
- a. Verify that the idle CCW heat exchanger outlet valve (FCV-430 or FCV-431) is open.
- b. Open or verify open FCV-355 Header "C" supply.
- c. Close pump suction header crosstie valve (CCW-4) between headers "B" and "C".
- d. Close CCW Pump 1 discharge valve (CCW-18) to header "B".
"A".
- e. Close CCW Pump 2 discharge valve (CCW-16) to header
- f. Close CCW Pump 3 discharge valve (CCW-17) to header "B". ,
- g. Isolate CCW header "C" from header "B" by closing valve CCW-24.
SER P OP-1 OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 07/05/83
- PAGE 21 OF 49 TITLE: LOSS OF COOLANT ACCIDENT APPENDIX C I
AUXILIARY FEED PUMP SUCTION SUPPLY FROM FIRE WATER TANK j The Operator has 20 minutes to perfbm this operation after the lo lo level alam 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 impor- ; tant to expedite this procedure and reestablish AFW flow to the steam [ generators prior to the reactor losing its heat sink. COMMENTS ACTION
~ i Using the attached drawing, proceed to supply the AFW pumps suction from the fire water tank.
Close or verify closed MU-0-284 1. Closing these valves pre-
- 1. vents losing fire water and MU-0-286. 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.
- 5. Open FP-0-306 and FP-0-307.
- 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 the auxiliary feedwater pumps and vent the pump casings if required to remove sir.
u
.a 1
I} -4 9 4 5 6 6 s- ,_ 9z o o l
- a Fire Water ci 5 To M.U. h $
Tank . L Filters $ F 16 g Sealed FP-0-4 Open Open y a
~ m Valve - g T e -r Open
_. gjose V HU-0-325 i g
.07 J L Suction
#a Close i 1
S wA - I HO-O RawWateriea% [m -29 g,g7 1f . 284 jg j From Raw ' P I 1[ Water Reservoir - Package Close Boller M U Filter STR
'M '
Bypass
' Blowdown g8 ttu 286 ,o,z FCV-436 u l-297 Sealed
~
' AIN 1 Va ve Ppl-1 ^- Open m w
i7i 6 @ z QSN o FCV-437 " Fire Water Tank to gm ?~ l AFW Pump Suction g AFW , I Pp 1-2 Open 1-3 L
. e .o;w .s
N E' OlABLO CANYON POWER PLANT UNIT NO(S) 1 AN0 2
, , E SON 6 DATE 07/05/83 m
PAGE 23 OF 49 TITLE: LOSS OF COOLANT ACCIDENT APPENDIX D j RHR TRAIN / COMPONENT FAILURE A. FAILURE IN RHR TRAIN NO. 2 ACTION COMMENTS
- 1. If RHR pump No. 2 failed, con- 1. Monitor RWST level, when tainment sump to RHR valve the level reaches the 8982B or RHR pump No. 2 to SI lo lo alarm setpoint, suction valve 8804B failed to trip all safeguards pumps open proceed with steps a. to taking suction from the
- d. to provide charging and SI tank.
pump suction from RHR pump No. 1. ,
- a. Verify RHR pump No.1 crosstie valves to SI .
pump suction 8807A or B open.
- b. Close or verify closed Train No. 2 to SI pump suction valve 88048.
- c. Throttle HCV 638 to ensure adequate suction for the SI and centrifugal charging pumps (approximately 20 psig above containment pressure) while maintaining RHR pump motor current less than 57.5 amps.
- d. Return to the LOCA procedure step that was left to perfom Appendix A.
t (
l NUMBER EP OP-1 OlABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6 j _ 07/05/83 l
- DATE TITLE: LOSS OF COOLANT ACCIDENT j
APPENDIX D
.g i
B. FAILURE IN RHR TRAIN NO. 1 COMMENTS ACTION
- 1. Monitor RWST level,
- 1. If RHR pump No.1 failed, containment sumpe to RNR valve 8982A or RHR pump when the level reaches No.1 to charging pumps suction valve the lo lo alann set-8804A failed to open, proceed with point, trip all safe-steps a. to d. to provide charging guards pumps taking and SI pump suction from RHR pump suction from the tank.
No. 2.
- a. Verify RHR pump No. 2 crosstie valves to SI pump suction 8807A l
or B open,
- b. Close or verify closed Train No. I to SI pump suction valve 8804A.
- c. Throttle HCV 637 to ensure ade-quate suction for the SI and centrifugal charging pumps (approximately 20 psig above containment pressure) while maintaining RHR pump motor current less than 57.5 amps.
- d. Return the the LOCA procedure step that was left to perform Appendix A.
1 1 I
1 UMBER P OP-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 7 ATE 07/05/83 PAGE 25 OF 49 TITLE: LOSS OF COOLANT ACCIDENT APPENDIX E
- i LOSS OF OFF-SITE POWER DURING LOCA WITH LOSS OF DIESEL GENERATOR ACTION COMMENTS A. If a diesel generator fails during the LOCA procedure, continue with the LOCA procedure as written until Appendix A (LOCA Injection /Recircu-lation Change Over Procedure) is to be perfomed. Then follow the guidance given below for the alignment for cold leg and hot leg recirculation.
B. Diesel Generator Failure Diesel Generator 1-1 Fai ure
- 1. If diesel generator 1-1 has failed, the following steps O should be used to align the system for cold leg recircu-lation
- a. Verify the following pumps are running.
ASW Pumps 1 and 2 AFW Pump 3 Charging Pumps 1 and 2 CCW Ptsnps 1 and 2 SI Pump 1 C.S. Pump 1 RHR Pump 1
- b. With diesel generator 1-1 failed, do the following steps in the order given below in Appendix A (LOCA Injec-tion / Recirculation Change OverProcedure).
Steps 2,3,4,5,7,8,9,10,15,18, 19, 20, 21, 22, 23, 24, 25, 26, 27, 28, then do step 17. g
I OtABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 R IS ON DATE 07/05/83 PAGE 26 OF 49 i TITLE: LOSS OF COOLANT ACCIDENT APPENDIX E (Cont.) j ACTION COMMENTS
- c. Throttle HCV-638 to provide adequate suction for the SI and charging pumps (approx-imately 20 psig above con-tainment pressure while maintaining RHR pump motor current less than 57.5 amps).
- d. Verify the cold leg recirculation flow path as follows:
RHR pump 1 from containment sump to cold legs 1 and 2 SI pump 1 from RHR pump 1 to all cold legs, charging pumps 1 and 2 from RHR pump 1 to all cold legs via the BIT. . l Containment spray pump 1 from RWST to spray headers.
- 2. Proceed as follows after 19-1/2 hours for hot leg recirculation.
- a. Perfom the following steps in the order given below in Appendix B (Cold Leg Recircu-lation/ Hot Leg Recirculation Change Over Procedure).
Steps: 1,3,4,5,6,7,8,9,10,11.
- b. Close HCV-638 RHR discharge valve.
- c. Open 8716A RHR pump crosstie valve.
l d. Open 8703 RHR to hot legs l 1 and 2.
- e. Throttle open HCV 638 to hold an RHR pressure greater than 29 psig above containment pressure or less than 57.5 amps on RHR I I pumps.
M8ER EP OP-1 DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND,2 ,
,S DATE 07/05/83 PAGE 27 OF 49 TITLE: LOSS OF COOLANT ACCIDENT l
?!
APPENDIX E (Cont.) s COMMENTS ACTION
- f. Verify hot leg recirculation flow path as follows:
RHR pump 1 from containment sump to SI pump 1 suction via valves 8804A, 8807A and B and to hot legs 1 and 2 via valve 8703. SI pump 1 from RHR pump i to RCS hot legs 1 and 2 Diesel Generator 1-2 Failure
- 1. If diesel generator 1-2 has failed the following steps should be used to align the system for cold leg recircu-j lation.
- a. Verify the tollowing pumps are running.
ASW Pumps 1 AFd Pumps 2 and 3 Charging Pump 1 CCW Pumps 1 and 3 SI Pumps 1 and 2 C.S. Pump 2 RHR Pump 2
- b. With diesel generator 1-2 failed, do the following steps in the order given below in Appendix A (LOCA Injection /
Recirculation Change Over Procedure). Steps: 2,3,4,5,7,8,9,10,11,12 13,14,15,16,17,18,25,26,27,28. 1 1 y
NUMBER EP OP-8 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6 DATE 07/05/83 TITLE: 1.055 0F COOLANT ACCIDENT APPENDIX E (Cont.) ch I
'. ACTION _ COMMENTS
- c. Throttle HCV-637 to provide adequate suction for the SI and charging pumps (approxi-mately 20 psig above contain-ment pressure while maintain- ,
ing RHR pump motor current less than 57.5 amps).
- d. Verify the cold leg recircu-lation flow path as follows:
~
Containment spray pump 2 from RWST to spray headers. RHR pump 2 from containment sump to cold legs 3 and 4,' SI pumps 1 and 2 from RHR pump 2 to all cold legs, charging pump 1 from RHR pump 2 to all cold legs via the GIT.
- 2. Proceed as follows after 19-1/2 hours for hot leg recirculation.
- a. Perform the following steps in the order given below in Appendix B (Cold Leg Recircu-lation/ Hot Leg Recirculation Change Over Procedure).
Steps: 1,6,7,8,9,10,12,13,14, 15,16,18,19.
- b. Close 8807A and B (RHR Pump No. 2 to charging pumps).
- c. Close HCV-637 RHR discharge
. valve.
- d. Open 8716B RHR crosstie valve.
- e. Open 8703 RHR to hot legs 1 and 2.
l l l
1 l N DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 , EV S ON 6 DATE 07/05/83 PAGE 29 OF 49 TITLE: LOSS OF COOLANT ACCIDENT i APPENDIX F (Cont.) i ACTION COMMENTS
- f. Throttle open HCV-637 to hold an RHR pressure greater than 20 psig above contain-ment pressure or less than 57.5 amps on the RHR pumps. .
- g. Verify the hot leg recirculation flow path as follows:
RHR pump 2 from containment sump to SI pumps 1 and 2 suction, via valve 8804B and to hot legs 1 and 2 via 8703. SI pumps 1 and 2 from RHR pump 2 to all RCS hot legs. Diesel Generator 1-3 Failure
- 1. If diesel generator 1-3 has failed, the following steps should ce used to align the system for cold leg recirculation.
- a. Verify the following pumps are running ASW Pump 2 AFW Pump 2 Charging Pump 2 CCW Pumps 2 and 3 SI Pump 2 C.S. Pumps 1 and 2 RHR Pumps 1 and 2
- b. With the diesel generator 1-3 failed, do the following
- steps in order given below in Appendix A (LOCA Injection / Recirculation Change 1 OverProcedure).
Steps: 2,3,4,5,7,8,9,10,11,12,13 14,15,16,17,18.19,20,21,22,23,24, ' 27,28. _ O V - l s
l l 8 P OP-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 S ON 6
- DATE 07/05/83 PAGE 30 OF 49 TITLE. LOSS OF COOLANT ACCIDENT b
APPENDIX E (Cont.) ~j ACTION COMENTS
- c. Throttle HCV-638 and 637 to provide adecuate suction for the SI and charging pump (approximately 20 psig above containment pressure while maintaining RHR pump motor current less than 57.5 amps).
- d. Verify cold leg recirculation flow path as follows:
Containment spray pumps 1 and 2 from RWST.to spray. headers. Rha pump No. 2 from containment sump to cold legs 3 and 4 and ! to Si pump No. 2. SI pump No. 2 from RER No. 2 to all cold legs. RHR pumo .'.c. I from containment sump ta coid leg 1 and 2 and to No. 2 centrifugal charging pumo. Centrifugal charging pump Nc. 2 from 9HR Ptinp No. 2 to all cold legs via the BIT.
- 2. Proceed as follows after 19-l/2 nours for hot leg recirculation.
- a. Perfonn the following steps in the order given in Appendix B (Cold Leg Recirculation / Hot Leg Recirculation Change Over
, Procedure). Steps: 1,2,3,4,6,12,13,14,15,16, 17,18,19,20, then perfonn step 22. O
s
~
~; .
i NUMBER EP Op-1 OtABLO CANYON POWER PLAN UNIT P40(S) 1 AND 2 ,
's' '
DATE 07/05/83 i PAGE 31 OF 49
~ ; TITLE: LOSS OF COOLANT ACCIDENT I <
_ APPENDIX E (Cont.) }
! 4 ACTION COMMENTS y
!, b. Close1 3804A RHR supply b. All BIT inlet and outlet to charging pumps. valves will not close i l ' with a failure of 1-3
' diesel generator. This j ' step prevents flow to the cold legs via the
, charging pumps and SIT.
- c. Verify hot leg recircu)ation i
flow path'as follows.
' RHR pump 1 from containment sump to hot legs 1 and.2 via
'x HCV-638.
RHR pump No. 2 from contain-l ' ment sump to SI pump No. 2 via 88048. t - SI pump 2 from RHR pump 2 1 to RCS hot legs 3 and 4. I a 1 1
~
r n iA t ld i l' t 0
O NUMBER EO OP-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6 OATE' 07/05/83 TITLE: LOSS OF COOLANT ACCIDENT APPENDIX F , 1 DETEFNINATION OF ADEQUATE CORE COOLING This appendix provides the guidance to detemine 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 themoccuple 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 themocouple readings exceed 1200*F, notify the Shift Foreman that inadequate core cooling exists and go to step 5.
! If there are not 5 or more that exceed 1200'F, discontinue this appendix but continue to monitor the thermocouple readings.
- 3. At the thermocouple incore board in the control room, Monitor 10 core-centered thermocouples. If any 3 of the 10 thermocouples exceed 700*F (Pegged hi) proceed to step 4.
If there are not 3 thermocouples that exceed 700'F, discontinue this appendix but continue to monitor the themoccuple readings.
- 4. If SI flow to the RCS and AFW flow to the steam generators canrot be verified, notify the Shif t Foreman that inadequate core cooling may exist and go to step 5.
If both SI slow to the RCS and AFW flow to the sTe'am generators can be verified, discontinue this Appendix but continue to monitor the themoccuple readings.
- 5. The Shif t Foreman will verify if inadequate core cooling exists using the appropriate steps above. If inadequate core cooling exists the Shift Foreman will direct I operations as follows:
NUMBER P OP-1 DIABLO CANYON POWER PW UNIT NO(S) 1 AND 2 DATE 07/05/83 PAGE 33 OF 49 TITLE: LOSS OF COOLANT ACCIDENT APPENDIX F (Cont.) .I
'5 COMMENT ACTION
- a. Declare a General Emergency Implement the instructions given in Emergency Procedure G-1 regarding on and off-site protective actions.
- b. Attemot to establish SI flow to the RCS and AF4 flow to the steam generators.
- c. Continue monitoring core outlet temperature to determine the ef-fectiveness of the remaining actions. -
- d. DEPRESSURIZE THE RCS ty method 1 or 2 below.
- 1) Dump steam to the condenser 1) THIS IS THE PREFERRED ME HOD.
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 available a drop in RCS pressure suf-to deliver water to the RCS ficient to allow the SI flow required to cool the core.
THEN This method is to be used if Open the pressurizer PORV's. 1) (above) is ineffective.
- e. If no means of depressurization are e. Attempt to establish CCW and available, or if the depressurization seal water flow to the pump; did not result in decreasing core however, if CCW and/or seal exit thermocouple temperatures, water flow cannot be establish-ed, proceed to start a RCP.
THEN The pump must be started to move coolant thru the core. START A RCP if possible. If the RCP fails after starting, replace the lost RCP with any remaining RCP. f] O ( l
8 DIABLO CANYON POWER PLANT UNIT NO(S) , 1,AND 2 yy"1S ON DATE 07/05/83 TITLE: LOSS OF COOLANT ACCIDENT APPENDIX G
~
BLACXOUT WITH SAFETY INJECTION EMERGENCY LOADING OF VITAL BUSSES
- 1. If the vital busses lose voltage prior to resetting the safety injection signal, the vital busses will automatically load the vital equipment given below. Verify the equipment has been loaded by observing breaker lights on the control board.
- 2. If the vital busses lose voltage after the safety injection signal has been reset, load or verify loaded the equipment given below onto the vital busses manually. Allow approximately 4 seconds between loading of each piece of equipment onto a given vital bus. Load or verify that the CFCU are running in low speed.
VITAL BUS VITAL BUS VITAL BUS F G H D/G l-3 D/G l-2 D/G l-1 MCC 1-F MCC 1-G MCC 1-H CC Pp 1-1 SI Pp 1-1 CC Pp 1-2 SI Pp 1-2 h 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 Pp 1-2 AFW Pp 1-1 ASW Pp l-2
- 3. Load the containment spray Pumps only if they were running prior to the blackout.
VITAL BUS VITAL BUS G H l Cont Spray Pp 1-1 Cont Spray Pp 1-2 l 1 1
NUMBER EP OP-I DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND,2 , DATE 07/05/83 PAGE 35 OF 49 O TITLE; LOSS OF COOLANT ACCIDENT APPENDIX H VEP.IFICATION OF ESF FUNCTIONING AND EFFECTIVENESS DURING LOCA The primary function of the Shift Technical Adviser during any emergency is to evaluate plant conditions and advise the Shift Foreman on recovery procedures or actions to be taken to mitigate the consequences of the emergency. This appendix provides a method of evaluating the effective-ness of the ESF system during any LOCA and provides guidance on re-classifying the accident from a Site Emergency to a General Emergency should conditions warrant. The on shift Shift Technical Adviser (or his designated alternate if additional manpower is available) will make this evaluation as the eve'nt progresses and will make the necessary recommendations to the Shift Foreman based on his findings. For all accidents except the LOCAL, the maximum amount of activity which could be released is low enough so that persons located beyond the site boundary are not in immediate jeopardy even under the worst circumstances. In the case of the LOCA, however, it is theoretically possible that a large fraction of the core inventory of the volatile fission products (noble gases and iodines) could be released if one assumes multiple failures of the various engineered safety features. O . In such a case, doses within the LPZ could be very high, particularly to the thyroid gland. Loss of life is possible. As a result, it is imperative that downwind areas of the LPZ be evacuated as soon as possible in a LOCA situation where the functioning and/or effectiveness of the engineered safety feature systems is in doubt. In the case of the LOCA with inadequate core cooling, the major release would not be l expected for at least two hours due to the time required to melt a large fraction of the core and the expected time before any containment failure would be likely. Th.1, early recognition of the signs of ESF malfunction and prompt action in this event can prevent most, if not all, of the exposure of persons within the LPZ. In the event of a LOCA, the Evaluations Coordinator should pay partic-ular attention for signs that the ESF systems have malfunctioned, and if their effectiveness is in doubt, go ahead and classify the accident as a General Emergency and have the Emergency Coordinator notify those agencies given in General Appendix 2 of the emergency procedures and the NRC Operation Center inanediately. This Appendix and worksheets provide a checklist of three major cate-gories of items to look for, and provides criterion to indicate that the various ESF have or have not functioned. In several cases there is more than one indicator to verify the functioning of a particular
'Which includes loss of the primary system heat sink and resultant expulsion of coolant from the primary system to the extent that O safety injection is required.
N BE N 1 AND 2 otABLO CANYON POWER PLANT UNIT NO(S) DATE 07/05/83 PAGE 36 OF 49 TITLE: LOSS OF COOLANT ACCIDENT APPENDIX H (Cont'd) : I
' safety feature. For example, SI pump flow is measured directly by a flow indicator, but can also be inferred from pump operation and l
valve position indicators. If the various indications do not agree, a judgement must be made on the basis of what is considered to be the best evidence. Nomally, however, the conservative course of action l should be followed.
- 1. Worksheet for Verification of ESF Functioning and Effectiveness During a LOCA.
This worksheet is to be used first to check that t'he minimum components in each of the ECCS and containment cooling systems have operated correctly. Although this does not guarantee that they will be effective, it provides reasonable assurance. Conversely, their failure vastly increases the chance of fuel melting or overheating and overpressurization of the containment (thereby Therefore, jeopardizing its ability to retain fission products). classify the accident as a General Emergency unless the minimum i required components in each of the categories have functioned or are irrediately initiateo manually. The worksheet applies only to the injection phase. Although it is also necessary to maintain core cooling during the recirculation phase, the speed with which it must be restored is less cricical. However, if the ability to cool the core is lost, and is not likely to be restored rapidly, a General Emergency is justified. Included on the worksheet is the verification of containment iso-lation valve closure. Post-accident dose calculations are based upon the assumption that containment leakage rate is 0.1%/ day. If the leakage rate exceeds this, the off-site does will increase proportionately. Although it is not possible to rapidly measure l the leak rate, if all major penetrations that lead directly to the stmosphere are closed by at least one valve, the leak rate is probably reasonably low. If at least one valve in each of the paths on the worksheet (Page 39), Item 7, is not closed either automatically or by operator action within abnut 15 minutes, consider the accident a General Emergency.
- 2. Worksheet for Verification of Containment pressure less than Design Pressure This worksheet is used to determine if the internal containment pressure significantly exceeds the design pressure of the structure.
Doubts are cast about the ability of the containment to retain I In
NUMBER EP OP-1 OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6
- DATE 07/05/83 PAGE 37 OF 49 TITm LOSS OF COOLANT ACCIDENT APPENDIX H (Cont'd)
~
i the fission products (at least a maximum leakage rate of 0.1"/ day) if design pressure is exceeded. It also indicates that the ESF are not functioning properly, since the pressure should never get that high if a minimum safeguards train works correctly. The containment is designed for 47 psig coincident with the forces caused by a double design earthquake (0.4g). With no earthquake (or following completion of an earthquake), the containment can withstand 1.5 times the previous pressure, or 70 psig. Figure 1 on the worksheet shows the maximum allowable containment pressure as a function of the earthquake strength. If the curve is exceeced, the accident must be considered a General Emergency.
- 3. Worksheet for Veiification of Containment Radiation Level Within Expectations This worksheet is used to determine the extent of core damage.
Two high range garrna instruments (RE-30 and RE-31) have been installed to measure the internal containment radiation level following a LOCA. Figure 1 on the worksheet shows the calculated response of these instruments as a function of time after a LOCA Oo assuming various degrees of core damage. Any LOCA would be expected to release the activity contained in the coolant and so a reading of this magnitude should not be cause for concern. Similarly, in a major LOCA some cladding failure may occur due to the combined effects of DNB, depressurization, and metal-water reaction. Cladding failure will release some of the activity contained in the gap between the pellet and the cladding. How-ever, the amount of cladding failure should be small. Thus, if the activity in the containment reaches the line labeled "100". gap release," it is indicative of gross core damage and/or the onset of fuel melting. In either case, the ECCS has failed to function as expected and the accident shoulc be considered as a General Emergency. That is, if the containment radioactivity reaches or exceeds the value on Figure 1 for 100% gap release, consider the accident as a General Emergency. If there is any question about the validity of the readings, or if the above instruments have failed, readings can be taken at the containment exterior with protable radiation protection equipment. Specifically, Figure 2 on the worksheet shows similar , data for a CP type instrument located at the exterior surface of I the steel liner (but inside the movable concrete shield) at the equipment hatch. Figure 3 on the worksheet shows the does rate outside the containment concrete wall. The readings at the equipment hatch can be made with an extension probe on a Victoreen J 4
NUMBER E) OP-1 OtABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISION 6 OATE -07/05/83 PAGE 38 OF 49 TITLE: LOSS OF COOLANT ACCIDENT 4 3 i ! APPENDIX H (Cont'd)
'j-Rad Gun. The HPI-1010 would be an appropriate instrument to use for measurements external to the concrete containment wall.
NOTE: Normal background is about 0.015 mR/hr on the HPI-1010. I O
l NUMBER EP OP-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 07/05/83 PAGE 39 OF 49 TITLE: LOSS OF COOLANT ACCIDENT WORKSHEET 1, APPENDIX H ' WORKSHEET FOR VERIFICATION OF ESF FUNCTIONING Jf AND EFFECTIVENESS DURING A LOCA
?
DATE TIME PERFORMED BY :
- 1. BASIC ACCIDENT INFORMATION UNIT DESCRIPTION DATE/ TIME OF OCCURENCE
/
- 2. CENTRIFUGAL CHARGING PUMPS Pump suction valve open_ C 8805A O 8805B a.
- b. BIT inlet valve open O 8803A O88038
- c. BIT outlet valve ooen C 8801A O 88018
- d. Charging pump @ C No. 1 O No. 2 gpm
- e. Flow through FI-917 f.
At least one train must be verified in service by verifying C YES C NO an operable flow path and the pump ON, or by verifying flow through FI-917. O BY TIME
- 3. SAFETY INJECTION PUMPS Pump supply valve from RWST og 8976 a.
- b. Pump suction valve open C 8923A C 89238
- c. Pump discharge crosstie valve open C 8821A C 88218
- d. Pump cold leg discharge open C 8835
- e. SIS pump ON, C No. I lj %. 2 psig 4
- f. RCS pressure 1500 psig C YES C NO opm FI-922 cpm Flow established FI-918 g.
- h. If RCS 1500 psig, at least one train must be ON/A OYES C NO verified in service by verifying an operable flow path and the pump ON, or by verifying flow established through the FI.
BY TIME
- 4. ACCUMULATORS
- a. Accumulators discharge (LI's show low level) No.1 O LIS50 or 951; No. 2 LI952 or 953; No. 3 C LI954 or 955; No. 4 C LI 956 or 957 '
NO psig
- b. RCS pressure <600 psig? O YES O c. At least one LI per accumulator indicates dischar e, if RCS <600 psig.
(V O N/A YES I NO O TIME BY l I l
NUMBER FP OP-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6 OATE 07/05/83 TITLE. LOSS OF COOLANT ACCIDENT WORKSHEET 1, APPENDIX H ,
- 5. RESIDUAL HEAT REMOVAL PUMPS
..j '- a. Pump supply valve from RWST open O 8980 i
- b. Pump suction valve open O 8700A C 87008
- c. HX outlet flow control vhlve open C HDV-638 0 HCV-637
- d. Cold leg injection vilve open_ C 8809A O 88098
- e. RHR pump g C No. 1 O No. 2 RCS pressure <170 psig C YES C N0 psig f.
O FI-970 gpm C FI-971 gpm
- g. Flow established
- h. If RCS <170 psig, at least one train must be verified in service by verifying an operable flow path and the pump ON, or by serif ing flow through the FI. N/A YES O NO BY TIME i
- 6. CONTAINMENT SPRAY AND COOLING Spray additive tank valve open 8992 a.
- b. Spray additive tank valve open I~l8994A 9001A O 89948 9001B g
- c. Spray pump discharge valve open
- d. Spray pump ON. O No. 1 O No. 2
- e. FancoolersOji: No. 1 0; Nc. 2 0 ; No. 3 0 ; No. 4 C ; No. 5 O
- f. Containment Hi-Hi pressure signal received O YES C NO
- g. At least two spray pumps have functioned OR one spray pump and three fan coolers functioned if a containment Hi-Hi pressure signal received.
l O N/A O YES C NO BY TIME INSIDE CONT. OUTSIDE CONTAINMENT
- 7. CONTAINMENT ISOLATION VALVE CLOSURE
- a. Pressure / Vacuum relief closed O FCV-662 O FCV-663 and 664
- b. Purge supply closed O FCV-660 0 FCV-661 i c. Purge exhaust closed O RCV-Il O RCV-12
- d. At least one valve in each of the above flow paths must be closed within 15 minutes O N/A C YES CN0 BY TIME
- 8. If item 2.f. 3.h, 4.c, 5.h, 6.g OR 7.d is NO, consider the accident as a General Emergency BY TIME k
.' l
)
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP OP-1 REVISION 6 O TITLE: LOSS OF COOLANT ACCIDENT DATE PAGE 41 OF 49 07/05/83 i d. WORKSHEET 2 APPENDIX H
- WORKSHEET FOR VERIFICATION OF CONTAINMENT PRESSURE LESS THAN DESIGN PRESSURE PERFORMED BY DATE TIME
- 1. BASIC ACCIDENT INFORMATION UNIT DESCRIPTION DATE/ TIME OF OCCURRENCE /
- 2. EARTHQUAKE FORCE MONITOR (EFM-1)
Peak Earthquake EFM-1 Indicator Peak Readino Adceleration
- a. Longitudinal x 0.01 = g
- b. Vertical x 0.01 = g 1
- c. Transverse x 0.01 = g
- 3. CONTAINMENT PRESSURE 80 - - - -
- - - - - - - ---= -
~
g 79 .PR-932 OPERABLE _-_- - -- G
- b. -
m _ . . . . . . ..-
=
m g (O. --- d E . - _ _ . _ . . . . . ...._._ _ _ . . . . . . . . . _ M 5 PR-932 IMOPERABLE 50 . . - . . - - - - . - ... -- O 40 - - - - - - - 0 0.1 0.2
=
0.3 0.4 PEAK EARTH 0VAKE ACCELERATION (g) Fi 1 Internal Pressure C litv of the Containment Versus Eart e Acceleration
NUMBER P OP-1 otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION DATE 07/05/83 ME LOSS OF COOLANT ACCIDENT
- a. Usingthelargest1$$e$kbtOn^' inks [romtheEFM-1(item 2above) -l and Figure 1 determine: -
; psig
- 1) Maximum allowable pressure with PR-932 operable psig
- 2) Maximum allowable pressure without_ PR-932 operable
- b. Using containment pressure indicator PR-932 or any 2 of 4 of the following indicators PI-934, 935, 936, 937, record containment pressure every two or three minutes for the first 15 minutes of the accident.
TIME PRESSURE (PSIG)_ INSTRUMENT ID O TIME BY
- 4. DESIGN LIMITATION (complete 3.a OR 3.b)
- a. If PR-932 was used in item 3.b to detemine containment pressure, are any pressure readings greater than the maximm allcwable pressure with PR-932 l
operable (item 3.a.1): YES ] NO C 2R
- b. If any 2 of 4 of the following indicators, PI-934, 935,*936, or 937, were used to detemine containment pressure, are any pressure readings greater than the maximum allowable pressure without PR-932 operable (item 3.a.2):
YES O no O
- 5. If item 3.a OR 3.b is YES, consider the accident as a General Emergency.
BY TIME
I OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 . E IS N 6 DATE 07/05/S3 PAGE 43 OF 49 'k TITLE: LOSS OF COOLANT ACCIDENT
~
WORK 5A~EET 3, APPENDIX H 4 WORKSHEET FOR VERIFICATION OF CONTAINMENT RADIATION LEVELS .
=?
DATE TIME PERFORMED SY
- 1. BASIC ACCIDENT INFORMATION UNIT DESCRIPTION DATE/ TIME OF OCCURRENCE
/
- 2. Using the lowest reading on one of the following, RE-30, RE-31, (in the Control Room), the Victoreen Rad Gun (between the equipment hatch steel door and movable concrete shield), or a HPI-1010 (at the containment concrete wall), detemine the radiation 7evel following an accident approximately every 15 minutes for 2 hours.
TIME : DOSE RATE (R/HR) BY __ INSTRUMENT ID O l O f _
NUMBER EP OP-1 DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 DATE 07/05/83 PAGE 44 OF 49 TITLE: LOSS OF COOLANT ACCIDENT WORKSHEET 3 APPENDIX H , Determination of Expected Radiation Level j
- 3. _
- a. ident fevels Using Figure 1, (page 44) the time after the acfation nd ecual to readings from RE-30 and RE-31 (item 2), are rad or higher than expectsd for 100% gap release.
N/A YES NO Using Figure 2, (page 45) the time after the accident and i b. readings from the Victoreen Rad Gun (item 2), are radiation levels equal to or higher than expected for 100% gap release. YES N0 O N/A
- c. the time after the accident and Using Figure readings 3, (page from the 46)0 (item 2), are radiation levels equal to HPI-101 or higher than expected for 100% gap release.
N/A O YES O NO
- 4. If item 3.a., 3.b., OR 3.c. is YES, consider the accident as a General Emergency.
BY TIME l i e,
ll NUMBER P OP-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 , REVIS:ON - DATE 07/05/83 PAGE 45 CF 49 m
] TITLE: LOSS OF COOLANT ACCIDENT WORKSHEET 3, APPENDIX H e
,3 i 1
*!; .;. i;*
. .-m h
I'- : if, ' I!'l if '$f 10CX - - -- g -- g - - , ;,
--l -t--E j i ,, .. ,:
.ig.i.
1lIi ' ;
. % johtd. MELT
- i. st.:
%': q i
;9i. ;; Ie i:,
li .i s.: lil! i 1 '*l 10K , ,
~
if- ., l
,,., . .- f .i.
IiI: i'! iib */gNj.L"f F 4 llll .[l! llllI
!!!* !!ll II!! llI _ _ - _
ix I 1
.(, i .
i ., .#. .4
' Tit > : i , ,. GENERAL EMERGENCY w ,
! l-
+- ABOVE THIS LINE E l [,[ ~. a.l li .l m - [a.z, : ! ; i ; - ; l : ; .-
- l. j l. j l i - , ..
100 -_ - - . g I t
~
e l e je e a 10 . i etIi i u- 't! ; *: I ll [ii I' 3 i !i : j ' I; f it! Ic - - _ _ _ _ - .
. l 1 I l
!!!' - StAng,A7tyjyy
*i'-l '
fl!!'ll l : li ,g 1 ammesse -
. 46 e i t t
- lt*a l-i^,.-
*j* !
.e.. 4 g_3 !g.,
1 2 3 4 5 6 7 8 0 1 TIME AFTER AC:lDDiT (HO:JR$) FIGURE 1 nmr paTr **e'ar M** f +asere ene t pgg g gg l G ll l l l
NUMBER EP OP-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2
- REVISION g AGE 46 F TITLE. LOSS OF COOLANT ACCIDENT WORKSHEET 3, APPENDIX H ..
1 s, .l lT~ .
- ( *l.- .
.I ,
l i!?li;s! .
,;,lllln ' '
,' .tl.! , ,
ene t p g w tT I'i - 1CK , , _
, ,y -m
. . - - E- _->_ .._
- e. j- i . _e .
;!. tsig e,s ...
i 'a
'a
- i'l 2
!' 'l l =,l i8 ll; 6 ,., m::' g' 4.,c ,
1K _ m __ _ _ . _ _ i i
.;e eei ... ..). . ..: a6 .'
s'f ll}l l.l i . . *** llil .:a. :i
% :l lI.l i i !.lli. -l .
!! i.I i l l j i. ll 'i j i l 100 .-
n i . c ; GENERAL EMEP.GENCY 2
! __ L __t L .
& .ABOVE THIS LINE ii.
.< _10074P1Et'mL.
M I,l i j_.I!.l ,t - .. 't i i: 5 ti:l 1 ei
,,.:.l: fir! ii. j:lI i.i w I!: "- .l :i s!l:3 l. !' . ' .' l .
y 10 . I i
.. . 1 .i., ..
i;.i li;i i
..l .i .. lits. e. . ;i.t fl!
I
! ! f ! *:
f t
- s. ! e s ;.-
;: 'l .i :1. .. :lt* - i
(
s,l. .
3 l :f ! 11l il ii !.: l!;! - 0.1 . t-7 ,' 5 i - r.
+
1
' #C:DG.dA.C7t'JGY?
i t
.. .l- . ,
..l .i ;!!: ,,
l 0.01 i i I t!l ::. '!i ! ! 4
.3
. i.
llll 6
',: !! i 8
0 1 2 3 5 7 i TIME AFTER ACCIDE?!T (HCURS) l FIGURE 2 ) Dmr en r mm'5r '00!'"'" wMEu e tien en,' a'Atut: 'ecA
NUMBER EP OP-1 DIABLO CANYON POWER PL. ANT UNIT NO(S) 1 AND . 2 REVISION 6 OATE 07/05/83 PAGE 47 OF 49 TITLE: LOSS OF COOLANT ACCIDENT s
?
WORKSHEET 3, APPENDIX H J.}
.?
r --- -- 10K : _..;._ _ .._ .-.. - _ _
.p-
\* I y
1K - - -
- d._ICO *4.EUL
,.!Il --
l - 14EL['C:.s
. i'
' 8I:
i l M
,.... , . .:1
.i. ti i: QI - ; 1. fCf. p r:f wet _T 3 Di: illfl W i I f ! illi lii:
i
~
t....
' l i y 'i. I *I- I ?. DEL 6 21
1' l1lli 6 li i IIl ' 6
!' '! 6 /
h'i!!j
*i i
I 10 __ . _ m ,
^% '
W ..i .4 . i. . E 1: 'l;. ' * !! ;; l's . i't? 1
!!i!llll!!! _
I! !!' !!! !!A 'll! - i 4 ) 6 t i . . . .... N. ... . a y g e en g d a'.' it' 0l
!!:' I!!! l'I [ !! 3 I'-~_.,..- GENERAL EMERGENCY
~~~
e ABOVE THIS LINE
? l? I- 3
'
- t e!l! l
. , i sii! l. . 't
~*
i.' I ' il
.i f;
'). 01 '- ' I O 1 2 3 4 5 6 7 a TL'tE AFTER A0010['.T (HOUP.5)
FI7J7.E 3 OCSE RA*E OL*TSIDE OF Wi Alt."E!!T SHIELD WALL FOLLOWI?!G LOCA Ov . l
NUMBER EP OP-1 1 AND 2 REVISION o tABLO CANYON POWER Pt ANT UNIT NO(S) . DATE /05/83
. PAGE 48 OF 49 TiTut t.0SS OF COOLANT ACCIDENT
~
'- .'. '.:=-=:] : jpit E:gEi _M ;-Z_
i- =-- .
. - - - :' F . Y.!;=. ; -N -
= :.yg2 gi., :, z . [_ ,. . . . . _ - . _ . .
- L . ; '= -, ;- . . . = = --
3 _nc - = .i ==: == : *
-_ 2 W -,= _:.#C=~--==- .
2300 . "'.'M.1aturattsir
- : ..:- 105. t. r._um..eff.- er..ror. curve-with._ $ ._. .
i
.f:.._
.u
._=_-: c . =._
1
..__..r-
. rt-f.. ,- ,..
3 .. . . . . _ .
.,-._.:__..._n_..=.
i _... . -. _=_ : L=_.-- .: - -- - =c
.__ _ i. ._=. . == , n :.= ...- ._.
*2200 . . .=_ m _n.... : ~_
i~ d 9 b ' U E N -- ~[l 7 .#'l 2:5~~r~ii ~_.7 _2 5 1 .-I~i$id Urit.-[0 d di"Vd'-Oi dF _ - :- . i -- i : i-;.: - _ 5.j'-ST==;=g s p =Pr-2= ;
"; , ; W ps y m ercors.and_rr ._e. : :- c :2 _J,. _ - - T a n __._ __.=
. - - - - - 1 2: .
2100 : .. w;=.succmal lag: scoec. a.-=,.=.==.=:-.i=.=.- __---
.. r
. :: .= . 2: . == : ==.:-=.. = . .: . - r.. . -
p...,.=.____..___...__m._..........
. ...__;.--.;___.___.. , ;. =. _
..;._f_=__.g_-....- -- .
i _. i ... .. v .:. . t: u - : .: ==:=_= - = _;.::== =.. : . =_ =.r = =
=: _ W 2000
- =_..t.... . _ . -
. -=.:. : :=:=2_= :.::_ : tu: _:t - . r.. . . .__'- g -- :..__=.._g'.-~~..=.
-- _: . -- ... =:.=.=::_.._ e:= =2-u_. . -_ .-. - ..
-t _c -._
; '== -= "=-
- ' W:'eG i - *Te +'-
- =t
" 3 _' =_-E = '
N iM H-^b-5=~-bli'iN5:$:5 1900 - . AU NT!:E!!':= -iE - J.E . ~ 7 . . "I- '-.u.E'; ":.~ . n_. - _:t.2 (_.__ + -t_.-
^
= =. . ,_=.._=___:. . _ = , = - _._
...a...=:.......t....__.=,__.:-.--....__.....i.... _ .; ; . ; _._.. . __
1800 E
.. . .. ic . .- - _g. .. . . . -- =.:. . _.___ r ._=4 :- -- .,.;.=g.p.....=._.:=,=_.__-
4 n._;==__.,._...-=-:=
=._r=... . = _ = = . . . . . = _ .
u,
==. ._ '.. . ... .. - 1. -- . E. =__a .. .. .=.1. . :. m . . ==_.r nz .
1700 -
-27'"- :=.-..L._. .
= + : - --:; = .- --. .: . .
.:_ .- == : _==- - 2 : ==
I
. ~ ..
.== .e _ . = 2_. . == : =_. .;_.--- : p r _1_===s =:== --x .:. l ._ a . _a
. . . :: = , = u = > =- . g: :-= ~.= - . - -
1600 E .- . . ;._:-f_ .. _-$. f_3i=L..-3. 3= . p. h :j _;;_.:9. t. . = - l ' .:~ f:: Q- e -9.=:2_= ._~.
. -- r : .
- - -1 r , = - =a .
=n -
- - .._ .._ =..;. . =: _ --
-t.:-i. .- E_. Ei '. *-
r_ = . . .v . - c. : . , _
- c. r _-
. . - : . c
- . . - - - -=-: = r_ = 2 + =-- +-. . . ._ . . - . .
'-~ . ' . - g' _ , _^-!=_~~.~.~.=H..=.2_'=.'"_"._-
_ -_+4 =.D. . . . _^ .;=.G_ .... u _ .. '. C_. i-
= - - - ,-x==
1500 ~ ~.-~ a. _ .a .
- . -L..
. . _ :.---L=-=......_=..-.=.=...v--
. = _=_:-- = = t=:_=_- .. _ . . .a = _ : . .==- :r = .. . f _.
= -rT_ E:Ed ==.__ .=.__-a =._ :-=== =. =..=
~
._ .r= .. . ._=;b= =_in ; = 1=::=E::
=" - .
!= - P .
.*~ . :_ ,w,,,,4., . =.= = =.z=_.-
1400 .- r:_ . . = - . -
. i ..-
- .- : =. e _ --
- w__-
- _. . .=. .w.=: =.==v : =_: = ==. . . --- - : = 4 : :=:- :
t==_. i _ ._..u L r*=" _. : --:= . , : .. : . r
.c.- .-_z..-=_.
=.... . . . = . . . = . _ ._ .. .. ..
m m 1300
.c.
._.-r_._.'=.=_m._-=
=_.=
t _-- : -:= =-- -- : :
>==..-=-=:...
=:; . == = . . =: . ,. ==_: . &. =- _. . .=. .=- -
-~,=,._:_._=.--_=.=_=...._
I- -
.-__=-..__..-==-
= u. . . = -= r_-:.==
..=l-*==1'.'.-=_a=-_:.'.=.=--.==- ----e --
; _ . . _ := r : =. == . - e . _.= :. : :. == _=.= : . . - -
=--:-=,-=_=_t-=t=_=_==_:..=.__=.=t::.-.t-BE'1200 . , . .
= .j. < a._=_-___.._...==_=..=__--
-a=_=.,..._.=...=.._--.-_-._=...=.
- ......_._u_.._.. : r. . .
x .._. - o ~ 1' % d .=..__._,.,k..._ li54Gli M.5 =. _- -..:
$1100 5=Mrt _==t
, . . . . . . _ _g -'.. REPTAKE-dikN. . . .y- - a. .s. ___:= . =. . . . - s
.. 5 I-k .
; -{._ .
_ ___:= .._ u._ = = :. : . _ _.- .1
...p====.==_=-_:.=:_ =.a -l w
x . . =.:=,a.==_._ _.. . .. ._. -- .m,%g. _& ny hx.5W_--= _ = .i -: -== = . .-w. - --=. _ . 7- = = - e.; x 1000 =-=_=:-
.=:=:.__=:,=;c=-=A.._.__-.___.-==_..._==._.
=
~
- z . = = = == ~c . [= =_- ;. =: . == .
==__: =- =_
. _ =_ . :=_=
- _n _; _ . _ = _ = _ = _ = _ = _ _ _ _ = . ,
_ _ _ -__ ..: _= __ : _=.
...===.._==
.__._=.___=.E.=___=__.__._.._:c:__=._=r=._--=__i_=.=.r=_==,1..._....,..__
=s===-==.
900 m=_ _ =;._ - _ _ r _: _.- - . =
= = :p. m =- =- ==-= == p .2.- _ -===w== = . : - / -- - m-r . _.=_.. _=- ==.==
_ . . -. ..= -- - ru_
.-2 =. -=_; * :
;- - = .- cr- . _ . .
==_=.r. ===:=- :..~_t
~--_=~: f - = = _ - .- _ :.- .. . __.-:-----
_ . . . : _- : = = _ z-
- = : =.- -- t=- ,-:_=_= =. q _== : . - - _ . :-
,. . . . . .- . ---=_.=--:.e 800 ^ - - - .
-.=-=1==:-=== =
- ,;95. =. = _:= . : - ---= 7. ==- _ . :1 . =.=:.=~=. ,l= . _ . :_. . == . = = . a_.=
_=. = = -=-.=:=. : __. - .-: . .-.
.. ~
' : P ~'_~1 = =- ". .=T =- _ =- ==-=_ ==: . _==. =-
- h==:= = .==. =!.===.-=" :- .
- ' " . . - I, ==..=, - . _
700 -
-r===_-=Ljg:.F._;=:
- 2 =.E ;. s:Ey:-t:=f;-si+i :_t1_:-- p-Ugr_ : _-..: u./ . r== . = -= - =: c,= ..:.=.==.:=.===- -- ==~--=-s
=1 r_. a . =_= = :==-- .= == x= v. . . --
e
. : . : t == =-..-r ,._; == .:- ..=====a
~-
g=-g.c jr.:g=_E_E_EE$es:1.;;g=y 600 jeg--t=g=;;=;;r.- - ; _3. _f. .ci;. -.W. :-=._.y-
'." . . t.
e:Ees_--RCs=5ATUPMWE=EE..__i
- m et:=m= M_-: =i ! . __:- ::5=., =>-V.-
500
^
~R i- :
-?=--=+. =.#1- ==.1_*WEw
= G f E ?? ?_' 6 =i:5 t == ? M
-~ -
400 -
. , . = _ , ~_ . - . .
....+....,t_..=_-1_-&....--.=.,,_ =n . = n 5---- _4.=_- ?
- 3. ~ _ .vy
.-E5:== _ _ . . Lg. .z-a=.u: -+. h= +=
. . .. .._:_. ..... .. ,. ... .v.-. ._. . _ . . _ = w .m c.-_:. Aa
- ._...4__
- v. - e. . _ , . _ . = . .
o
- .....-=.,_=.-.- .
-- - _-. . =_. __ ...._....,.._._.t._-*""c..rn.=..._.......n Q ^ ......;_ .-: a .
- : b
-:-. . ---_.:::--._--_:_=-.=--=.- . -'
S^V :.cr,; w -- _ y .,_:2.-.=.___:-_- JU .. i _.=.:...=..-_p._. . _- s. _.r:--- ._ _
. =.: . _. a.c:_._ ;- .
- -,-- =_ ..y . ... __.. r_ _ .. _= _ ..
p.:...r...:=:.: 5.c*J... i- _ - m._: 2. =_; r=.L.-_ :.._.= Ann 7 200 ,. 400 500 RCSTemperature(qh) 100 200 300 0 l l I l
NUMBER EP OP-1 CIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 , DATE 07/05/83 TITLE: LOSS OF COOLANT ACCIDENT f
-4 APPENDIX Z 2 EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
'1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Designate this event a Site Area Emercency. Notify plant staff and organi:ations required for tnis class 1fication by Emergency Procedures G-2 " Establishment of the On-Site Emergency Organi:ation" and G-3 " Notification of Off-Site Organi:ation" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation."
- b. In the event inadequate core cooling is verified per Appendix F or the verification of ESF Functioning and Effectiveness during LOCA, Acpendix H, indicates ESF failure, reclassify this event as a _ General Emercency. Notify plant staff and response organi:a-tions in accorcance with EP G-2 and EP G-3 and implement the instructions in EP G-1 regarding on and off-site protective actions.
O
PGwE D(ATLO CANY3N POWER PLANT
- PROCEDURE ON-THE-SPOT CHANGE M i4 i2")"* /
,,oce. ,e .. EF OF-48 .
o .
= =. 2 0 20 ,a as -
4 rm LOSS OF ALL AC P6WER-
- k. .re. o, en.no.- @ esauseur (, a> 0 reuaoa^av(v ao >: E,.ir.e4on o.ce n.oo.si.no Dec nm.n, OPERATION 9 ono,n , N .LlGw/
~
Tia - ~f Chang. (Does this aner the intent of ongrW procedure? Yes k W )
. (Does it constitute an unreviewed safety / environmental question? O YES , %NO)
) de\ete shp 12. 6 , (2, c- M it d %
IO of le,1. page. E 1 O Reason for Chang. C, WC $ g Q,yg yC A(,C b i N *b y k1' b (2*h en k a D9u d y ccm.sel by w.4 yo c cs.s 3 e re-u,_,,_ U (Ptart warw c; Stan) lb/
'(Plant kanagem ra staff w/SRo Ucense)
M W83
/ / Dere*
C 710 Initial op stribution By:
!aunediate distribution to ine Control Room and affsted wort areas required? % YES Af_ . Q, Q@
Distributed To: $ Control Room Q Others jf o.te Receiveo by oocument Controi
= == w 14 a.v.
s! esac no .no = uan#s oa no r n s ir mac - ==0wO= _,. w 0 =^ gg j g u.aas wwOO-000
% ra n ct.o on-m s,. ch.ng.O maoan wor ===a O 4
E Action TakerVRomarks d 6. I$ h see acetions sneets[ DISTRIBUDON: @ sane C Omers x l
i i NUMBER EP OP-6 TC7F43 Pacific Gas and Electric Company REV,tSION 6 DATE 7/5/83 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE I OF 5 EMERGENCY OPERATING PROCEDURE i TITLE: EMERGENCY B0 RATION huid g ' APPROVED: Y b PLANT MANAGER 6 DATE SCOPE This procedure covers the situations which require emergency boration and the methods for accomplishing this operation. Three methods of emergency boration are discussed in this procedure. The preferred method is borating at 10g;m using the VCT make-up system. The next method is borating through the emergency boration valve (CVCS-8104). The next alternate method is boration using the RWST. SYMPTOMS Any one of the following conditions requires emergency boration.
- 1. Control rods inserted below the low-low insertion limit. (alare PK03-14)
- 2. Failure of any control rod to fully insert following a reactor trip as
( indicated by rod position indication and rod bottom lights.
- 3. Uncontrolled reactor coolant system cooldown following a reactor trip with no ESF action as indicated by:
- a. Lo-Lo T avg alarm (window PK02-04).
- b. Continuous or unexpected decrease of T,yg below no load value (547'F).
- c. Abnormal decreasing pressurizer level and/or pressure.
- 4. Uncontrolled or unexplained reactivity increase as indicated by:
- a. Unexplained control rod insertion.
- b. Increasing T gyg or nuclear power with no increased load demand.
- c. Unexpected increasing count rate when shutdown.
- 5. When boration is required and normal boration through the VCT make-up system is not possible.
- 6. Shutdown margin less than acceptable minimum limits as per Technical Specification 3.1.1.1, 3.1.1.2 and 3. 9. l .
AUTOMATIC ACTIONS
- 1. None l
l 1 1
- j
NUMBER EP OP-6 l REvlslON 6
-OlABLO CANYON POWER PLANT UNIT NO(S) 1 AND 72 ATE 7/5/83 N ORAT M --
PAGE 2 or 5 TITLE-O IMMEDI ATE OPERATOR ACTIONS _ COMMENTS ACTIONS
- i 1. If the VCT makeup system is operable, borate at 10gpm 8
? by using the BORATE or MANUAL \
MODE.
- 2. If the VCT makeup system is inoperable or is not sufficient, use the emergency boration valve l
as follows: i
- a. Verify boric acid pump in low speed or transfer the running ,
boric acid pump to low speed
- b. Open the emergency boration motor operated valve (CVCS-8104).
- c. Monitor pZR level and open
- c. Increase charging flow: additional letdown orifice valve if necessary. If PZR
- 1) If the PD pump is inservice, is solid, verify PCV-135 is go to manual and increase functioning properly.
charging flow to maximum. I I
- 2) CAUTION: Re-open the recirc
- 2) If a centrifugal pump is in valve if an 51 occurs or if service, go to manual and the pump is in danger of increase charging flow to dead-heading.
maximum. If necessary, close one recirc. valve (8105 or 8106).
- d. High VCT pressure will inhi-
- d. Verify sufficient charging and emer- bit boric acid flow. It may gency borate flows into RCS. be necessary to vent VCT.
The minimum BORIC ACID flow SUBSEQUENT OPERATOR ACTION (12*.) is 10gpm.
- 1. If the above methods did not function:
- a. Swap charging pump suction from the VCT to the RWST.
Shift to centrifugal pump operations, b. This will insure that suf-
- b. ficient baron is injected if not already in use. Insure charging to satisfy Tech. Specs.
flow is >100 gam. 3.1.1.1, 3.1.1.2 and 3.9.1. l
NUMBER EP OP-6 i OlABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVislON 6 M MERGENCY B0 RATION DATE 7/5/83 TITLE - PAGE 3 OF 5 SUBSEQUENT OPERATOR ACTIONS (Continued) ACTIONS COMMENTS
- 2. Borate as needed to place the -
.i reactor in a safe condition
- a. If boration was required due to a. 300 gallons of a stuck rod borate 100 ppm for 12%B.A.=100 ppm each stuck rod.
- b. If the boration was required due b. If rods are in to violation of Rod Insertion Limits manual, pull rods (RIL), borate until rods are above to match TAV'i witr RIL. TREF as boration occurs.
- c. If criticality was reached inad-vertently below the RIL, borate, 100 ppm.
- d. If the boration was due to Tech.
Specs. 3.1.1.1, 3.1.1.2 or 3.9.1, borate until within limits.
- e. If boration was due to an uncontrolled or unexplained reactivity increase or uncontrolled cooldown following a reactor trip, borate as necessary to regain control
- 3. When sufficient boron has been added proceed as follows:
- a. If the VCT makeuo system method was used for this orocedure
- 1) Stoo the boration
- 2) Set up the VCT makeup system for 2) Use the boron AUTOMATIC makeup. meter to determine the necessary blend.
- b. If the emergency boration valve (CVCS-8104) method was used:
- 1) Close the emergency boration valve (CVCS-8104).
- 2) Return the boric acid pump to auto.
NUMBER EP OP-6 DI ABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Revision 6
- DATE 7/5/83 EMERGENCY BORATION PAGE 4 OF 5 a lTLE -
0
- 3) Return the charging control to automatic and open recirc. valves if closed.
.4) Close the additional letdown orifice i 4 stop valve if it was opened.
- 5) Use the boron meter and adjust the automatic makeuo system to the new concentration.
- c. Have the Rad and Chem department take a boron sample.
- 1) Take sample fron:
- a. Hot legs of reactor coolant loops.
- b. Pressurizer liquid volume.
- 2) Adjust VCT makeup blend as needed.
- 3) Use pressurizer sprays to equalize boron concentrations if necessary.
- a. Monitor the level in the boric acid tank (s) to detemine if replenishment of the tank (s) is necessary to meet plant Technical Specification limiting conditions for operation.
l
- NUMBER EP OP-6 REVislON 6 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 7/5/83 EMERGENCY B0 RATION pace 5oF 5 TITLE _
O APPENDIX Z i EMERGENCY DROCEDURE NOTIFICAT:0N INSTRUCTIONS i
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows.
J
- a. Notify the Plant Superintendent, Suoervisor of Operations and Plant Manager or their designated alternates.
- b. If the emergency boration resulted from the plant not being' in a controlled or expected condition while operating or shutdcwn (sucn as symptoms 1, 2, 3, 4 or 6), designate this event as a Sienificant Event. Notify the NRC Bethesda Operations Center within one nour as cescribed in Operating Procecure 0-4 " Operating Orcer (One Hour Reporting Recuirements to NRC)."
- 2. If, in the coinion of the Shift Foreman, the plant condition recuiring energency boration warrants increased awareness on the part of the plant emergency organi:ation or state anc county response organizations, designate tnis event a Notification of Unusual Event anc notify plant staff and response organ 1:ations recu1 rec cy Emergency Procedure G-2
" Establishment of the On-Site Emergency Organization" and G-3 "Notifi-cation of Off-Site Organizations" in accordance with Emergency Proce-O dure G-1 " Accident Classification and Emergency Plan Activation."
1 [ l /"'N 5
m ueER EP Ob 8 7GF43 Pacific Gas and Electric Company REVISION 6 DATE 7/5/83 l DFPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 OF 23 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2
, ! EMERGENCY OPERATING PROCEDURE l l TITLE: CONTROL ROOM INACCESSIBILITY APPROVED: Yb PLANT MANAGEp g,/ DATE SCOPE These instructions are provided to cover those conditions prevailing wher.
Operation from the main Control Room is no longer possible due to fire, smoke, heat, chlorine, high radioactivity or otner occurrences which make the Control Room uninhabitable. SYMPTOMS The following alarms may come in:
- 1. Control Room Ventilation alarm (PK5-06) due to hi radiation or hi chlorine.
A 2. Fire / Smoke detector alarm (PK 10-10). V 3. High radiation alarms. OBJECTIVES
- 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 tne Control Room if conditions require this.
AUTOMATIC ACTIONS
- 1. Possible transfer to Control Room ventilation to Mode 3 (high Chlorine) or Mode 4 (Pressurization).
- 2. Possible start of the diesel generators (if offsite power is lost).
IMMEDIATE OPERATOR ACTIONS
- 1. Trip the reactor and main unit turbine.
- 2. Verify reactor tripped (all rods on bottom DRPI - reactor power decreasing, Nuclear Instruments).
- 3. Verify turbine tripped (all four SV closed on EH panel).
'O v 4. Proceed to the hot shutdown panel.
l OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 E S ON 6 OATE 7/5/83 TITLE. CONTROL ROOM INACCESSI5!LITY
~
SUBSEQUENT OPERATOR ACTIONS
'. ACTIONS COMMENTS Transfer of equipment to local The below listed equipment should have control may remove it from its control swit:h placed in the follow- various auto control schemes ing position prior to transferring to (i.e., press., level,etc.)
local control to insure a bumpless Auto starts due to bus transfer , transfer. or SI will still occur. Trans-ferring BA pps & Pzr groues to
- a. PZR HTR GRPS 12 and 14 to local control removes them frcm the neutral position.
their auto control schemes. The appropriate orifice (It may be advisable to leave
- b. them in REMOTE at this time).
isolation valve (8149 A, B,C) to the open position, and orifices not in service in the closed position.
- c. BA XFR PPS 11 and 12 to low speed.
- 1. TO MAINTAIN THE PLANT IN HOT STANCSY A. With off-site power available
- 1. The following equioment can be transferred to local control irrediately:
*a. BA XFER pump 11
*b. Containment fan coolers It is advisable to leave the 11, 13 and 14. following equipment in AUTO (Remote) if they are controlling 2149A&C (letdown orifice properly in the AUTO position,
*c. unless manucl control is valves).
desired. HCV 142 FCV 128 PCV 19,20,21 and 22 (10'; steam dumps) LCV 110,111,115 and 113 ( AFW level control valves)
"These items must have their control transfer relays hand reset when transferring control back to Control Rocm (in addition to being in remote position on transfer switch).
* \
\
DIAB _LO CANYON POWER PLANT UNIT NO(S) 1 i.ND 2 "f')lS R ON
. DATE 7/5/83 PAGE 3 OF 23 TITLE: CONTROL ROOM INACCESSIBILITY ACTIOMf COMMENTS 1
d '. HCV 142 - i e. FCV 128
- f. 10". steam duma valves 9 LCV 110,111,115 and 113
- h. CCW pump 11 and 13
- 1. ASW pump 11
- j. Cent. Chg. pumo 11
*k. P:r. 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:
*l. Containment fan cooler 12
*2. 8149B (letdown orifice valve)
- b. Located inside the 480V Bus G AUX relay panel:
*l. FCV 95 ( AFW pump 11)
*2. MCV 8104 (Emerg. Borate Valve)
*3. LCV 106
*4 LCV 107
*5. BA XFER pump 12
*6. CONTAINMENT fan cooler 15
'Inese items must have their control transfer relays hand reset when transferring control back to Control Room (in addition to being in remete
- posi_ tion on transfer switch).
A b
NUMBER EP OP-8 O!ABLO CANYON PCWER PLANT UNIT NO(S) 1 AND 2 DATE 7/5/83 PAGE 4 vs 23 TITLE. CONTROL ROOM INACCESSIBILITY ACTIONS COMMENTS .j
', c. Located at 4 KV Bus G
- 1. CCW pump 12
- 2. ASW pump 12
- 3. Cent. Chg. pump 12
- d. Located at 4 KV Bus H AFW pump 12
- e. LOCATED INSIDE 480V Sus 130 cutout switch panel
*PZR heater group 12'
- 3. Trip the main feedwater pumo turbines and ensure that they go on turning gear once zero speed is reached.
- 4. Ensure that the beartng oil pumo, HP seal oil backuo pump and the bearing lift oil pumps are running; and that the main unit turbine goes on turning gear once zero speed is reached.
- 5. Maintain the reactor at hot standby condition by:
- a. Controlling steam generators a. See attached graoh for deter-at 33% with the auxiliary mining actual VS. indic.
feedwater controls. level (acorox. 63% indic. on wide range equals 33% ( actual on nareow range at l 1005#). l 1
*These items must nave their control transfer relays hand reset when I transferring control back to Centrol Doom (in addition to being in remote position on transfer switch).
NUMBER EP OP-8 REVISION 6 DIABLO CANYON POWER Ft. ANT UNIT NO(S) 1 Af!D 2 , 7/5/83 DATE' PAGE 5 OF 23 TITLE. CONTROL ROOM INACCESSIBILITY COMMENTS ACTIONS
- b. Controlling pressuri:er level at 22*. by use of the charging pumps and letdown valves. Do not allow level to go below 20" to ensure against letdown isolation.
If letcown isolation does occur, restore letdown per Appendix A.
- c. Control pressuri:er cressure at 2235 osi by use of the backup heaters as needed.
- d. Verify steam generator pressure is being main-tained at approximately 1005 psi by use of the concenser steam dump.
O V This will be an auto-matic function unless vacuum is lost on the condenser. Manual oper-ation of the 10* steam cumps will then be required.
- e. Calculate the SCM for hot Xe free conditions.
This may require local
- f. Stoo any dilution in pro- f.
valve manipulations. gress.
- 6. Establish as personnel
- 6. Establish or verify communi- availability allows.
cations between the hot shut-down panel and:
- a. Outside telephone exchange '
(send an operator to the plant office).
- b. Dedicated shutdown panel
- c. 480V vital switchgear area
- d. 4 KV vital switchgear area
(
,O l
ua DIABLO CANYON POWER PLANT UNIT NO ) 1 AND 2 6 DATE 7/5/83 PAGE 6 OF 23 I h TITLE. CONTROL ROOM INACCESSIBILITY COMMENTS ACTIONS
- 7. Maintain shutdown margin using method a. or b. below,
- a. By opening the emergency a. Observe boric acid flow on FI at hot shutdown panel, borate valve 8104 fecm ;
the hot shutdown panel. I
- b. Boration may be accomplished b. Indication of boric acid ficw l by opening manual valve 8471 using this method will be at so that boric acid flows local FI (PM 96 on 100' El.
through normally open Aux. B1dg.) FCV-110A, but bypasses the blender, and running the boric acid pump in fast speed.
- 8. Place diesel generator control 8. Done locally in each C.G.
room, selector switch on excitation cubicle to LOCAL position. Verify the AUT0/ TEST selector switch on local panel in the AUTC position. ( )
- 9. Place SU FCR breaker transfer switches to LOCAL position on cubicles.
B. With loss of off-site power:
- 1. The same as A. above except that diesels start automati-cally and assume the vital bus loads.
- a. Verify that the diesels a. Shutdown unnecessary equip.
have started and have not needed for current olant assumed their normal status. loads. Verify 4 KV Bus F, G and H volts at the hot shutdown panel.
- b. Verify that equipment with controls located at hot shutdown panel have re-l started after transfer of I power to diesels. Restart locally if necessary.
l l I
NUMBER EP OP-8 1 AND 2 REVISION 6 DI ABLO CANYON POWER PLANT UNIT NO(S) , OATE 7/5/83 PAGE 7 OF 23 TITLE. CONTROL ROOM INACCESSIBILITY
~,
COMMENTS 3 ACTIONS
.; Htr Grps 12&l3 on back-uo Transfer PZR heater groups c.
- c. supply can ONLY_ be controlled 12 & 13 to emergency supply.
480V vital power breakers 52-1G- (from outside the control room) by locally closing or 72, 52-lH-74 opening their breakers for pressure control. C. If Control Room access is not C. Maintain hot standby until Control restored rapidly, a decision Room access is restored and control must be reached on how long has been returned to the Control to remain in hot standby Room. and when to start cooling The down to cold shutdown. basis for this decision is the amount of water inven-tory in the condensa:e storage tank. Refer to cor.- densate curves in this pec-cedure for guidance in making O U this decision. D. Notify plant manage'.ent. E. Declare this event an alert. Carry out the instructions given in General Appendix 2 to the Emergency Procedures (Notification of Offsite Agencies in the Event of an Emergency). TO TAKE THE PLANT FROM HOT STANDBY TO COLD SH CONTROL ROOM COMMENTS ACTIONS
- 1. Containment entry will be
- 1. Calculate the SOM for cold Xe required to accorolish various free conditions and borate as evolutions in this procecure, necessary. Energize pressurizer therefore, preparations heaters during boration to equalize should be made as soon as the boron concentrations in the PZR practicable to allow for with the RCS, Alternatively, see this. Also, I&C Deot.
Appendix B for spray actuation. personnel assistance will be required to execute certain steos.
" P-8 1 Ai4D 2 E 3 ON DIABLO CANYON POWER PLANT UNIT NOTS) 7/5/83
- DATE
~
PAGE 8 OF 23 TITLE. CONTROL ROOM INACCESSIBILITY 4 COMMENTS ?* ACTIONS .
. 2. Sample the RCS and PZR to
~
ensure boron concentrations are equalized and adequate for cold shutdown.
- 3. Do not exceed 100 F/HR
- 3. Maintain RCS temperature and cooldown rate. A 50*F/HR press. within the operating band cooldown rate is rec 0rrended.
of the attached curves during Cooldown.
- 4. Remote readout of the boron
- 4. Maintain cold Xe free baron conc. analyzer is available at by closely monitoring RCS boron the secondary sample par.el conc. (85' El.).
- 5. If heater groues 12 and 13
- 5. De-energize all PZR heaters. are on backup sucaly, ocen Open and rack out breakers for their bkrs.
Prop. heaters (52-130-5) and group 13 heaters (52-13E-2). Place heater groups 12 and 14 in the OFF position.
- 6. As an alternate means of
- 6. Corcence RCS cooldewn using cooldown (if condenser 10* atmoseheric steam relief available) use handjack on valves and reducing pressure 40* steam dump valve.
using pressurizer spray per Aopendix B attached. (If it Ensure letdown remains in is desired to secure normal service while utilizing charging to RCS valve 8146, auxiliary spray (560 F ?. a pneumatic jumper will have T limit). to be installed around SV 200 in PM 90 in Containment.) NOTE: During cooldown, actual PZR level can be determinec by using the attached curve and indicated level at the dedicated shutdown panel (LI-406).
- 7. Automatic and manual SI is
' 7. When RCS temperature has been not available with these reduced below 543*F (as indi- breakers open. If plant cated at the dedicated shutdown conditions warrant initiation panel) open the following instru- of auto SI, close both instru-ment AC breakers to inhibit ment AC breakers.
HI steam line flow and Low Pzr pressure SI. lc b
. I l l
M8E P P-8 OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ,S O'N DATE 7/5/83 PAGE 9 OF 23 TITLE. CONTROL ROCM INACCESSIBILITY r COMMENTS , ACTIONS
- a. PY 1115 Train A Output Cab.
- b. PY 1418 Train B Output Cab.
- 8. Shutdown two RCP's to decrease the 8. Local indication of RCP heat input to the system. Leave vibration and RCP seal RCP d2 running, as it is connected injection flows should be to the PZR surge line. observed periodically during cooldown.
- 9. Do not allow the temperature diff-erence between loops to exceed 25 F. The temperature of RCS loop 1 is directly indicated at the dedicated shutdown panel. Temper-ature for loops 2, 3 and 4 can be determined as a function of steam gen. pressure using the saturatien curve on the attached graphs.
() fm I
- 10. When RCS pressure decreases below 1000 psig, close the accum-ulator outlet valves (one at
- 10. MOV 8808A 52-lF 46 MOV 8808B 52-1G-07 MOV 8808C 52-lH-10 a time) by performing the MOV 8808D 52-lG-05 following at each breaker:
- a. Lay down close contactor seal in wire on terminal 44 (inside bkr cubicle).
- b. Close breaker.
- c. Depress close contactor.
- d. When close contactor drops d. Closure of these valves out, immediately re-open can be verified locally, breaker. (If open contac-tor picks up before breaker is opened, close valve fully using local handwheel,
- e. Re-lift and tape seal in wire on terminal 74.
A A] l l
N EP OP-8 DIASLO CANYCN FOWER PLANT UNIT NO(S) 1 AND 2 E IS ON 6 DATE 7/5/83 PAGE 10 CF 23 TITLE. CONTROL ROCM INACCESSISILITY COMMENTS j ACTIONS
.; .11. When RCS pressure drops below 15C0d or RCP si seal leak-off flow decreases below 1 GPM (can be observed locally) ocen di seal bypass valve 8142 by placing pneumatic jumoer around SV 205 at PM 90.
(El. 91' East side of contain-ment.)
- 12. Open additional orifices
- 12. Continue to cool RCS until the as necessary to maintain temperature is less than 350*F and pressure is below 390s. normal letdown flow.
Maintain pressure by reducing spray flow and energizing PZR heater.
- 13. Place RHR system in service on 13. Cut in control transfer relays recirc. to collect a RHR system cutout switches on the RPR water samole for boron determination pumps prior to starting locally.
by manually closing MOV 8809A&B (RHR to C.L. 1,2,3 & 4) and starting RHR Observe pump amps locally. pumps from their switcngear cubicles. Observe that recirc. ficw has been Do not allow the RHR to ran longer than 30 min. on established (Observe FI's located recirc. locally outside the RHR pump rooms). 14 Collect RHR sample and analyze for boror conc. Ensure baron conc. equal to or greater than the RCS baron conc.
- 15. Shutdown both RHR pumps.
- 16. Close 8980 using handwheel. 16. RWST to RHR suction.
- 17. Close the breakers for 8701 17. RHR suction from RCS H.L.4 (52-lG-25) & 8702 (52-lH-19).
- 18. Observe local pump suction
- 18. Open 8702 and 8701 by momen-tarily pushing the open con- pressure indication (which tactor for the valve. The valve should increase to RCS should be full open in about 100 pressure).
l seconds. When the valve is full I I open as indicated by the open con-tactor dropping out OPEN the valve breaker to prevent the valve from reciosing automatically. O
1 l BE P P DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 g ON DATE 7/5/83 PAGE 11 OF 23 TITLE: CONTROL ROOM INACCESSIBILITY l i' '
- 19. Open the CCW outlet FCV 364 19. Observe CCW flow thru HX's .
f and FCV 365 (RHR HX's) by local FI's (100' El Aux. shutting off the air supoly Bldg.) to the valves. (Valves fail open on loss of air.)
- 20. Start el RHR pump on recirc. 20. Monitor recire. ficw locally.
- 21. Slowly open 8809A until an 21. Observe local temperature increase in flow is observed indicator on RCS outle:
This is to allcw the RHR of RHR HX. (locatedin system to heat up. RHR HX room)
- 22. Start d2 RHR pump as per steps 20 and 21 above. (except using 8809B in step 21).
- 23. Slowly ocen 8809A & S to commence further cooldown of RCS.
A b 24. Install signal simulator units to PM 135 and FM 133 24 This allows for coeration of HCV 133 and PCV 135. Contact (located in PM 87 on 85' I&C personnel for installaticr. el. of Aux. Bldg.)
- 25. Install pressure gauge upstream of PCV 135 to monitor letdown press.
- 26. Open RHR Hx crosstie valves 8734A & B and establish RHR to letdown by fully opening HCV 133.
- 27. Regulate letdown flew by con- 27. Letdown orifice valves trolling PCV 135, should remain open.
- 28. Wheh condenser vacuum can no 28. Condenser vacuum can be longer be maintained, proceed observed at the main unit as follows: turbine pedestal on PI 256, or on local indicator in PM 177 on 104' E1. (near PY 17).
l
- a. Terminate condenser steam l dumo (if in use).
pO. V
BER 1 AND 2 jPOP-8 DIABLO CANYON POWER PLANT UNIT NO(S) -
.
- DATE 7/5/83 PAGE 12 OF 23 TITLE. CONTROL ROOM INACCESSIBILITY COMMENTS ;
ACTIONS 4 b. Break ccndenser vacuum.
- c. Shutdown the air ejectors and secure shaft seal system on the main feed pumps and main unit turbina. {
- 29. Open & rack out SI pump breakers (52-HH-15 and 52-HF-15) and manually shut valve 8835. (SI to C.L. 1,2,3 and 4.)
- 30. Reduce letdown flow less than charging flow to begin increasing PZR level to approx. 90%.
- 31. When RCS temp. is reduced below 200 F, fill the steam generators all the way and place in wet layup.
- 32. Ensure shutdown margin remains greater than 1.0% t K/K.
- 33. Fill the P:R all the way. 33. While filling and cooling down the PZR with auxiliary spray, per Ap::endix B, ensure the PZR cooldown rate does not exceed 200 F/HR.
34 Shutdown remaining RCP's when the RCS temp. is below 160*F.
- 35. Continue to cooldown the PZR until the PZR temp.
is below 150'F.
- 36. Reduce the system pressure to approx. 50 psi by reduc- ,
l ing charging flow and increasing RHR letdown flow.
- 37. Shutdown the charging pumo.
NUMBER EP OP-8 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6 DATE 7/5/83 PAGE 13 CF 23 O TITLE: CONTROL ROOM INACCESSIBILITY
. 38. Stop any spray flow in progress and close the RHR letdown valve HCV 133,
- 39. Leave the RHR system in service recirculating from hot leg 4 to the cold legs.
- 40. After approximately 72 hours of cooling, one RHR train and related auxiliary systems may be shut down. The remaining RHR train must remain in service.
O o d
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 g
. . D ATE ~ 7/6/83 PAGE 14 OF 23 TITLE. CONTROL ROCM INACCESSIBILITY
~i APPENDIX A 4 LETDOWN ISOLATION Should letdown isolation occur due to low PZR level, proceed as follows:
- 1. Place control switch (s) for LTCN orifice valve (s) in CLOSED position.
I
- 2. Re-establish PZR level via charging flow control. .
I
- 3. At nuclear auxiliary relay rack "B", depress and hold in energized i position relays 33aoX / LCV 459 and 33aoX / LCV 460 for approx.
10 seconds. NOTE: Relays 33aoX / LCV 459 and 33acX / LCV 460 are located in the top right hand corner of RNARB (cable spreading rm.128' el.) ano are appropriately labeled.. 4 Open letdown orifice isolation valve (s) as required from the hot shutdown panel. Check letdown flow re-established. 5. O l 1 h 1 l l l
NUMBER EP OP-8 OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6
- DATE 7/5/S3 PAGE 15 OF 23 TITLE. CONTROL ROOM INACCESSIBILITY APPENDIX B
~
E PRESSURIZER SPRAY ACTUATION _ When pressurizer spray actuation is required in the performance of this procedure use method A or B below: A. With RCP 1-1 or 1-2 operating. This method uses a normal pressurizer spray valve and requires a l
- 1. 8 RCP associated with its respective spray valve to be in operation.
- a. To use PCV 455A (Loop 1):
(1) Contact the I&C Dept. and have them di' connect 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 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.
- 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 (Transmation model 1040 or ecuiv.) to the disconnected leads. This will allow for modulation of PCV 455 B. (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. Eh VI
l
" " EP OP-8 OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 E S 0N 6
. DATE 7/5/83 TITLE. CONTRCL PCCM INACCESSIBILITY b
l APPENDIX B CONT'D i B. With no RCP's in operation
- 1. This method requires access into containment on the 91 ft. elev.
Proceed as follows:
- a. Contact the I&C Dept. and have them install a pneumatic jumper arouno SV 66 in Mech panel 90 (located 91 ft. elev.
next to the aux. spray valve) for aux, spray valve 8115. (Valve is air to open, fail closed).
- b. Establish phone cartunications between Mech. panel 90 and the Hot Shutdown Panel,
- c. Cut in air to open valve 8145 and cut out air to close the valve as required.
- d. Observe valve locally to ensure valve is responding correctly.
O 6 l l l m.
NUMBER EP OP-8 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6 CATE 7/5/E3 _ PAGE 17 CF 23
/
,\
Q TITLE. CONTROL ROOM INACCESSIBILITY
- REQU: RED CONDENSATE STORAGE CAPACITY AS A FUNCTION OF STANDBY TIME AND C00LDOWN T.I..M..E..(R_A._T_E_D .Mw..t.=. 3_42. 3. .). _.
..__...I._- . . _ .._...._.:.__.
_1_ _ __ i __.___.__.__t_.___ ' 73 _ t.. --__..;__.___ .
.___ _._ r__...._ _ _ _
.- _ t.__ _ _ ,
7
. __t____. ...___.
. 2_
p__ t t r . _ _ :- -
.p .
L_ __ _ __ _ _ -j
. 7.__ __ i
~~
/ _ _ _ _. ._
/
p / , i e t-l. __ _ ..a _ c, __ c._. ; _ __ - - _ _ _ _ _ . _ _ . _ _ . . --
.,.r .
.~ s . . - - n _. __ _;
wr .... . . ; ._,_.____ ,
. m. _:.v.:.1.-
<. 1 _ _
.- A
- 3 ..+_ _ _ * . _ -___
u_ __ __ _7 , 7s c u
,._ _____,f .._-- ,
g 8',) - _.L__._ w g _ _ _._ __ g p___ _ _ . .._ g _1._ __r---------- _u _ . /
#g w l / / ',
r- - g , /
/
/ ,
a . ,
/ /
o . ! /
/
. . / . /
w n. ._~. / . e . / ' e .
/
y l /
/.
c < i
= u_ , f , i c . f .
/ .___ i V / I
/ i i / _
c i e + , w x
/ ,
, /
/ ,
= e c-w
, . , - .r =
f . 6 . m -
. i e .
. , / 1 . __
i / . , . I p ! F.- . _ _ _ _
.v- ' .-_.__l___.. , ;. ~3
_ _. _ }
- i _ . _ . . _ _ . _
. _L.__ __ _ . y .> .
L/ _-_ _ _L_ -
~
_ . _ . _ ,. p' _ , p__._._. g .. __ _ . .. . 30 5 2 3 4 C-( 0 1 TIME AT HOT STANDBY (HOURS) l
~~
NUMBER EP OP-8 1 AND 2 REVISION 6 OfABLO CANYON POWER TLANT UNIT NO(S) OATE 7/5/83 PAGE 18 OF 23 TITLE; CONTROL ROOM INACCESSIBILI~Y O REQUIRED CONDENSATE L55/EL TO MAINTAIN . A GIVEN HOT STANDBY - - - -~ TIME. ..(.R_ATEDMWt 7~_. upu .__ . _ 7 L. eg - ' -.+ , ......./ __. ....__ _- ._j. c CV- . _ . . _ . g p- , _ i- -, I- ,
.: , .-l l .
, .. / ;
l >
-' n -. .
}
l
' _1
*~/
l -
* / _l 6
/
u,_
- : /
70
- F i / .
' . . /
- _e l-
. ['- ,
3 I s s /. , < l
, y -
^
6 6 . ss . C i
. /
;d
< 60 _-
. i
/
- /! t l
t _ a__ _ [ _. I- ' + ._, 3
= ,
I , f , -
, y a
i /* P ' - f i t4 l / w t
?
! - -- l- f a
La EO f i i
> * * ^ ,
i
/ __l i ,
LJ ' I_ t i
' / ~
i
* / i i
y f
' / -
>- / -
< i 8
/ l ~
$ t
_t F / o _ 6 [
- 3
/ ,
c *
* /
6 Z i . ( O 4Q~ / i 6 i V * /* 3 e i
' / f ,
c l
* / i .
i p 6J , Q: '
' / !
-i i ,
Z i / i l 6 y 6 / ! t i
/ ,
LJ ' e C *
' i / - .
/ e 4
' / .
3 0 -_ _.. _ i / I I t , _8/ I . 6 7
/ t i 6
/- *
/e e
/ 4 6 . .
/ .
8
/ <
/ 9, 20 i ,
t e ,
/ . ,
1 . . , , ;
/ *
/
- r r, p-I .
g **/ i e e i . , -k , 3 ! 1, .
, ~~T' i
. e i .
' -i 4 i
;_ .._. ._ p -p. ,
10 ; ; ,
- i .
- l l , ,
_e , i , r r-o b i _- .,
. . . u. , -F- 4 I t n s
20 2'.: 0 . 12 16 4 8 0 HOT STANDBY TIME (HOU'45) _
OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP OP-8 REVISION 6 I DATE 7/5/83 PAGE 19 OF 23 (]
'% J TITLE. CONTROL ROOM INACCESS!BILITY REQUIRED LEVEL OF CONDENSATE TO C00LDOWN TO 350*F.
D ", - - . _ _ -
- :=== -- = =
n= ::- ==. : =. = . -- . . . . ::. =_ . . === = = -. -..= :--: k
. = ... .. - . . .
_ _ _ _ _ _ _ _ . . . . __.._.---.=..=.._=__..._-._:.=....-1Hc 4 . --
--- = . -- :
. - . . . . _ . . = - := - .
..- -._ -. . -=__ _ . _ =- - - _.. - - - ..: 2 Hrs
=- - --
.._/_:
. . . . . - . . . :- .f - ., y,
, a . . .
.--/- : . , : Mrs y/_
. . /. ._ , 5 i:rs
- .f. 5 u.,5
._, /=._-.
X .:=-- 5~ # ~- _= =.. .E /=N2:Y[I?'.)-fd 10 ' Hrs
/. ' 12 Ws w =_.-
_ - - _ . . .==-/._..z= _ fg./-l._ ._._.=.
~ = ==-
== ---
._ ==.= ./.: '=/.= --.
-- : --- =- - .= -.F.=? . -y y - -
~==[' ~~g.=$ .-/~Gg~ ='.)M 3
/.:= . =:- . ,- .-,.., ,& f/.=g 2,, 97, z
e, _ Hrs a f.. ,_--/.
.= / - -. . . _-. :-/=- - g g_ :- j'./ _--./...,i w - / -/. . . :. .- - . .f- -/- .
y
..v
.,%- masse
- - .l
+ - -p.- -
.. -f ; _ .
L~ ~ gg ~"-- - q g / s' -- - -- = P R.v,.":.u y < t.n
,0
,/ :=/- _ ; . . - -r/-- . . -/y .=--/ -
-/ -
/ - ~~- ;i,,iG 2 /-- , ._ g _
w + ,,_, s. j
, /- - ,*/- ._ -(Ow-,. r. . .d-M..:.
/ ,' ,l - , , ,
s_
,1' rs',r
-;f " '
'_f
/ ~'
C ' ,/ ,-/, i . L ., ,-',._",/ g , u M&pp' , p. ,! ,- '~
,' f, W,h;' f , --
1_ .--.h,/~I -.' /'
,_mi,.-: , . - . - . . . _ . - .- -
9- .+-f.,7?:' ,
.Q - - . , -
J-/ . . . _ hhhl,.-l 1_ 1 -
' 's,r/A-/'
f,~Fff::
- .. = -. - .- == . ;
/. -
.-=.:_.-- I
'f -._~--...- . -....--'*.-:----
.- ---_'- ~-- .. = .. -.--- : =.
- . - . f/u4'-
.- _ =--- ---
-y-; ._
s- _ - . - - . _ . ..-- -= . . . . - ____ u_.-.----- _ =2.- _- :r.:_;E= - l y -- ==---- .= -: .--
=. =.:.: _. -
A 0 2 4 6 8 10 i2 U l I DURATION OF COCLDOWN TO 350*F (HOURS) l
NUMBER EP OP-8 1 1 AND 2 REVISION 6 / D iABLo CANYON POWER PLANT UNIT NO(S)
- OATE 7/5/83 PAGE 20 OF 23 TITLE. CONTROL ROOM INACCESSIBILITY
_ _ _ _ e 2
. _ I - .._t.-
l .-
._w...__
m' - < ts ,-.
,...c
- .g..- p .4g
_ 4 d_ m_ p
. .q
; 1 p.-y. .w
- .n.
.._J ,,* P Q
i.. _.._ _. . t
. _ . . g . .. .t.,., .. . o. . do . ,
l....__..____..l_.__..__a.._...__.;,g.... _. . y n, p ,,, g . . .. ,. 9 - rf
. ej
- 9 %
. . , . , A R i
... q p.
.-q
. . ( .. ; 4 - -
~ - , _ . .
_ . _ _ . . s... ..
. _ e _.. '
' ...._...,f.
. .. _ . - , .. - ~ ..
'CQ ~.
._[......--._l-...
l
' .- j .. . . -
I . . . - . ~ - ca C -. . _ . . . . . 4 ._ . . . . . _ . - . 3 j
.' - /
t.... . 2 80 _ . . . . _.9._. m 1
~
//
l4 j l 70 -
.o . . ..i .. . .
/
/
.i__. .
/. ....;_.
/, / ' ,/ .__
$w ; .
a .. . g- _ . _ . gy . . _ _ t ......i..... L
- i LJ l -l 1
< j 40 -
.,7 ' . _.} ._
. . ,. .. y .
4- . .
,,/..4__..._____ ; #
30
.~....I 2.
f_.- l .__.'1'._ . f . . . . ._.. ._. -. C. _ . . . i
?.0 Y. ,
' llfl.. ~.. ~ L._
- . ..._. ... I t0 -
l i ! j . ' ' to soo 60 10 80 O 10 40 50 O 10 LO INDICATED LEVEL (*. OF SPAN) LI 406 PRESSURIZER LEVEL CORRECTION O PSIG;CURVES 70*F) FOR PRE I b (CONTAINMENT TEMPERATURE =100*? EXCEPT AT :
NUMBER EP OP-B DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION ,6 . DATE //5/84
/m )
PAGE 21 OF 23 (U < TITLE: CONTROL RCOM INACCESSIBILITY e 1
. . . . _ .. . ...4
__....p... .
.. c .-.
o 0. 4 .......; . . . . .. i t. S 6
.u.
. . . . . . - .j . .. . ._.._ y c
- g. . ,-
p
. . . . . . . . . . p .. . . . ; .. . . _ . / . . -., ... . . - .
... . .. . ; . . .. _ . .__ .. .. _ . -, . . . . ; . . .. . _ f . e toO
.. . . . . . ..... .y ._ _ y . . . .. . , _e. .. .' . _ .
... . . . . . . . . . . . _ . , . . . ~ _ . . - . . . . . -
....._..p......_..
u... j, .
. . . . . _ . , ...__.._u .l.
.s en
_......._. . /./ - . . _ I.._. _ ... _. _ .;. . .
/ /.. . .-. . _ _ .
..s ... .- e...... .
/ ._ ,,f. .. f .
. . . . . . . .- . . . : , -./._ f .
- .- /4. . /..,/
ga _
.._-...n._-
. _ . . . . . . ,f . . . . . ._ _ -
< TO / .. _
/ ./s -._t..
. _ l' -. .. / . /.,./ . ...__...L.--.-._....._.
C. . ~ . . . . . m . . . . . ,. . w
..........L....__.f.... p j f'
. ...... _4 . . . .
o g 60 .__..4..._... :. '
, _. _...L..
,,,a
.: ../,j, / .,f....... . ..
-- 7.
_.u....-_....
. p .
n . . _L
..n ' f_j,f ._ _
._A.. . . _ . . _ . , . _ .
ta . . ( > p _ . _ _ . . -.
% j . . . . . .. . . . . . - .
..p,,
y y' j,,. J _..._.p..__
.._.. ,. ..._ n . _ ..
,,.a
..._.,,,7,,.
_............a.._..{_..._... C $O r p ... . .---L.,.,'-
, / , . . . . . . . . . _ . - . . . _ . . , _ _ . . . - .. _'..__
g .- . . // e . .... '- . _ . . _ j ...._..4..
. . . . . . , . . . . . . . . . . . . _. . . . _ _. g .__
__-._.s... .a....._.. ' 3o . .. - =: i,
--. . ... _. - .. _ . ._.+
._- .. __ J.
.. . . . .. * // .
L .._. .. . ,. -. s
. . -.Q__ . _-
- o. ..
. - p - . _ _ ~ _ _ - . . _ . . _ - - - _
t0 ,--
.._..._._a_.._
u._ . . . -
.._.......p.___..._..._....
3__.__ to
, ./
... . .....L.
. . 7.. .._. -....{
._.1
,p . . .- ! .. 4 ,
, . ./ , , .- ,
0 to 10 30 40 50 60 :o 60 30 soo INDICATED LEVEL (4 0F SPAN) STEAM GENERATOR LEVEL (WIDE RANGE) CORRECTION CURVES FOR STEAM GENERATOR PRESSURE (PSIG) . (CONTAINMENT ~ TEMPERATURE-100*F) l' l
- ((v)
NUMBER EP OP-8 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6 DATE 7/5/83 PAGE 22 OF 23 I- TITLE. CONTROL ROOM INACCESSIU'
-- 23cg MIN. TEMP. FOR /
f f P-250 ALARM "~ ~- AND ADMIN. LIMIT F '-
- HYDRO AND LEAK TESTS f -
CORRECTED FOR -
}, _ _ . . . . _ _ . .j INSTRUMENT ERROR.... .
220C ...
, 2100, . . _ _ _ _ _ - _ . _ _ _ _ . .
2000 - __._l- .f .. --
/.
190C I. I 1 .. g . l I 1 ECC' . _ _
. .I l . . . .- .
~
. _ .1 . _ . . _ _ _
1700 .
. d . . .; __ . . a ._ . .
1 160d ...-- l j . . . _ . . _ . . - - . . _ . 1 -- iSCC) . ( pgp pggp gpgg e 130g TECH. SPEC. LIMIT g c_ l LIMIT CORRECTED - - - - - - - FCR INSTRUMENT . . :.-- 1204 . l ERROR 1100 u . G,100C _ . . _ _ . . _ . . _ . . w g: , 90Cl _ _ _ . . . . . l -- -- - - . - . .- 800 . ._._..._ ____. ._ .
} . _ _ _ ._ . _ _
od\ . _ - - . . _ . . _ _ . . . . . . _
~ ~
' - ~ ~ " - - - ~ ~ ~
l, _ _ . . . . - AX. PRESS. 6CO - FOR RHR
. . _ - . . . . . . OPERATION '
-f___.--..--_.-
SCC'
- j- r
__ ._.._.% SATURATION CURVE ACC . A 3CL . _ _. _
"- ^^-- -'-
- MIN. PRESS. FOR --- - - - - - - - -
203 RCP OPERATION MAX. TEMP. FOR h l . . RHR OPERATION . . Ten - L. .. _. .... .. euo suu ovu ,vu r O. t ivo e v'v svu
NUMBER EP OP-8 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6 DATE 7/5/53 PAGE 23 OF 23 d TITLE. CONTROL RCCM INACCESSIBILITY 5
- 4 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. Designate this event an Alert. Notify plant staff and response organizations required for this classification by imolementing Emergency Procedure G-2 " Establishment of the On-Site Emergency Organization" and G-3 Emergency Procedure " Notification of Off-Site Organi:ations" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation."
- b. If, after evacuation of the Control Room, control of shutdown system.s cannot be established within 15 minutes, redesignate this event as a Site Area Emercency. Notify plant staff and response organi:a-tions required by EP G-2 and EP G-3 in accordance with EP G-1.
O I O I
= ._
NuusEg EP ON23 Pacific Gas and Electric Company
} SS.G REVISION 3 DATE 07/05/83 C'N ' CEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE I OF 15 U f DIABLO CANYON POWER PLANT UNIT NO(S) 1 and ?
j ji EMERGENCY OPERATING PROCEDURE llb TITLE. NATURAL CIRCULATION OF REACTOR COOLANT W
- APPROVED. Y DATE PLANT MANAgA SCOPE If forced reactor coolant flow is terminated, (all 4 RCP's tripced) Natural Circulation of the coolant will occur when a temperature gradier.t exists be-tween the core and the steam generators. EP OP-23 provides guidance for tre operator when Natural Circulation is required. Special consideration is giv-en to prevent too rapid a cooldown which could cause upper head void forma-tion.
EP OP-23 assumes that off-site power is available but that all reactor coolar.t pumps (RCP) are available to cool thelore (e.g., loss of CCW to RCP's or RCP's failure). SYMPTOMS
-~ /
- 1. RTD bypass line low flow alarms.
(
- 2. Reactor coolant low flow protection bistable monitor lights on.
- 3. Reactor coolant flow indication decreases to near zero in all loops.
- 4. RCP breaker lights and motor ammeters indicate breakers tripped.
- 5. Possible RCP bus undervoltage or underfrequency.
AUTOMATIC ACTIONS
- 1. Reactor trip if above P-7.
l 2. Turbine trip above P-7. OBJECTIVES
- 1. Remove decay heat from the Reactor Coolant System (RCS) and maintain sub-cooling by controlling RCS pressure and temperature.
- 2. Maintain the Reactor subcritical.
1 ATTACHMENT _
- 1. Natural Circulation of Reactor Coolant
[v\ e
P-23 NUMBER 1 AND 2 3 DIABLO CANVON POWEQ PLANT UNIT NO(S) REVISION
-
- DATE 07/05/83 PAGE 2 OF 15 TITLE. NATURAL CIRCULATION OF REACTOR COOLANT RESPONSE NOT OBTAINED ,
ACTION / EXPECTED RESPONSE _
,; IMMEDIATE ACTIONS CAUTION: If 51 actuation occurs at any time, immediately go to E-0, Reactor Trio with Safety Injection.
Verify Reactor Trip: 1. Manually trip reactor. 1. All control rods fully inserted. a. If any control rod NOT
- a. fully inserted, THEN erer-gency borate 100 com for each rod not fuiiy insert-ed.
- b. Neutron flux -
DECREASING Verify Turbine Trip: 2. Manually trip turbine 2.
- a. All turbine stop valves -
CLOSED To limit an increasing RCS pressure O 3. transient, manually OPEN the normal pressuri:er scray valves PCV-445A & B during the RCP coastdown. SUBSECUENT ACTICNS CAUTION: Since RCP's are trippec RTO oypass temperature and associated interlocks will be inaccurate. Use wide range loop RID's and core ther ocouDies to determine RCS temperature.
- 1. Check RCS Average Temperature Wide Range Tem;:erature - a. Dump steam:
a. Decreasing towards 547'F
- 1) Manually open conden-ser steam dump valve OR manually open stear generator 10% dumps.
I h
U BE bU 1 AND 2 DIABLO CANYCN POWER PLANT UNIT NO(S) *
- DATE 07/05/53 s PAGE 3 OF 15 TITLE NATURAL CIRCULATION OF REACTOR C00LANT 2
RESFONSE NOT OBTAINED 1 ACTION / EXPECTED RESPONSE SUBSEOUENT ACTIONS (CON'T)
- b. Wide Range Temperature -
LESS THAN 554*F
- 1) Verify feedwater flow control 1) Manually close valve.
valves - CLOSED
- c. STOP dumping steam. E
- c. Temperature - STABILIZES AT Sa7*F cooldown continues, THE'4 close the main steam 1so-lation valves.
- 2. Verify AFW ficw on FI 157, 158, 159 &
160 (VS3) Both motor driven AFW pur:cs running a. START non-operating motor
- a. driven AFW pump.
O Turbine driven pump steam supply b. Manually OPEN valve. b. valve FCV-95 OPEN IF 2 steam generator narrow rafige levels
< 15%.
- c. Manually OPEN AFW level
- c. AFW level control valves OPEN and control valves to recover restoring steam generator level to steam generator level.
narrow range indication.
- 3. Check RCS Pressure:
- a. IF pressure less thar,lE50
- a. Pressure - GREATER THAN 1850 PSIG. 5i9,THENverifySIacuation and go to E-0, REACTCR TRIP WITH SAFETY INJECTICN.
- b. E pressure decreasinc, THE';;
- b. Pressure - STABLE OR INCREASING.
- 1) Verify pressurizer PORV's closed; if not, manually close.
- 2) Verify pressurizer hesters on; if not manually turn : r pO
BER P OP-23 1 AWD 2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 07/05/83 PAGE 4 OF 15 TITLE NATURAL CIRCULATION OF REACTOR COOLANT RESPONSE NOT OBTAINED ., ACTION / EXPECTED RESPONSE
,; SUBSE00ENT ACTICNS (CON'T)
- c. After the RCP coastdown, if pressurizer spray is required to control RCS pressure:
- 1) OPEN pressurizer auxiliary i spray valves CVCS-8145 and/or 8148.
NOTE: Table 5.7-1 of Section 5 of the Technical Specifications limits the numcer of unheated auxiliary spray cycles if tne spray water tem;erature and pressurizer water tem;erature differential is >320 F.
- 2) Position the nor al pressurizer spray valves PCV-455 A & B, in MANUAL for desired RCS pressure control.
NOTE: Positioning PCV 455 A & B allows for some pressuri:er spray bypass flow tnus giving more FINE RCS pressure control. 4 Check Pressuri:er Level; Level - GREATER THAN 17't, a. Verify letdown isolation,
- a. if not, manually isolate letdown,
- b. Manually control chargin;
- b. Level - TRENDING TO 22'; to restore pressuri:er level.
- c. Manually control charging
- c. Verify seal water flow to the to restore adecuate seal reactor coolant pumps, water flow to RCP's.
1 i CAUTION: Do not tnrottle AFW flow until water levei is aoove too of U-Tubes. (69% WR)
- 5. Check Steam Generator Levels:
- a. Continue filling stean
- a. Level - IN NARROW RANGE. generators until level is in narrow range.
i l l
NUMBER EP OP-23 REVISION 3 OlABLO CANYCN POWER PLANT UNIT NO(S)_ 1 AND 2 DATE 07/C5/E3 PAGE 5 OF 15 d m LE. NATURAL CIRCULATION OF REACTOR CCOLANT RESPONSE NOT OBTAINED j ACTION / EXPECTED RESPONSE t SUBSEOUENT ACT:CNS (CON'T)
- b. Throttle AFW flow to maintain range level at 33%.
- 1) Shutdown the turbine driven Aux. Feedwater Pump at 33*. Narrow Range Steam Generator Level.
CAUTION: Since RCF'S are trippec, RID typass temperatures anc associated interlocks will be inaccurate, use wice range icop RTD'S and core thereccoucles to deter-ine RCS tercerature.
- 6. Verify Natural Circulation From Trending Values:
- a. If 50'F subcooling can n
- a. Verify RCS subcgoling by observing NOT be verified:
(v) greater than 50-F subcooling margin monitor (VE2). 1) Verify using c:re average them.00:u le reading (;t. UCCC1) on the P-250 ccm-puter.
- 2) If the P-250 is net available, use '.0 core centerec :ner-mocouples to ceter-mine core outlet temperature.
- 3) Lower stean pressure setpoint en tne Steam dum: valves to provide a core outlet tem:erature of < 600-F.
- b. Steam pressure - STABLE.
- c. RCS hot leg temperature - STABLE OR SLOWLY DECREASING.
NUMBER EP OP-23 , OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3
*
- DATE 07/CS/83 m LE NATURAL CIRCULAT:0N OF REACTOR COOLANT i
RESPONSE NOT OBTAINED T-ACTION / EXPECTED RESPONSE .
. SUESEQUENT ACTIONS (CON'T)
- d. Core exit TC's - STABLE CR SLOWLY !
f DECREASING i
- e. RCS cold leg temperature *
- NEAR SATURATION TEMPERATLRE FOR STEAM PRESSURE.
- 7. IF condenser NOT available.,
- 7. Transfer condenser steam dumo to TEEN use steam ger.erator cressure control mode. 10'. dumps.
- 8. If D-12 is activated take the following steps:
c
- a. Place both steam duma inter-lock switches to the Sy; ass Interlock position (s; ring b.
return). Block both trains of steam O line safety injection circuit.
- 9. Monitor the NIS cnannels to veriff continued subcritical status of the core.
- a. Manually re-enerci:e
- a. When neutron flux has decreased below P-6, 10~ arcs in the source rance de e: ors.
intermediate range, verify source range detectors re-energi:ed.
- b. Transfer a nuclear recorder to the source range scale.
- 10. Maintain Stable Plant Conditions
- a. Pressurizer pressure - AT 2235 PSIG.
- b. Pressurizer level - AT 22%
NUMBER EP OP-23 DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISION 3
+ DATE 07/05/83 PAGE 7 OF 15 /~'N TITLE: NATURAL CIRCULATION OF REACTOR COOLANT RESPONSE NOT OBTAINED d ACTION / EXPECTED RESPONSE
- f. SUBSEQUENT RESPONSE
- c. Steam Generator narrow range levels - AT 33%.
- 11. In'.estigate the cause cf the loss .
of forced reactor coolant flow.
- a. If RCP flow cannot be. ,
- a. If RCP can be returned to service restored rapidly, refer '
refer to OP A-6 Reactor Coolant to Vol. 9 of Plant Man- l Pump Procedure. ual to determine tne length of time tne olant can maintain " HOT STANC-BY" based on Condensate Storage Tank water in-ventory, if using atmos-pheric steam dum:s for steat-generator pressure control.
) b. If RCP's are returned to service refer to EP OP-5 Reactor Trip Without Safety injection.
NOTE: If the decision to initiate cocidown is made, it will be necessary to corate the reactor coolant. This process should be started as soon as possible to take advantage of the higner natural circulation flow rates immediately following a trip.
- 12. Borate the reactor coolant system to the cold xenon free condition via ,
the BIT (the preferrec path).
- a. OPEN MOV 8803 A and B.
- b. OPEN MOV 8801 A and B.
- c. Verify flow on FI-917 (VB2).
NOTE 1: It should take approximately 15 mirutes to inject'the BIT based on 120 gpm centrifugal charging pump flow and maintaining ^ adequate seal injection to the RCP's. - NOTE 2: It may be necessary to inject the EIT as many as three tig.es to achihve a colc xenon free concentration. IA ( )
%./ ,
1 M k
E EP OP-23 DiABLo CANYON power PLANT UNIT NO(S) 1 AND 2 3 DATE 07/C5/S3 PAGE 8 OF 15 TITLE NATURAL CIRCULATION OF REACTOR COCLANT ' O RESPONSE NOT OBTAINED j ACTION / EXPECTED RESPONSE SUESEQUENT ACTIONS (CON'T)_ !
- d. Keep pressurizer heaters ener-gized during boration.
- e. Maintain pressure using aux-iliary spray.
- 13. Verify Cold Shutdown boron con-centration by sampling:
- a. RCS hot leg.
- b. Pressuri:er li;uid
- b. Pressur':er licuid may not be the same concentration as tne ;
active portion of the RCS.
- c. Letdown line 14 Line up the CVCS makeup control system for the new boron corcentration and place the system in AUTD.
- 15. Comence degassing ne RCS consecu-tively with cocidown to a hydrogen concentration of less than 5cc/Kg.
Refer to OP BIA:III.
- 16. Start all fans if possible.
- 16. Verify that all Control Rod Drive Mechanism cooling fans are in operation.
- 17. Start RCS cocidown,
- a. Maintain cooldown rate LESS THAN 25'F/hr.
- b. Slowly increase rate of steam dumo to start the cooldown.
h
^ ^ - - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
l 1 NWBER E? OP-23 DIABio CANYCN TOWER PLANT UNIT NO(S) 1 AND 2 REVISION 3
- 07/C5/33
'DATE PAGE 9 OF 15 !
m LE. NATURAL CIRCULATION OF REACTOR COOLANT
' RE:;90NSE NOT OBTAINED 3 ACTION / EXPECTED RESPONSE .
SUBSEOUENT ACTIONS (CON'T)
- 1) Transfer steam dump contrcl to MANUAL.
- 2) Dumo steam using Me
- 2) OPEN dump valves as 10*; in manual c:nte::1 necessary to cbtain dumps, desired ccoldown rate.
CALTION: If tne steam generator IC'; cum::s are usec for coolcown, : ain- l tain steam generatcr pressures balanced to avoid an S! on steam generator-l differential pressure.
- c. Manually throttle aux-
- c. Verify Auxiliary Feedwater iliary feedwater flew, System is automau cally. as necessary.
maintaining Ste m Generator Narrow Range level ~at 33';.
- d. Monitor the Concensate Storage Tar.k.
V 1) If CST level is icw, and condensate pumps are avail-able resto e CST ievel by pumping down the condenser hotwell.
- 2) At LO-LO Level Alarm in the CST refer to Appendix A of E? OP-3A to sh1't CST suction to an alternate source.
- 18. Check RCS Hot Leg Temperature:
- a. DO NOT proceed until
- a. RCS hot leg temperature - LESS TICS not lea temperature THAN 550'F. '
is less than 550 F.
- 19. Comence decressurizing the RCS to approximately 1865 psig:
- a. IF letdown NOT in service
- a. If letdown is in service, THEN use pressurizer depressurize RCS using pres-surizer auxiliary spray. PORV's.
t (( g ] v> f
BER P OP-23 DIABLO CANYCN POWER PLANT UNIT NO(S) 1 AND 2 g 07/05/83
*
- OATE T;7ts NATURAL CIRC'JLATICN OF REACTOR COOLANT l RESPONSE NOT OBTAINED 2 ACTION / EXPECTED RESPONSE .~
- f. SUSSE0UENT ACTIONS (CON'T)
- 20. When the reactor coolant system pressure decreases below the P-11 setpoint (1915 psig) block both trains of tne pressuri:er low pressure safety injection signal.
CAUTION: SI actuation circuits will automatically unclock if RCS , cressure increase above 1915 DSIG
- 21. Maintain the following RCS conditions:
- a. RCS pressure - about 1865 psig.
- b. Pressurizer level - about 22%.
- c. RCS cooldown rate - Less than 25 F/hr.
- 22. Verify RCS cooldown:
- a. Core exit thermocouples -
Trencing down,
- b. Wide Range hot leg RTO temperature-Trending down.
- c. RCS succooling on subcooling monitor (VS2) - increasing (minimum of 50'F).
NOTE: Thermoccuole toggle switch on VS2 adjacent to subc0oling monitor gives ca::acility to monitor core succooling margin or reactor vessel head region subcooling margin. ! 23. Jepressurize RCS as follows: l If all CRDM. fans are running a. If all CRCM cooling fans a. l maintain 50*F subccoling. are NOT available for l operation: I
- 1) Maintain 200 F sub-cooling until RCS pressure is 1200 psi;.
I h
NUMBER EP OP-23 1 AND 2 REVISION 3 DIABLO CANYON POWER PLANT UNIT NO(S) .. , OATE 07/05/23 PAGE 11 OF 15 k TITLE: NATURAL CIRCULATION OF REACTCR COOLANT RESPONSE NOT OBTAINED . ACTION / EXPECTED RE500NSES SUBSEQUENT ACTIONS (CON'T)
- 2) Maintain RCS pressure at 1865 osig until RCS tem:erature is.
cooled down to 420-:. If letdown in service, depres- b. If letdcwn NOT in ser-
- b. vice, THEN use pres-surize using auxiliary spray. surizer PORVs.
- 24. Continue RCS cooldown AND depressuri-zation:
- a. Mainta'n cooldown rate - LESS THAN 25"F/hr.
Maintain subcooling re;uirements b. If the retuired suo-
- b. cooling cannot be main-of step 23.a. tained, Sf6P the ce-pI pressuri:ation and re-t'd establish the required subcooling.
- c. Maintain the reactor coolant system pressure-temperature relationship within tne boundaries of the Plant Cooldown Curve, Vol. 9 of the Plant Manual.
NOTE: Plant Cooldown Curve attached is for information only.
- 25. Verify NO voiding in Reactor Vessel 25. If voiding is sus;ected cue to large variations in Head Area. pressurizer level or R'/L:S Plenum Range <100'., THEN repressurize the RCS to collapse the voic in the head area. Also re'er to EP OP-44, Gaseous Voids In The RCS.
- a. Pressurizer level RESPONSE NORMAL.
,[m), I
l DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 tjuMBEREPOP-23
** ' DATE 07/05/83 l e
PAGE 12 OF 15 TITLE: NATURAL CIRCULATICN OF REACTOR COOLANT 4 RESPONSE NOT OBTAINED ACTION / EXPECTED RESPONSES , .. 4 SUBSECUENT ACT!ONS (CON'T) I
- b. Reactor Vessel Level Instrument Plenum Range (FAM FNL) indicating 100%.
I
- 26. If all CRCM fans are NOT in operation:
- a. Maintain RCS at 1200 osig while continuing to coolcown to 350 F.
- b. Maintain 1200 psig for approxi-mately 8 hours to allow the upoer head to cool off to a temperature less than saturation for 400 psig (445;F) before continuing with tne depressuri-zation.
27. Check if SI system should be disabled: RCS pressure - Less than 10C0 psig a. DO NOT disable any SI a. but greater than 700 psig, system ecuipment if greater than 1000 osig.
- b. DO NOT disable any SI
- b. Average RCS temoerature - LESS 350 F but RCI cold leg tempera- system equioment if ture greater than 323 F. Average RCS tempera;ure is greater than 350 F.
- c. Isolate SI accumulators.
- 1) Close the isolation valves.
- 2) Rack out each isolation valve breaker.
- d. Disable the safety injection pumps by opening the DC control power to the pump breaker.
- e. Disable the non-operating centri-fugal charging pump by opening the DC control power to the pump breaker
. l l BE OIABLO CANYON POWER PLANT UNIT NO(S) 1 AN0 2 C'd 3 DATE 07/05/E3 PAGE 13 OF 15 TITLE NATURAL CIRCULATION OF REACTOR COOLANT I < RESPONSE NOT OBTAINED ACTION / EXPECTED RESPONSE
~
SUBSEQUENT ACTIONS (CON'T)
- 28. Open additional letdown orifices if necessary to maintain normal letdown flow.
- 29. Maintain adepuate RCP Seal In-jection Flow.
- a. Adjust HCV-142, as necessary.
- 30. When system pressure has been reduced to approximately 400 psig, hold it con-stant at this value by reducing auxiliary spray flow and energi-ing the PZR heaters as necessary.
- 31. When RCS hot leg temperature has been reduced to less than 350 F and pressure is between 380 420 psig, place the RPR (5 system in service recirculating from
\ hot leg a to the cold legs, in accor-dance with OP B-2:II RER Normal Oper-ation.
- 32. Prior to RCS cpid leg temperature being reduced to 323*F insure the pressurizer PORVs are providing low pressure pro-tection by verifying the Low Pressure Setpoint protection c/o switch is CUT IN (VB2).
- a. If the positive disclacement reciprocating cnarging pump is operating:
- 1) Verify MOV's 8701 and 8702 are open.
- 2) Rack out their trotor breakers.
- 33. Continue RCS cooldown to below 200 F with RHR System.
1 l l NUMBER EP OP-23 DIASLO CANYCN POWER PLANT UNIT NO(S) 1 AND 2 REVISION - -
' ' DATE ' 07/CS/83 TITLE NATURAL CIRCULATION OF REACTOR COOLANT i
I E RESPONSE NOT OBTAINED . ACTION / EXPECTED RESPONSE e, SUBSEC'UENT ACTIONS (CON'T) 1 CAUTION: Depressurizing tne RCS cefore tne entire RCS is belcw 200'F may result in void for ation in the system. I i
- 34. Continue Cooldown of Inactive Portion I of RCS:
- a. E fans NOT running, i
- a. U::::er head region - ALL CROM THEN 00 NOT cearessuri:e FANS RUNNING.
RCS until uccer head 0 cools to less tnan 200 F l (aporoximately 27 hours af ter RHR syste-i is placed in service). i
- b. DO NOT depressuri:e RCS
- b. Steam Generator U-Tut:es - until steam generators CONTINUE DUMPING STEAM have stopoed steaming.
from all steam generators until it is VERIFIED that they have stopped steaming.
- 35. GO TO Operating Procedure L-S,
" Plant Cooldown From Minimum Load to Cold Shutdcwn", Step 21 for continued cocidown of the RCS to a cold shutdown condition using RHR forced cool down.
i h
NUMBER EP CP-23 OlABLO CANYON POWER PLANT UNIT NO(S) l AND 2 REVISION 3
- DAT;- 07/05/83
' PAGE 15 OF 15 TITLE- NATURAL CIRCULATION OF REACTOR COOLANT 5
APPENDIX Z 4, EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this eTergency 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 res::ense organizations re:;uirec for tnis classification by implementing Emergency Procedures G-2 " Establishment of the On-Site Emergency Organizaticn" and G-3 " Notification of Off-Site Emergency Organization" in accordance with Emergency Procecure G-1 "Accicent Classification and Emergency Plan Activation."
O sa
. MX:?2! TA ,.
~ L _
' DEPARTMENT OF NUCLEAR PLANT OPERATIONS __ . . ..
DIABLO CANYON POWER PLANT EMERGENCY OPERATING PROCEDURE !4 TITLE: NATURAL CIRCULATION OF REACTOR COOLANT 2500 __ _ :- _ . = _ _ .
- _ ___ _ __=__-
( ';2400 _ ( \ / ___ .- 2300 , 2200 _
)
2100 , a 2000 1900 s 1300 _ ll__ _-
- r. --
- 1700 - --
g - rass-
- g. .- ,. g p c
- q 1600 ___ b _ q__;_.__:; ..-
_ n n s .-_- _
-_g.,.
. m- -
1500
--=
-- , = _ - - - +
~
1400
~;
1300 :
-f _.
fs - ( !v )1200 i,.d 1100 b -
**~ --
' p
_E: 1000
- ~ - -
ti 2:. __ ,
<=' w Eli 900 _ _ _ . 7p ggpp- -
- ::. - t:
/ _!$'y _ " .____.-__._._f_
h M_ @_.
!!.800 . , .
VM^1-4StiV1 ktiCEE8MM h,: l;; ,00
- nmmm .= vuhmAEr e gy e- - . _- __
~'.
m 600 m / -'
;_p:
__."__Es4 mm
;L a __
= -s 500 z m 2 5 c-=.;'
~
400 W i- 9_' ._. i, ;~ . _ ; __, w7-
.w- m u.;
_,y- g-- w, , _ _ = = _ 300 .. .
~
.W.t% / i'H LE M ;. 1
'u^= -
p aw w tn
=
kw : ; m_ & 100 -
<x /= s --
) - %- ~
( (s
./ 0 _ s'2 _ -7 ^45=
300 af,] 500 600 700 'F ,,,,. 0 100 200 TEMPERATURE 'F [*;
. , . .-- - _.- _-- ,-- ,_ ,,,a m
NUMBER EP R-1 2GFJB Pacific Gas and Electric Company REVISION 10
- m DATE 7/5/83 DEPARTMENT OF NUCLEAR PLANT OPERATIONS 0I DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE lOF 15 EMERGENCY PROCEDURE TITLE; PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY W RELATED) AND/0R OVEREXPOSURE APPROVED:
PLANTMAgER 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) from an external source.
- 3. Overexposure (or suspected overexposure) from an internal source.
- 4. A combination of the above.
4 Injuries or illnesses which do not involve radioactive contamination or overexposure are handled in accordance with Emergency Procedures M-1 or M-2. This procedure and changes thereto requires PSRC review. I DISCUSSION Any radiologically related injury or illness or potential radiation 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 q evidence which may contribute to the understanding of the incident and < assist both in care of the injured and in preventing re-occurrence. IWEDIATE 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 location.
~
- 2. Shift Foreman (Interim Site Emergency Coordinator)
O- s DC0084 IIX a
< *L - _ _ _ - - _ - _ _ - _ . _ _ .
1 AND.2
- 0 0iAeto cANYOrd PCwER PLANT UNIT NO(S)
DATE 7/5/83 PAGE 2 og 15 PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY M LE. RELATED) AND/0R OVEREXPOSURE
- a. Evaluate plant status that rnay 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 perennel such as the project construction EMTC ] to the scene of the injury or illness if required.
- c. Notify Chemistry agd Radiation Protection personnel (ext.
L. ,-
- 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 Shif t Foreman shall direct all subsequent actions until relieved by the long-tenn 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.
- b. Take actions as specified in the following sections as appropriate for the particular occurrence.
Section 2: Minor injury when contamination is present. Section 3: Serious injury when contamination is present. Section 4: Overexposure from external source Section 5: Overexposure from internal source. .
- c. Perfonn the notifications required by Appendix Z " Emergency Procedure Notification Instructions."
M)TE: Form 69-9221 " Emergency Notification Racord" is provided to record notifications not docurrented elsewhere.
- d. Collect personnel dosirnetry assigned to the individual and have it evaluated.
't Ci DCOO84 21X
N R-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1.AND 2 DATE 7/5/83 PAGE 3 OF 15 O TITLE: PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/0R OVEREXPOSURE
- e. Begin gathering infomation to assist the long-tenn Site Emergency Radiological Advisor in his evaluation. Guidance
~
on things which should be investigated is given in Appendix 2 " Factors to Consider in Making a Preliminary Evaluation." l
- f. Close out the event with the following written reports:
- 1) Report to NRC (required within 24 hours for an unusual Event, or within 30 days for a report under 10CFR20.403).
I
- 2) Form 62-4587 " Report of Industrial Injury to Employee."
- 3) Fonn 62-4586." Employers' Report of Occupational Injury or Illness."
- 4) Nuclear Plant Problem Report. (See Nuclear Plant Administrative Procedure C-12.)
OTE: Reports to NRC and the Nuclear Plant Problem Report are not required for minor injuries or illness for which onsite first aid and decontamination is adequate.
- 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.
l 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.
M: These personnel surveys are in addition to other raTiological surveys (e.g., work area, equipment) which may be required by radiation protection management.
- O DC0084 31X
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 . f0 OATE 7/5/83 PAGE 4 OP 15 ' l PERSONNEL INJURY OR ILLNESS (RADIOLOGICALLY l N RELATED) AND/0R OVEREXPOSURE
- b. Decontaminate the wound using the standard procedures
- discussed in Radiation Control Procedure G-4. In cases of i severe contamination, where there is a realistic possibility
~
that havesignificant occurred, internal retention it is desirable of radionuclides to retain may(or wash solutions samples thereof), swabs, and other such material which may be useful to the Site Emergency Radiological Advisor. OTE: Refer to Emergency Procedure RB-5 " Personnel Uicontamination" in the event normal decontamination facilities are overloaded or unavailable.
- c. Complete any additional first aid measures.
- d. Complete accident report Fom 62-4587, " Report of Industrial Injury to Employee" and forward t'o plant clerk for processing.
ETE: 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 Fom 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.
- a. Call San Luis Ambulance and French Hospital and have the patient transported to French Hospital. The detailed 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 infomed of the status of the ambulance.
- b. During the interval until the ambulance arrives keep the patient as comfortable as possible. Survey and decontaminate the patient to the extent that time and conditions permit. Do not decontaminate the patient if it will aggravate his injury. Record survey results on the l
" Skin and clothing Decontamination" Form (Fom 69-9392.)
l DC0084 4IX
N N 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/5/83 PAGE 6 OF 15 O PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY b TITLE: RELATED) AND/OR 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-tenn 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 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.
OTE: Refer to Emergency Procedure RB-5 " Personnel Uscontaminationd in the event normal 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 team 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 applicable limit contained in Radiation Control Standard No. 1, and where the individual does not require prompt medical attention for any other reason. Personnel suspected of overexposure shall not 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,
- 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: DC0084 SIX 1 - - - - - - - , _ _ _ . , _ _
N E R-1 DIABLO CANYON POWER PLANT UNIT NCMS) 1 AN,0 2 , DATE 7/5/83 PAGE 6 op 15 l TITLE: PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/0R OVEREXPOSURE h l 1) The patient is known or suspected to have received at least any of the following: l
'. a) 25 rem to the whole body, active blood forming organs, lens of eyes, gonads, head or trunk, b) 150 rem to the skin.
I 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 dematitis (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.
Reoness, 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 permit.
Do not aggravate any injury or unduly alam the patient in performing these operations. Record survey results on the
" Skin and Clothing Decontamination" Fom (Fom 69-9392) and/or " Radiation Dose Rate Survey Record" (Fom 69-9316).
In cases of severe contamination, handle as in Step 3.c to the extent practical.
- d. To the extent practical, save all vomit, urine, feces or other samples which may assist the long-tem Site Emergency Radiological Advisor in evaluating the accident. This is particularly important if internal deposition of radioactive materials is suspected.
l l l 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 l processed for evaluation. DC0084 6IX
N DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 O DATE 7/5/83 PAGE 7 OF15 PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY TITLE: y 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 ,
1 I 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 permissible 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 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.
- c. Survey the patient thoroughly and record the results on the
" Skin and Clothing Decontamination" Form (Fonn 69-9392).
- d. Decontaminate individual to as low as practical without 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, determine the necessity for further medical attention or surveillance.
- f. Collect and save any urine, feces, or vomit wnich is passed from the patient. The long-term Site Emergency Radiological Advisor may request that special urine samples be collecte-d 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 arrangements to have all urine, feces or vomit samples retained for radiological analysis.
!I DC0084 71X
1 AND 2 N OtABLO CANYON POWER PLANT UNIT NO(S) O DATE 7/5/83 PAGE 8 OF 15 PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY T TLE. RELATED) AND/0R 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."
- 9. Emergency Procedure G-2, " Establishment of the Onsite Emergency 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."
- 13. Ernergency Procedure OR-1, "Offsite Support and Assistance" ATTACHMENTS
- 1. Fom 69-9221 " Emergency Notification Record."
- 2. Fonn 69-9316 " Radiation Dose Rate Survey Record."
- 3. Fonn 69-9392, " Skin and Clothing Decontamination."
- 4. Form 62-4587, " Report of Industrial Injury to Employee."
l DC0084 8X O
N M ER R-1 otABLO CANYON POWER PLANT UNIT NO(S) . 1.AND 2 DATE 7/5/83 PAGE 9 OF 15 PERSONNEL ILJURY OR ILLNESS (PADI0 LOGICALLY m LE. RELATED) AND/0R OVEREXPOSURE
- 5. Form 62-4586, " Employers' Report of Occupational Injury or
. Illness."
- 6. Form 62-6015. " Medical Referral ." l
- 7. Light Duty Program letter. J
- 8. Safety, Health and Claims Personnel to Be Contacted for Reporting !
of Injuries at Diablo Canyon (1/83). l 4 i
) '
DC0084 9X l l l
l I-1 AND 2 f0 D IAsto canyon POWER PtN4T UNIT NO(S) OATE 7/5/83 10 or 15 PAGE l PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY ! Tira RELATED) AND/0R OVEREXPOSURE . APPENDIX 1 MEASURES TO BE TAKEN IF MEDICAL CARE IS REQtlI The follcwing are the procedural steps to be taken in treatment: 543-2626, Emergency No. 543-7911)
- 1. Call San Luis Ambulance (Phone and provide the following information:
- a. Name of caller.
+ ~
- b. Company affiliation.
- c. Phone number of caller. (Where he can be reached.)
- d. Name of injured or ill person,
- e. Where the patient is located. '
1 f. Where the patient is to be transported (French Hospital).
- g. Nature of injury or illness.
- h. Patient is contaminated, i.
Any other medical information which might be pertinent to transporting the patient. 69-9221. " Emergency Noti fication Record this information on Fonn Record," or other suitable log. Contact the Security Shift Supervisor [ ]and_havehimcalland 2. the security force at the Port San Luis entrance bItisalsoYdvisable alert them that the ambulance is entering. to have an escort accompany the ambulance from the Security Building to the first aid room to minimize the delay in reaching . the destination. Call ahead
- 3. The victim shall be transported to French Hospital.and provide the to the hospital (Phone 543-5353) infonnation:
- a. Name of caller.
( ( .,
*1 OC0084 10X L __
N R-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1.AND 2 oats 7/5/83 O TITLE: PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY PAGE 11 OF 15 RELATED) AND/0R OVEREXPOSURE APPENDIX 1 (Cont'd) MEASURES TO BE TAKEN IF MEDICAL CARE IS REQUIRED
- b. Company e.ffiliation.
- 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 infomation on Form 69-9221, " Emergency Notification 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 l 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.
P0TE: Two hospital kits and radios are stored in Access Control. XHHitional equipment and radios are also available at the PG&E San Luis Obispo Service Center.
- 7. Two additional individuals qualified in radiation monitoring should be dispatched to French Hospital to assist hospital personnel.
K)TE: Refer to EP OR-1 "Offsite Support and Assistance" for air ambulance and medivac support. O DC0084 11X
l i N R-1 OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 7/5/83 I PAGE 12 Op 15 PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY TITLE: l 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) infonnation 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 Connon to All Accidents
- a. Date, time of occurrence.
- b. Basic reconstruction of events.
- c. Probable source (s) of radioactivity involved.
- 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 nonunifonn 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?
DC0084 12X l
NUMBE P R-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 O DATE 7/5/83 PAGE 13 op 15
- PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY TITLE.
RELATED) AND/0R 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?
O DC0084 13X
N R4 otAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 7/5/83 PAGE 14 OF 15 PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY TITLE. RELATED) AND/0R OVEREXPOSURE 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. 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 where the exposure (for the quarter) exceeds the following:
5 Rem Whole Body l 30 'em Skin of Whole Body 75 kem Extremities Notify the NRC Bethesda Operations Center using the red phone in the Control Room as a minimum within'one hour. g 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 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 Director, NRC Region 5, by telephone and telegraph, mailgram or facsimile within 24 hours of the event. Indicate the notification is pursuant to 10CFR20.403 (Notification of Incidents).
- c. 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 onsite decontamination is required (soap and water washings do not 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 l
Organizations" in accordance with Emergency Procedure G-1
" Accident Classification and Emergency Plan Activation."
i DC0084 14X
N R4 DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 DATE 7/5/83 PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY TITLE. RELATED) AND/0R OVEREXPOSURE
- d. In addition to the notifications perforTned under "c." above,
? for a Notification of Unusual Event, if the case involves an overexposure from an external source which exceet:
25 Rem Whole Body 150 Rem Skin 375 Rem Extremities Imediately notify 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 NRC 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: q
- b. Compensation Claims Representative in the Department of Safety Health and Claims, per the attached list of personnel.
NOTE: 1) The System Dispatcher will handie the notification of General Office Personnel if they cannot be promptly reached.
- 2) Nuclear Mutual Limited (NHL) holds the Company 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 Department. The Department 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 (ANI/MAELU)
. holds third party insurance coverage and would be:
similarly notified in accidents involving a third party. I i .) DC0084~ 15X
- 8 4
4 _~- --. . ,
9 e W W W M Z K A g M w E k" w ( W C I M z 3 w ll> C. I ac: C 2 5 w ww C C 4= W 4 C4 w M w E M
>a w Z E E
<3 C aw ===
L} W ma u
==
auC w3 w ems y J C. W 8 (x (h>"i>v > e C C. 3 W cc, w Z 8C C
~ K O W C E W IdsI
{
< =
G
& C w w C E l
I Y W 5_ W E M C m M b
>= b e < <
8 E
- m
=
w
> C N E w cc W W
% G3 J f*") ene (
U I l d a w i = a.
.s
- y w
l
-._,_,o -
DEPARTMENT OF NUCLEAR PLANT OPERATIONS 50-9316 7/80 (100) DIABLO CANYON POE R PLANT RADIATION DOSE RATE SURVEY RECORD SURVEY NO. TIME SWP/RWP NO sTE -- AREA OR EQUIPMENT OF - 5}!EET TYPE OF SURVEV NEUTRCN ! GAMMA l BETA e rad /hridisunce ' mR/hridisuncenrem/hr i disunch ITe4 DESCRIMION NO. i l l
.j l
l i I _! I I I J I 1 l . i l l __ l l I I I I I - O - j' I .. I SURVEYED BY TYPE Dtist,40R SERIAL NO. DATE CALIB. DUE SURVEY TYPE INSTRUMENT 1 I _ sETA l am . l NEJTRON l COPf9ENTS RECOMMENDATIONS DATE _ SURVEY REVIEWED
, SUPERVISOR l
_ - . _ _ , . _ . . . . _ . . _ _ _ _ _ . . _ . _ , _ . ~ . . . . _ . _ _ _ _ .
l . 69 9392 7/81 (100) - , I DIABLO CANYON POWER PLNG SKIN AND Cl.0 THING DECONTAMINATION r .. ., . ...... .
.- ,,. . .... .. ;;.y;-
DECOM T AMIN ATION IN F O RM A TION MS 4 m - t l l e 66 i i e 6gMWM e WW eD
...s.... mum e
W
** e e
S . . te . , W .. . . _ _
w RIGIT $10E LEFT SIDE-FRONT REAR 3 sg , l\// (gre t w)) W
- ky/ ,t .
/
.A , A s t x /s f
<(.
1k YSO) $$ k h$$ ,
,gsi k \
- \ 'l i _
#~I k-( 7 ! _~
[ g RIGHT SACK _ , LEFT PALM RIGHT PALM LEFT SACX
.l l 4
/ _
f / Ap , 1 < a, e . 4' ,, - s p( )
! -) (
l I: 1 h M TORSO FRONT VIEW r, TORSO REAR VIEW
; \
Q PERSONAL CLOTHING n SKIN O PROTECTIVE CLOTHING
02 dea 7 Kev.1/7e PACIFIC GAS AND ELECTRIC COMPANY Report of Industrial injury to Employee
- 1. Name 6. Division ZIP
- 2. Address
- 3. e 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 accidenc 1.
2. O 3. 15. Signatureof Employee
- 16. Date injury reported:
- 17. Date 30 days elapses: 18.
- See Over Signature of Supervisor INSTRUCTIONS: This report (Itams 1 thru 15) should be written and signed by the employee person.
afly and countersgned 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 .iuperviser should fiil in the date of the report (item 16) and compute and notate the date 30 ders from the data the injury was reported (Item 171. If the employee later requires tressment by a doctor or becomes disabled, Form 62-4586 must be prepared and forwarded to me Safety, Health and C: aims Department /MMEDIATELY accompanied by the onginal of this report. If the employee is unable to fill out or sign this report. it should be prepared,.sgned by the supervisor and the empicyee should be given a copy within 5 days as required by law. If the injured employee cannot write English, the report may be made according to a verbal statement. If necoseery, the errcloyee may sign by a mark and a witness to the report should sign below the em. playee's rnark.
< O h __ ._- _ _ ___ _ _ _ _ _ _ _ _ _ _ _ _
if m wem o emannse your ngpris unemy imus lit of me intenmassa % senese susersee Die page one pruennt it te vast sammas paysema. O
. _ .f _ _ -ve.m. T,. .ny__ .r t. _ - - .n v
,* uune unearmens to provise tressment purasant to Laser Case Season 44WI snes:
W vennen 3 werving een afsor uruserstang to erovese esen truotment neefy tpe emeesvar et see name ene esersus of suen tremeng anveeen or %elity, one m entnee 5 voereing asys fenomenc inrees amannseen ansa swamet a servitse resort se tpe om. asever u .nasuse: (1) The nerne are seerso et innsres amensvee (2) The oneseves's eneescon 'insory a ooresnes Dv sne onvecen: (3) Pindrige en sammentemes (44 The mesmettwo . _ a reserves try the messeves: (S) The gaannes sourse, seems one eurseen of tressment: (S) If aseregneue, the emmeneuse reewnM tmse: (7) An oenneen en to aneener museums permanent ces"edityv e e to to antisseems see, if someomo, en asumsee of is emannt: 31 An osensen es to wnesper tne omoseves unit evennemiv ee eene to e=enge e trw assume-teen name performes et the tune of Inswy.
. .m__.___._._e__.e_._.m_.
O partenaerty. resort prenwety to tne emosever unnant (1) The amenoves's eeregeen oormais reesrn to usare: (2) The emereves's consstnen remaste pern or mer g iss== nere: (31 keessemera!tean er margrry is mamme or resemnesions. 444 The esenseves's annettien Deuemes pervronsit eres stemonary: St T% enenesse's seretten unsurgoes e ors ==ousy une=====a ayuncont cpenge: teries repery sneed cornoun a snoemment of the pressoas course of treatment reumasres.it erv, DV tfter Eromage8: (4) The esseteves sereferres to anutner pnvoesn for eenesneutest; l (7) The enWhsvos rmIEW resuegel asalttenal saucestem informesten. l l 9
.a. e,. Tr?S $ pacPlc SAS ans ELECTRIC COMP 488Y gnioiever's Report of Occuestionse insurY o' Ill""8 CONp10 TNT 1AL-for Un av Camoany Anortm's
.8 C,ev1GaSe g3petRAL Oppect GA ospeemakc W W es-== -..a g= e ,=an = ev.wou= t i ar g = . ACEUws.T wi.use n , Age wwwsum AC &otret eEPC AT % Men e
.l * *Jaa. Eaa w=w aa = ._ - =
_ .sa e . =m. _--- e n .s p . -
. e. = , '
e.as.p en . c
. me. mes.s
.m m. -.. .
i.e _ ai . Coa.s.a.
.m 3.
==.= G m
o.r. o.me. aw am ==
- e. auer a n
.C. m.-===.a
.m. .mmu.n .i. m.sm -
m.e.amu.m.a.m se . um. . .mm. .
- .',I l
- ._. . . w = m.
*- *t.sans so
- 1. O PACIFIC GAS AND ELECTRIC COMPANY 4. I.2". ** e uns
% n seats stwert sus estmacism, ca me cmwase
- PUSLIC UTILITY-Gas & Bearis ,
m an. a nn emes m g 2. . .i.
, s. . .a. .-. ~. .. e. . 4. s _ 5. .=._ _.1 .e
- ' 007-2199_ = " " "
.= ~, c = s.6..,.. %
7..=
- 6. ""* *=':?"',
6 -
', ! 8.-*"* **- = l an."*a """ ' ""
*** l o
9*'" CMALE OFEMALE l 10***""*"" ' *** "" l11* ^* !' 12**"""'""" se as g . "
- e.
- e. ca. %
gg. a .. , , . YEA RS S .een o.m. e g ,. ,.. .. _ _ = .. _-- ' i h' == *' ' - - - l U""'"* as-as
- =
A k.Iw a. IQW *
."n'"" C Q ow. '=e
- I j
\
u.~.. ~.-. I,s.,Cves ONO s ===.o===. 9.".'."
'.'.::"N'.
1 s. ~ ~ ~ -a- - * ===== .e caba e EGi _. l e ! 88 17,= w m.mn w = mese # . we
.m a -s 93 la aMas.
u A 9e 9T T as
**'a= * < = * " = - - ,,
18.'= ..... G 19.a = * ==~ * - =a= =a = === **==== ei.es us .
- 20.""'*"""=**-- @."'"***-*****'='-- e as I
' '.EB C b .s srv . sam. g %en . om. ggg,e - __ _ =amme .e ammst .n ess. m.a.ums.8 gC CNC I mo - I MOURS I CYES-e . =="*"' =.
===
s
=""****'*""a===' y TJl",",,* *,,* 8' * " *' '* --
- 25. CYES-o. CNO I CYES s
="'=='==='
"'== """ *- *==---== O .,=,.
28.*Ovss -- CNC ..
. _ . - _ We.em. M EAEE
. a_ . - . ==.
Fli.no se one remert .e ast en aevnes,m er itemiutv. eians. PACIPIC GAS & ELECTRIC COMPAMY i
"... fee reeert of innsrv reewres se se mas av en em. te answer or .nsurer av tne cptasser Wiset tus esiveenmass "
as suuSenEB .a any asperary Irgesmesnq OpfWe stb vm saa. Mr. $sfety. Meann & Casms Dost ,,e ossi
% ,,isers h .immeon Aessnes See s.- " " * "'
TsLar.o.es 751 4 11 e -i -- - :- 3171 W Cees. $ semen 6412 8e l.
,1 Report = Date ,19_ l Dr. , l Kindiv give to bearer, Mr.lMs. medical attention, and forward a complete detailed report immedi. stety to Manager, Safety, Health and Claims Dept.,245 Market Street, San Francisco,94106. Your bills should be itemized and all bills and l reports residered in triplicate. PACIFIC GAS AND ELECTRIC COMPANY < Sy usr. - F= aim - swet. bi* I
. . . . . tosv. steen PLEASE COMPLETE AND RET 1JRN TO EMPLOYEE (EMPLOYEE MUST HAVE COMPLETED CARD TO RETURN TO WORK)
Pacific Gas and Electric Co.: Date ,19 _ Mr./Ms. Occupation Report = Employed By l**
- I Division.
Injured at ,T. on ,19 C Retum to full work immediately C Modified work undi C Uneme to work unts C Rosmetions or linwiedene O Return Aoyt. Deam: Time: C Discharged from tremanent Siped MD.
\
F i O ! 7 C O ' C- A S A_NO N ~ Z C 7 7-~ C C C M EAESY i *" :.- ::tAE:.0 Cat.v0 N :C/;E P.aN T-C- v 2 ' 0.1:2 !! . A...a fea:- :r:: :2 9:4:4 * (!:3)333*~25 l l
.. : . 5: .:::r!.II ;
m== sm j I e 'waa ess i Daar Dr. Thank ycu f5r being one of our panel onysicians tha: : ta: cur em:icytes. Our primary g:al is to provida employees who sustain incustrial injurias Your , recuir.ng r.eci:al at.antien wita pr===:, first. class : ta=ent. l assis.ance in : Mis encaavor is 4;creciated. 14hile the nue::er of em icyens ::a: There is an area of c:ncarn :s us. recuire : ta=en: by a ;nysician has remained s.acle er in scue :asas ca:'i::ee, Os ns.::e!- of :sa: ling injuries recuiring time away f-em work, - i . e. , 1:s: time injuries, has eramatically inenasec. We believe that s=me of :nis time away frem work sign: possibly be avoided if :na availacill:y of lign: (medified) duty or desk-type wort were ==re widely known. Some pnysicians have s.atad that in some cases Me patien: will resconc more rapidly in treatnant if kact busy in a light-duty cacacity. P- cuc: ve, lign:-duty assignments are aims: always availa21e for ac::leynes releasac f:r worx wi:nin :na medical restrictions estanlisned by the physician. It our solicy :s have an injured ama' ayes acemmeanied by a sumerviser or Should there be any cues-c:Mer re:resentative on =e first coct:r's visit.
- en accu: :: availacili:y or type sf lign: duty :na: can :e previcac,.se
- or sne will be able to answer for us.
Cur amolayees' welfare is our main concarn. Should you have any cuesticas amour our program, I will be glad to call on you a your c nvenienca. 5incerely, t I r ( R. C. T!+3RN3ERRY ACT:kg: I
Page 1 of 2 PACIF5 GAS AND ELECTRIC COMPANY 3/83 RW9 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05.1 AND 2 y Safety. Health a'nd Claims Personnel to be Contacted for Reporting of Injuries at Diablo Canyon
.. EMPLOYEE INJURIES _
In all cases of serious employee injuries (for example, injuries involvin hospitalization, electric contact, hernia, amputation, fractures, or or death, which occur while on the job, report sh Durina Working Hours: - - PGandE localg T. B. Hor.ey (If Mr. Honey is not available, the person answering the telephone the message and notlTy Mr. Honey or any other parties necessary in the Safety. Health and Claims Department). Any Other Time _: P.eport to one of the persons on the following list, trying each in order until one is contacted: T. B. Honey Pinole
- 1. San Francisco
- 2. A. Thomas San Francisco
- 3. C. B. Powell San Rafael
- 4. P. S. Benitez Oakland i
- 5. T. G. Scott Albany
- 6. L. Lasagna San Francisco
- 7. C. W. Allen Larkspur
- 8. B. L. Wade Danville
- 9. J. A. G1 ;nne Lafayette
- 10. J. C. Vocke San Carlos
- 11. W. A. Hutchison Oakland
- 12. M. C. Dolan.
Walnut Creek !
- 13. M. W. Johnson Richomed
- 14. R. W. Hall Hercules
- 15. I. M. Crawford El Granada
- 16. R. G. Schumaker San Rafael
- 17. R. D. Fagg j Moraga
- 18. P. C. Boettcher Sunnyvale
- 19. H. W. Reynolds Belmont
- 20. B. P. Sadler !
_} I This listing extracted from Safety, Health, and Claims memo 01/13/83.regarding
, Personnel to be Contacted for Reporting of Accidents, dated
.I
)
DC0084 16VIII i . .
Safety. Health and Claims Personnel to beContacted for Reporti Page 2 of 2
-~
Non-Employee Injuries _ I __ C. O. Schrell, San Luis Obispo (office)
,(office) g i(home)
If he cannot be reached, contact one of the following in order of
,4 preference: .
During working hours:
- 1. John C. Echols
- 2. Doug G. Xeeler t, j
- 3. George G. Perry (collection only)'
Af ter working hours on Monday through 8:00 a.m. on Friday, except , ho Pleasant Hill
- 1. John C. Echols . Concord
- 2. Doug G. Keeler
- Layfayette
- 3. John C. Vocke Cupertino
- 4. Amos L. Bechtold Novato /
- 5. William H. Bingaman E. Anthony Giudici San Carlos
- 6. San Ramon
- 7. J. Alex McCorquodale Belmont
- 8. Bruce P. Sadler Hayward
- 9. George G. Perry (collection only ) Fairfield [
j
- 10. Stanley W. Johnston After S:00 p.m. on Fridays to 8:00 a.m. on Mondays and holidays:
He Contact the Investigator delegated to stay on call for all emergencies.If h may be reached through the System Dispatcher. Dispatcher 7J 6 ' t
' OC0084 17VII
- i s .
Nuussa EP R-2 SD(BS.5#5 Pacific Gas and Electric Company ,* REVISION 4 DEPARTMENT OF NUCLEAR Pt. ANT OPERATIONS DATE 7/6/83 l , DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 OF 60 EMERGENCY PROCEDURE TITI.E: RELEASE OF AIRBORNE RADIOACTIVE MATERIALS huf
~
APPROVED: O h 7[ 3 PLANT MANAGER / 0#rE SCOPE This procedure describes the steps to be taken to evaluate and recover from the consequences of an airborne release that results in an unusual Event, Alert, Site Area, or General Emergency. It does not describe the operation of the plant equipment necessary to terminate or minimize the release. This latter subject is covered in the appropriate OP series Emergency Procedure for the particular release mechanism. This procedure and all changes thereto requires PSRC review. SYMPTOMS
- 1. The fcilowing symptoms indicate that an airborne release may be occurring in the Controlled Area:
- a. There is actual or suspected leakage of water, steam, or noncondensible gases from any vessel or piping system containing primary coolant, liquid radwaste, or gaseous racwaste.
- b. Damage occurs to a submerged, irradiated fuel assembly with the resultant release of significant quantities of noncondensible gases.
- c. Alarms occur on CAMS.
- d. A fire occurs in radioactive materials.
- e. G-M type survey instruments in the area begin to show an increasing background count rate.
POTE: The external dose rate produced by airborne levels near MPC is very low and may not be noticed on a Rad Owl. However, it produces a noticeable increase on a G-M survey instrument,
- f. A major radioactive material spill occurs.
J DC0219 11
N R EP R-2 OtABLO CANYON POWER PLANT UNIT NO(S) [ ND 2 DATE 7/6/83 TITLE. RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
- 2. There are numerous indications available in the control room to identify and diagnose a possible airborne release.
~
These vary depending upon the mechanism of the release, and are covered in detail in the OP series Emergency Procedures and EP G-1, " Accident Classification and Emergency Plan Activation." However, the most likely symptom (s) will involve alarms on at least one of the area and/or process radiation monitors. IMMEDIATE ACTIONS
- 1. Personnel in the Area -
- a. Unless qualified and equipped with appropriate monitoring and/or respiratory equipment, evacuate the area and proceed to access control,
- b. Notify the control room.
- 2. The Shift Foreman (interim Site Emergency Coordinator) shall:
- a. Clear the affected area.
This can be done most efficiently by sounding the emergency signal. The emergency signal shall be sounded for the following circumstances:
- 1) Airborne contamination is widespread. Refer to EP R-4, "High External Radiation (In-Plant)."
- 2) Majer damage occurs to plant equipment. Refer to appropriate OP procedure or EP G-1, " Accident Classification and Emergency Plan Activation."
- 3) Site evacuation is necessary. Refer to EP G-5,
" Evacuation of Nonessential Site Personnel."
- 4) Mobilization of personnel is necessary. Refer to EP G-2, " Establishment of the Onsite Emergency Organization" ar:d EP G-4, " Personnel Assembly and Accountability."
- 5) The Shift Foreman deems it necessary,
- b. Establish an appropriate interim onsite emergency organization in accordance with EP G-1, " Accident l
Classification and Emergency Plan Activation." O DC0219 21
~
1 AND 2 N R EP R-2 DIABLQ CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 TITLE. RELEASE OF AIRBORNE RADIDACTIVE MATERIALS
- 1) Assign the Emergency Liaison Coordinator and the
~
Liaison Assistant to beain notification of offsite agencies and plant staff.
- 2) Assign operators to isolate the release using appropriate OP series emergency procedures.
- 3) Have the Emergency Evaluations and Recovery Coordinator (nomally the Shift Engineer) begin preliminary evaluation and classification of the actual or potential severity of the release. Instructions for perfoming this evaluation are contained in the Subsequent Actions section of this procedure.
- c. Treat any injured personnel in accordance with EP R-1,
" Personnel Injury (Radiologically Related) and/or Overexposure."
SUBSEQUENT ACTIONS
- 1. Subsequent Actions Comon to All Events
- a. Establish an appropriate long-term ons'ite emergency organization in accordance with EP G-2, " Establishment of Onsite Emergency Organization." As a minimum, notify the following personnel:
- 1) Plant Manager (Long-Tem Emergency Coordinator)
- 2) Plant Superintendent
- 3) Supervisor of Chemistry and Radiation Protection
- b. Alert offsite groups in accordance with EP G-3,
" Notification of Offsite Organizations."
- 1) Prompt notification of County and other offsite authorities should occur within about 15 minutes for the Unusual Event class and sooner (consistent with the need for other emergency actions) for other classes.
Use Form 69-9221 Emergency Notification Record. l POTE: As a minimum, notify the NRC Operations Center within one hour via the " hot line." This notification is required pursuant to 10CFR50.72 as an event requiring initiation of the licensee's emergency plan or any section of that plan. O DC0219 31
t' NUMBER EP R-2 otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 4 OATE 7/6/83 PAGE 4 OF 60 TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
- 2) Periodic updates on the status of the emergency shall be provided to the County and other offsite
- authorities, at least every 15 minutes. Use Form 69-10262, Emergency Status Fonn, giving as much l information as is known at the time.
- 2. Classify the Emergency
- a. General
- 1) To a large extent, subsequent actions are based upon the potential severity of the occurrence, as identified by the emergency classification. Therefore, the Emergency Evaluations and Recovery Coordinator (EERC) shall inform the Site Emergency Coordinator at the earliest possible time whether the emergency is classified as an Unusual Event, Alert, Site Area or General Emergency using EP G-1, " Accident Classification and Emergency Plan Activation."
t0TE: If core damage is a possibility, the Shift Engineer should be directing his attention towards its assessment and the task of classifying the accident should be assigned to someone else, such as a Senior Control Operator.
- 2) The EERC shall keep the Site Emergency Coordinator apprised of any escalation or reduction of the emergency classification,
- b. How to Make Initial Classification of the Emergency There are four general methods for initially classifying an emergency:
- 1) accident sce'ario,
- 2) estimate release rate,
- 3) use accident sumary sheets, or
- 4) perform offsite monitoring.
Each is discussed below.
- 1) Classify Emergency Based Upon Emergency Scenario DC0219 41
N R EP R-2 0iAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 7/6/83 'l PAGE 5 OF 60 TITLE. RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS The preferred method for initially classifying the emergency is to diagnose the most likely cause (LOCA,
~
steam line break, gas decay tank rupture, etc.) and base the classification on this information, a) Go to the appropriate OP series procedure and use the guidance contained therein to classify the accident. b) If the emergency does not fit any OP series procedure, or if the guidance in the OP series procedure is unclear, go to EP G-1. EP G-1 gives examples of typical emergency scenarios which fall into each accident classification. Classify the emergency at a level consistent with the scenario which most closely approximates the actual situation. c) If multiple emergency situations are occurring simultaneously, such that the probability of a G release of racloactive materials is increased over wnat it would be for a single occurrence, classify the emergency one level higner than it would otherwise nave been based on the most severe single occurrence.
- 2) Classify Emergency Based On Release Rate a) General The second best way to classify the emergency is to estimate the magnitude of the release rate.
However, using release rate infonnation to classify the emergency is subject to the following limitation: (1) If the classification based upon the emergency scenario is more severe than would be warranted by release data, use the conservative (emergency scenario) classification. Tne reason for this is that EP G-1 specifies a classification for many events based upon the potential for a release, and this conservative classification must be used even if the actual release does not materialize. . I I a DC0219 SI
N R EP R-2
- DIABLO CANYON POWER PLANT UNIT NO(G) 1 AND 2 DATE 7/6/83 PAGE 6 OF 60 TITLE- RELEASE OF AIRBORNE RADIOACTIVE MATERIALS l
(2) If the release data indicates a classification more severe than the classification based upon the scenario, use the conservative classification based on release data, if the release data is considered to be reliable. (3) Both whole body and thyroid exposure must be considered when making a classification based upon release data. Classify the emergency based upon the most conservative of these two values. b) Dose and Release Rate Criteria for Classifying Emergency The criteria for classifying an emergency based on dose and release data are sumarized in Appendix 1. I c) Instructions Regardless of the particular instruments used, the O basic technique is as follows: (1) Determine the classification criteria using Appendix 1. Use real meteorological data if possible, or default values as necessary. l (2) Estimate the noble gas and iodine release l rates in curies /second. There are numerous l possible techniques for doing this. Appendix l 2 gives detailed instructions for the following comon methods. (a) Use of plant vent noble gas monitors RE-14 or RE-29. (b) Use of plant vent iodine monitor RE-24. (c) Use of containment air sample results if leak is via containment purge or other path out of containment. (d) Use of RCS coolant sample results during S/G tube rupture. O DC0219 61
1 AND 2 NUMBER EP R-2 DIA8LO CANYON POWER PLANT UNIT NO(S)
~
DATE 7/6/83 TITLE. RELEASE OF AIRBORNE RADIOACTIVE MATERIALS (3) Compare the estimated release rate data with the criteria values.
- 3) Classify Emergency Using Accident Sumary Sheets Appendix 6 contains summary sheets for each accident analyzed in the FSAR. They can be used to estimate the severity of an accident.
- 4) Classify Emergency Based On Field Monitoring Data a) General As discussed in Appendix 1, the accident classification definitions are based upon dose rates at the site boundary. In theory, therefore, field data taken at the site boundary should provide a direct method of classifying the accident. In practice, this is only the third best technique because there is the possibility that you will miss the plume, and also because it takes considerable time to deploy monitoring teams.
b) Instructions Appendix 6 sumarizes the basic fomulas related to environmental monitoring that are useful in classifying accidents and in projecting doses. K)TE: At this point, the emergency is classified. Eo to Steps 3, 4, 5, or 6 for Unusual Event, Alert, Site Area Emergency, or General Emergency, respectively.
- 3. Subsequent Actions for an Unusual Event
- a. Evaluate the internal exposure received by affected personnel using the instructions given in Emergency Procedure R-1, " Personnel Injury (Radiologically Related) and/or Overexposure."
- b. Make the best possible quantification of the extent of any offsite release using the results of air samples, effluent monitors, environmental monitoring, or other techniques.
I Um DC0219 71 i
l NUMBER EP R-2 DIABLO CANYON POWER P'. ANT UNIT NO(S) 1 AND 2 1 REVISION 4 DATE 7/6/83 PAGE 8 OF 60 TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIAL.S
- c. Conduct appropriate cleanup and re-entry operations.
- t0TE: General guidelines for cleanup and re-entry are coiitained in Attachment 1.
- d. Close-out the event with a verbal sumary to offsite agencies and complete the following written reports:
- 1) Plant Problem Report (see Nuclear Plant Administrative Procedure C-12).
- 2) Written suma"y to NRC within 24 hours. .
4 Subsequent Actions for an Alert
- a. Activate the Technical Support Center, the Emergency Operations Facility, and the Operational support Center in accordance with EP's, EF-1, EF-3 and EF-2, respectively.
- b. If the release has the potential for necessitating onsite protective measures (i.e., if it is more than about 10 times the threshold levels for an Alert), make a check of downwind onsite assembly areas to determine if any protective measures are needed for onsite personnel,
- c. If the results of the initial assessment indicate that site personnel are receiving significant exposures, and that evacuation can measurably reduce it, the Site Emergency Coordinator shall order their evacuation either offsite (preferred) or to an upwind site location (if the duration of the release is expected to be very short).
- d. Provide periodic meteorological assessments to offsite authorities and, if any releases are occurring, dose projections for actual releases.
- 1) Activation of EARS is the preferred method for transmitting dose projections offsite.
- 2) If EARS is not available in either the automatic (EARAUT) or manual (EARMAN) mode, perform appropriate hand calculations using Appendices 2 - 6, and Attachment 1 of this procedure.
l e. Perform Comprehensive Follow-up Surveys Onsite DC0219 81
1 N ER EP R-2 DIABLO CANYGN POWER PLANT UNIT NO(S) 1 AND 2 DATE 7/6/83
- i N PAGE 9 OF 60 TITLE
- RELEASE OF AIRBORNE RADIOACTIVE MATERIALS
- 1) Personnel Assembly Areas Although a preliminary assessment should have been made
. at personnel assembly areas, if the release was substantially in excess of limits, it is wise to check or recheck these locations as time and conditions permit, with the following objectivet:
a) To verify that long-tem evacuation is not required if personnel were not previously evacuated based upon the initial assessment. b) To obtain iodine and particulate samples if these were not obtained earlier (assuming that significant quantities of iodine and particulate matter were released, and that the cloud has not long since passed). c) To run smear surveys to see whether decontaminatioa is required. If significant activity is found, the smear pads should be counted on the MCA to assist in determining the isotopes to which persons might have been exposed. (If significant personnel exposure is suspected, the persons should also be whole body counted in accordance with Emergency Procedure R-1.)
- 2) Remainder of Site Downwind areas which may have been contaminated should be checked for contamination to provide data for detemining the necessity and extent of cleanup operations. Smear samples should be retained for subsequent isotopic analysis if required.
- f. Perfom Offsite Monitoring as Warranted If the estimate of curie release and/or onsite monitoring indicates that offsite effects are negligible (as they would be for most Alert conditions), offsite monitoring may not be necessary. However, if there is a realistic possibility that offsite locations may have become contaminated, local government agencies should be alerted and an offsite monitoring program should be instituted for the following purposes:
( DC0219 91 i
NUMSER EP R-2 OtABLO CANYON P. . 4S) 1 AND 2 REVISION 4 DATE 7/6/83 PAGE 10 OF60 TITLE: RELEASE OF AIRBORNE RADIOACTIVE MATERIALS
- 1) Determine the need for long-term decontamination or impoundment of foodstuffs, even if offsite personnel
- evacuation is not required.
ETE: These decisions are the responsibility of local government agencies. However, current governmental recomendations are summarized in EP RB-10.
- 2) Allay any public concern.
- 3) Obtain background data for reports to regulatory agencies.
- g. Conduct appropriate post-accident cleanup and re-entry operations.
- h. Close-out the event with a verbal sumary to offsite agencies and complete the following written reports:
- 1) Plant Problem Report (see Nuclear Plant Administrative Procedure C-12).
- 2) Written summary to NRC within 8 hours.
O
- 5. Subsequent Actions for a Site Area Emergency
- a. Activate the Technical Support Center, thi offsite Emergency Operations Facility and the onsite Operational Support Center in accordance with EP's, EF-1, EF-3, and EF-2, respectively.
- b. Consider evacuation of nonessential site personnel.
l If it is likely that a release is occurring, or will occur which exceeds the threshold for a Site Area Emergency (i.e., 17mR WB or 85 mrem thyroid at site boundary), evacuation of site personnel either offsite (preferred) or to an upwind site location (if the duration of the release is expected to be very short).
- c. Provide periodic meteorological assessments to offsite authorities and, if any releases are occurring, dose projections for actual releases.
- 1) Activation of EARS is.the preferred method for transmitting dose projections offsite.
CLO219 101
1 AND 2 N R EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 PAGE 11 OF60 7,7tg; RELEASE OF AIRBORNE RADIOACTIVE MATERIALS
- 2) If EARS is not available in either the automatic
. (EARAUT) or manual (EARMAN) mode, perform appropriate hand calculations using Appendices 2 - 6, and Attachment 1 of this procedure. ;
l
- d. Perform Offsite Monitoring A Site Area Emergency release is of sufficient magnitude such that some offsite protective measures, such as evacuation of persons in portions of the LPZ, or long-term impoundment of foodstuffs, may be required near the site boundary. Therefore, an offsite monitoring program should be established for the following purposes:
- 1) Initially, the program should be directed toward identifying those areas where personnel evacuation may be necessary to prevent persons from exceeding the recomended evacuation criteria doses of 500 mrem whole body and/or 5 rem thyroid, s 2) Once any imediate evacuation is accomplished, the program should be set up to determine the need for long-term decontamination or impoundment of foodstuffs, which may be desirable even in areas where prompt personnel evacuation was not required.
OTE: These decisions are the responsibility of local government agencies. However, current government recomendations are sumarized in EP RB-10.
- 3) The program should provide background data for any necessary reports to regulatory agencies.
- 4) The program should provide the data to answer questions of public concern.
- e. Take Protective Measures for Members of the Public (if required) l l
l Table 1 sumarizes recomended protective actions for ' exposure to a passing plume. The area where action is taken must include the entire area in which the dose criteria have been exceeded. A somewhat larger area than this should be considered. DC0219 111 l 1 l
o NUMBER EP R-2 DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISION 4 DATE 7/6/83 PAGE 12 OF 60 TITLE RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS If evacuation is required, determine which area is to be evacuated. On a map, draw an arrow pointing in the downwind direction. Mark a 22.5* sector on both sides of this downwind sector. Evacuate everyone within this 67.5* sector out to the limit of the LPZ. NOTE: The decision to evacuate and which area is to be evacuated are the responsibility of local government agencies.
- f. Conduct appropriate post-accident cleanup and re-entry operations.
- g. Close-out the event with a verbal sumary to offsite agencies and complete the following written reports:
- 1) Plant Problem Report (see Nuclear Plant Administrative Procedure C-12).
- 2) Written sumary to NRC within 8 hours.
- 6. Subsequent Actions for a General Emergency
- a. Activate the Technical support Center, the Emergency Operations Facility and the onsite Operational Support Center in accordance with EP's, EF-1, EF-3, and EF-2, respectively,
- b. Evacuate Site Personnel
- 1) As soon as the accident has been classified as a General Emergency, evacuate all nonessential site personnel in a cordance with instructions given in EP G-5.
- 2) Evacuate site personnel engaged in recovery actions if it appears that they will exceed the emergency dose criteria given in EP RB-2.
- c. Evacuate Members of the Public from the Downwind LPZ As soon as the accident has been classified as a General Emergency, notify the Sheriff and recomended imediate evacuation of the LFZ in the downwind direction with the remainder of the ingestion pathway LPZ being placed on DC0219 121
4 NUMBER EP R-2 DiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 4 DATE 7/6/83
!O RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS PAGE 13 op 60 T m.E:
standby alert.1 If it is anticipated that conditions will escalate to a General Emergency, it is not necessary to delay evacuation of the LPZ until confirmed offsite monitoring results are obtained. If evacuation is required, detemine the area which should '1 be evacuated first. On a map, draw an arrow pointing in the downwind direction. Mark a 22.5' sector on either side of this downwind sector. Evacuate everyone within this 67.5* sector out to the limit of the LPZ.
- d. Provide periodic meteorological assessments to offiste authorities and, if any releases are occurring, dose projections for actual releases.
- 1) Activation of EARS is the preferred method for transmitting dose projections offsite.
- 2) If EARS is not available in eithei the automatic (EARAUT) or manual (EARMAN) mode, perfom appropriate hand calculations using appendices 2 - 6, and Attachment 1 of this procedure.
- e. Perform Offsite Monitoring
! 1) General A General Emergency release is of sufficient magnitude i such that some offsite protective measures beyond the LPZ, such as evacuation or long-tem impoundment of l foodstuffs, may be required. Therefore, an offsite I monitoring program should be established for the following purposes: a) Initially, the program should be directed toward identifying those areas located beyond the LPZ where personnel evacuation may be necessary to
'This can be done by souncing the Early Warning System.
I 1 k l DC0219 131
N R R-2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 p DATE 7/6/83 TITLE: RELEASE OF AIRBORNE RADIOACTIVE MATERIALS prevent persons from exceeding the recomended evacuation criteria doses of 500 mrem whole body
. and/or 5 rem thyroid, b) Once any imediate evacuation is accomplished, the program shall be set up to determine the need for long-term decontamination or impoundment of foodstuffs, which might be desirable even in areas where prompt personnel evacuation was not required.
ETE: These decisions are the responsibility of local government agencies. However, current government reccmendations are summarized in EP RB-10. c) The program should provide background data for any necessary reports to regulatory agencies. d) The program should provide the data to answer questions of public concern.
- f. Take Protective Measures Table 1 sumarizes recomended protective actions for exposure to a passing plume. The area where action is taken must include the entire area in which' the dose criteria are exceeded. A somewhat larger area than this should be considered.
OTE: Evacuate at least a 67.5* sector (22.5* on both sides of the downwind sector).
- g. Conduct appropriate post-accident cleanup and reentry operations.
- h. Close-out the event with verbal sumary to offsite agencies and complete the following written reports:
- 1) Plant Problem Report (see Nuclear Plant Administrative Procedure C-12).
l 6 DC0219 141
N ER R-2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 g DATE 7/6/83 PAGE 15OF 60 TITLE. RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS I i
- 2) Written sumary to NRC within 8 hours.
APPENDICES
- 1. Sumary of Criteria for Classifying Emergency Based Upon Dose and Release Data
- 2. Instructions for Estimating Noble Gas Release Rate Using Plant Vent Monitors RE-14 or RE-29
- 3. Instructions for Estimating Iodine Release Rate Using Plant Vent Monitor RE-24
- 4. Use of Containment Air Sample Data to Estimate Release Rate
- 5. Accident Summary Sheets
- 6. Summary of Field Monitoring Formulae that are Useful in Classifying Accidents ATTACHMENTS
~
- 1. Fom 69-11105, "Worksheet for Use of Main Steam Line Monitors, or RCS Coolant Sample Results During S/G Tube Rupture Accidents"
- 2. Fom 69-10262, " Emergency Status Form"
- 3. For 69-9221, " Emergency Notification Record" l
DC0219 15I
l m o TABLE I a g
- E !!
O RECOMMENDED PROTECTIVE ACTIONS TO REDUCE WHOLE BODY AND THYROID DOSE FROM EXPOSURE TO A GASEOUS PLUME {< Projected Dose (rem) to 9 @ the Population Reconsnended Actions (a) Consnents $ g Whole Body - Less than 0.5(b) No planned protective actions (c) . Previously reconenended h protective actions may be - Thyroid - less than 5 Offsite authorities may issue an advisory to seek shelter and await reconsidered or terminated. further instruction. Monitor E S fy environmental radiation levels. E g E 4 Whole Body - 0.5 to 5 Seek shelter as a minimum. If constraints exist to prevent a g Consider evacuation /unless full-scale evacuation, special y a constraints make it impractical. consideration should be given n Thyroid - 5 to 25 for evacuation of children and d Monitor environmental radiation si levels. Control access to pregnant women. affected areas. g g - a " Whole Body - 5 and above Conduct mandatory evacuation. Sheltering is an alternative 17 'O Monitor environmental radiation evacuation can not be promptly E - levels and adjust area for accomplished. G Thyroid - 25 and above mandatory evacuation based on these levels. Control access to affected areas.
-(a) These actions are reconsnended for planning purposes. Protective action decisions at the time of the incident must take existing conditions into consideration (e.g., weather, plume arrival time) . yoaz Mh -
(b) The value of 0.5 rem whole body is based upon guidance from the State of California (see 93 reference 3). muam (c) At the time of the incident, officials may implement low-impact protective actions in keeping oD with the principle of maintaining radiation exposures as low as reasonably achievable (ALARA). ][ O DC0219 161
? e e
N R M DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 'O RELEASE OF AIRBORNE RADIOACTIVE MATERIALS APPENDIX 1
~
SUMMARY
OF CRITERIA FOR CLASSIFYING EMERGENCY BASED UPON DOSE AND RELEASE DATA NOTE 1: For each classification, the actual definition is given from EP G-1. If the necessary information is available, this is the best criteria to use. In addition, however, a set of Derived Criteria are also provided. These are calculated criteria, which are slightly less accurate because of the necessity to make calculational assumptions, but which may be more useful depending on what infomation is readily availabie. POTE 2: In general, derived criteria are expressed in tems of the This site boundary atmosphere dilution factor, (X/d)$00 can be obtained from the meteorological compute . However, if this information is not readily available, default values of the criteria are given using the FSAR design oasis 3 (X/Q)800. = 5.3x10 ' sec/m . NOTE 3: The definitions of terms used in the equations are:
= noble gas relwase rate (Ci/sec)
NG Og = iodine release rate (Ci/sec) QNG = total curies of noble gas released (Ci) Qg = total curies of iodine released (Ci) X g
= iodine concentration (uCi/CC or Ci/m3 )
i (X/0)800 = centerline atmospheric dilution factor @ 800 m l (sec/m3 ) A. UNUSUAL EVENT
- 1. Definition Radiological effluent technical specification limits exceeded.
O kJ DC0219 17I
'l AND 2 EP R-2 N
OIABLO CANYON POWER PLANT UNIT NO(S) 4 DATE
'#" O RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS TITLE APPENDIX 1 (Continued)
. The technical specification limits correspond to site boundary 800 m or 0.5 miles dose rates of:
- a. Whole body 1 0.057 mR/hr.
- b. Thyroid 1 0.170 mrem /hr.
- 2. Derived Criteria
- a. Noble Gas Release Rate NG 1 6.3x107 (X/0)800 Default Value: 0 NG 1 0.0012 Ci/sec ,
- b. Iodine Release Rate y1 9.2x10 ll (Assumed to be I-131)
(X/Q)800 Default Value: y1 1.7x10 7 Ci/sec
- c. Centerline Iodine Concentration 0 800 m X
7 > 9.2x10 ll (Assumed to be I-131) B. ALERT
- 1. Definition Radiological effluents greater than 10 times technical specification limits exceeded.
This corresponds to the following dose rates at the site boundary (800 m or 0.5 miles):
- a. Whole body 1 0.57 mR/hr.
- b. Thyroid 1 1 70 mrem /hr.
9 DC0219 18I
1 AND 2 NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 PAGE 19 OF 60 O RELEASE OF AIRBORNE RADIOACTIVE MATERIALS V APPENDIX 1 (Continued) Derived Criteria
~
2.
- a. Noble Gas Release Rate h1 6.3 10' NG 7 (X/Q)800 Default Value: hg1 y 0.012 Ci/sec
- b. Iodine Release Rate h1 9.2 510 10 y (Assumed to be I-131)
(X/0)3ao Default Value: h1y 1.7x10 6 C1/sec
- c. Centerline Iodine Concentration at 800 m X; 1 9.2x10 10 (Assumed to be I-131)
C. SITE AREA EMERGENCY
- 1. Definition Radiological effluents correspond to greater than 50 mR/hr for 1/2 hour or greater than 500 mR/hr for 2 minutes to the whole body (o'r five times these levels to the thyroid) at the site boundary (800 m).
This can also be interpreted to mean an accident which prtduces a total dose at the site boundary of > 17 mR (whole
~
body) or 1 85 mrem (thyroid).
- 2. Derived Criteria
- a. Peak Noble Gas Release Rate (1 2 minutes duration) hNG 1 5.6x10 3 (X/h)800 Default Value: h NG 1 10.5 Ci/sec Q -
DC0219 191 l l
1 AND 2 Nm P R-2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83
- e PAGE 21 OF 60 RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS 7,
APPENDIX 1 (Continued)
- 2. Derived Criteria
- a. Noble Gas Release Rate 0NG > 0.011 (X/Q 800 Default Value: O NG 1 21 Ci/sec
- b. Iodine Release Rate 03 7 2.7x10~5 (Assumed to be I-131)
(X/Q)800 Default Value: 03 7 0.005 Ci/sec O O DC0219 211
1A 2 N R R-2 DIABLO CANYCN POWER Pt. ANT UNIT NO(S) p DATE 7/6/83 PAGE 2DF 60 7,7 g RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS APPENDIX 2
- INSTRUCTIONS FOR ESTIMATING NOBLE GAS RELEASE RATE USING PLANT VENT MONITORS RE-14 or RE-29 APPLICABILITY First choice if noble gas release is going out of plant vent.
INSTRUCTIONS
- 1. Determine Plant Vent Flow Rate (in efm) on Affected Unit
- a. Check FR-12 on Unit 2 RMS board in control room. If operable, read flow rate directly off of chart.
F = cfm vent
- b. If FR-12 is inoperable, determine the flow rate using the numoer of ventilation fans in operation and the following fan capacities:
FHB exhaust fans @ 35750 cfm/ fan = cfm Aux Bldg exhaust fans @ 73500 dfm/ fan = cfm Cont purge exhaust fans @ 55000 cfm/ fan = cfm Cont H2 purge fan @ 300 cfm/ fan
= cfm Sum F = cfm vent
- 2. Read RE-14 (in control room) if it is on scale. Otherwise, read RE-29 in the package boiler room. Convert the readings to plant vent concentration using Figure 1 (for RE-14) or Figure 2 (for RE-29). Sumarize the data in spaces provided.
TOTE: On Figure 1, assume effective age <1000 hours for all accidents except a fuel handling accident where the fuel has been out of the core for at least a month. l RE-14 RE-24 Time com uCi/cc Time mR/hr. uCi/cc UC0219 221
1 AND 2 N R EP R-2 OtABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83
' PAGE 23OF 60 l s RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS 7g APPENDIX 2 (Continued)
~
- 3. Calculate Noble Gas Release Rate Regardless of the instrument used, the formula for calculating l the noble gas release rate is: l 0NG(Ci/sec) = (uCi/cc Vent x F vent (cfm) x 4.72 x 10' INSTR. TIME (uCi/cc) x (Fvent) x (4.72 x 10 ") = ONG (Ci/sec)
RE- x x (4.72 x 10 2 = RE- x x (4.72 x 10 ") = RE- x x (4.72 x 10 ") = RE- x x (4.72 x 10 ") = RE- x x (4.72 x 10 ") = RE- x x (4.72 x 10 *) = RE- x x (4.72 x 10 ") = RE- x x (4.72 x 10 ") = RE- x x (4.72 x 10 ") = DATE BY l LJ DC0219 23I
1 AND 2 N R EP R-2 o psto CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 PAGE 24Or 60 TITLE APPENDIX 2 (Continued) FIGURE 1 RESPONSE OF PLANT VENT RADIOGAS MONITOR (RE-14) 8 ___ 10 ,
. ./ , . j i I iit
.. 4 i l t flill} I I I ( ll 'il l ) I t/lil i? i l I 'ill i i t i fi .il i I IlI!!ll i I Iili!il Il1ll1111 I I llllill i ViiI!ll i I !Il!!!. ;;
3 w 10~
,/ .,
i f I l I (til l i
- i 16 ill l l ) 8/i8) I I l !Illel [t I lIlilllll l Milllll I l !IliVI l illI!!j I l I iitill l I i 111111 I l l 1 llll j
; Err. Asc ; ,-
1 - . . . . .
. . .. ,10c0 nr . x ..... ,, , i....
., .. i . w .e ni i i n oin vi i tino g i , i nnl 2.
!!Illl l I IIIIIl[l l IIIIII llIll!!I A 3 IIIllOh I'l IIlli!! l ,
\) 10 -
E..
./ , . . ...... .f ' . .M ,rl CO r ;
i i i :n i i i i nit i i i / .il i i ) il::: / i i:iic! 2 i _ y / '
.; 1 '.
_ LM ' i i ii 66nt , . i i l !!! ail i : i s i n't i i ; n u.I I ii;" i i i liittl , l l Ilk!I, 1 IIIll0l l l1I!Il!l I llilllll i 1lll!!! l l llllN> 10 10~2 10" 10-7 10 " 10* ' 10 " Plant Vent Concentration (uC1/cc) DC0219 241
R 1 AND 2 NUMBER EP R-2 DIABLO CANYON POWER Pt. ANT UNIT NO(S) REVISION 4 DATE 7/6/83 8 PAGE 250F 60 7g RELEASE OF AIRBORNE RADIVACTIVE MATERIALS
- APPENDIX 2 (Continued)
_ = := - - = _- : _- . . _ _ _ - - = _ . . - - _ _ . - _ _ 2,m. ---
. _ _- ._g u .. __._;;"
q.._- , . _ e.
=.
4 '
.-=- -
==.___
_ _y
,_=
; s- _-.
~-
n -, g xm x, Mliqv _ -- . _ _ , . _ _ - . _ ,
, , _ q_ y . ,: ;i._- . - -
"... ., w --
-_1__ 1
-r __
- - -o _
-.._-t
.s me. .
=___ - '~-
. 2.__ --- :-.:: .
=
m ,% W.y 1-
, __u -_ ___
_ _ -----7 _
= &-c . ..
-.a n me---.- :____
__' . - - , , :P'., u ww 6 _. . v
- n - __ .
-a, ,,
es. e
=
=
-_. _ ::;. e mid!he=u.n.te.
s m. , g
- _ -w r-- 1 s
.- c -
p - _ _ .%iqp ptg. 3u wagy. i
- ~~-- l' '-~~~~""''".=.;H'~'- - ~; :
t "11':-1 ' =. aE4 w:
% i , mi
. -- .,. t>
.w e
i~w. _ --_:- - _. .. _ . . -. . c
.. ,.+. -
o me .2 . . . _ . , .. ~_ . .. . ._
- ne._--see a_,_--; ' %ist .atu*Js :.F; t a -WJ 1-ti h M4 L!:n Ua
. Ee - . . : :. .- g (J:.:gt,-:_ _ . -.: -=cp::r;:
wg _ _ ~ - - = , ~w.m .=. - :: s. 6
.a_ . .,.,,- y .2 . n-_ -.-. -,
,2 ~
- e
=
Nse __-- s. e c sc v
.c c> _,._
e . :_ o
.e ..
-. c
> t. %w _.._ .
Ew3 - --
- *-- -d teri '
l4 8 I3 D %te r. Pri W i ' O
- +A
. = s
< .D.:.,. 2 - *a
&c- =c m- u.e i .., , , , _ , , , ,
E<.,,,;p g:s ;:s.g:.,::e c e se
-g 1: .
M
- ~
~~
.c I I
!N. . , _.4lll , ci - ^. . . .s - _' ,,
- h. __
- s. .._..
.e. _ _,- . . . _ _ .
....w...= ,
w M c5 3 e.. -
".E =: _n: Ii.
. .J:in ih, .G".:iWFf*II -- o,
J N;bN.e 1
- a -thS -_ ::.xb- - - g: f:.=]-n- =r.,
i
,- l
~.' .I
".~ -- .
a.=.a .== . . , . , . . ". , . . .
.=. - . -
a m ur m..*M W
" 2 .--- .m EeI, mmE.wr.-
v.g .g r. . o _r.:.:_. : ,r-t a t.:.; _. .- :-::t::a . . f.m..= _:b w :.4. o
,,"_- -- -- ~ . - l .
t 2.-
=
_ 1 w
', - - - . = . _ _ . .4 .. , . . _
_.. . . - e, a.
.. =
Wm
,up.P. r ._ e.. wnm n. men < aimen, " ;re i 1 At r 4- -
m t NWP
"~. l'y !E'd5{SEi.;EE:j -
. h 2= l j i ..,, j .
. = g @s- j
,% h lk % g % g *
, 's '
E
.. (J4/Vu) asuodsay JanuoW vessag stoJD 4*N
1 AND 2 s EP R-2 OtABLO CANYON POWER PLANT UNIT NO(S) oArE 7/6/83 PAGE 260F 60 7,7 g RELEASE OF AIRSORNE RADICACTIVE MATERIALS APPENDIX 3
~
INSTRUCTIONS FOR ESTIMATING IODINE RELEASE RATE USING PLANT VENT MONITOR RE-24 APPLICABILITY RE-24' first choice for estimating iodine release rate for minor accidents, where release path is the plant vent. RE-24 will go off scale for any release classed as Site Area Emergency or above, and dose rates may make instrument inaccessible. Under such circumstances, it is best to estimate the release rate by some other method, although a technique is given for estimating high release rates using this instrument. INSTRUCTIONS
- 1. Determine Ratio of Plant Vent Flow Rate to Sampler Flow Rate I
- a. Sampler Flow Rate Read at instrument. Otherwise assume the nonnal setting of I cfm.
F,,,, = cfm
- b. Plant Vent Flow Rate
- 1. Check FR-12 on Unit 2 RMS board in control room. If operable, read flow rate directly off of chart.
F
- C#*
vent
- 2. If FR-21 is inoperable, determine the flow rate using the number of ventilation fans in operation and the following fan capacities:
= cfm FHB exhaust fans @ 35750 cfm/ fan Aux Bldg exhaust fans @ 73500 dfm/ fan = cfm Cont purge exhaust fans @ 55000 cfm/ fan = cfm
= cfm Cont H2 purge fan @ 300 dfm/ fan Sum F " C#*
vent DC0219 26I
1 AND 2 NUMBEn EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 4 DATE 7/6/83 ' PAGE 27CF 60 7,y RELEASE OF AIRBORNE RADIOACTIVE MATERIALS APPENDIX 3 (Continued)
- c. Calculate Flow Rate Ratio FRR = F yent +F samp *
- 2. Obtain Reading On Instrument and Calculate Release Rate
- a. Turn the toggle switch on the front of the instrument to the uCi/sec(x10 1) position.
- b. Turn the SCALE FACTOR switch to the "1000" position. This switch is located insido the door on the lower front part of the instrument. Record the scale factor in the blank in paragraph 2.d. below,
- c. To allow for instrument response time wait at least one (1) minute and then read the chart. Enter this reading in tne blank in paragraph 2.d. below. The chart reading is a number between 1 and 1000. If the instrument does not read on scale, I-131 is not a sion1+icant contribution to tne accioent,
- d. Calculate the release rate using the fonnula 07 (Ci/sec)=(Chart Reading)x(scale Factor)x(FRR)x 10 17 TIME (Readino)x(Factor) x (FRR) x (10~17) ,
= 0; (Ci/sec) 10 1" Y~
y:- TU~ ' . 7-7._ 7 TO T~ j
- 3. Calculating Release Rate If Cartridge is analyzed in the Lab Sor:stimes it is desirable to take the cartridge to the counting room. If so, have the technician report the total uCi of I or I-131 contained on the cartridge.
O DC0219 271 1
1 AND 2 N R EP R-2 DIA81.0 CANYON POWER PLANT UNIT NO(S) l OATE 7/6/83 PAGE 280F 60 737 g RELEASE OF AIRBORNE RADIOACTIVE MATERIALS APPENDIX 3 (Continued) a) Activity on Cartridge (Acart) = u (c kcle I or I-131) b) Estimate the time over which the release has persisted (in seconds). (SEC) atRELEASE = c) Calculate the average release rate using the equation: hg (Ci/sec) = [Acart (uCi)] x (FRR) x 10 6 [atRELEASE(Sec)]
=( )x( ) x 10~6 = C1/sec i
( ) 4 Calculating Release Rate If RE-24 is Inaccessible POTE: This method is very approximate and is an interim tecnnique only,
- a. Take a Radowl or other gamma dose rate measuring instrument and approach RE-24 as close as possible, being careful not to exceed oersonnel exoosure limits.
- b. Get as close to RE-24 as you can and take a Radowl reading (in R/hr) and also estimate the distance (in meters) you are from RE-24.
Oose Rate (OR) = R/hr
= m Distance to RE-24 (d)
- c. Estimate the time over which the release has persisted (in seconds). atRELEASE = sec DC0219 281 l
1 AND 2 ER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 ,\ 1 PAGE 290F 60 7,72 RELEASE OF AIRBORNE RADI0ACTI'.i MATERIALS APPENDIX 3 (Continued)
- d. Calculate the release rate from the equation.
Q; (Ci/sec) = 60 x (DR) x (d)2 x (pap) (#* RELEASE)
= 60 x ( )x( 12 x ( )
( )
= Ci/sec
- 5. Calculating Release Rate If RE-24 is Accessible, But Dose Rates Are Too High To Permit Cartridge To Be Collected
- a. Proceed as in paragraph 4 above, with the following ,
exceptions.
- 1) Open Cartridge holder door and take dose reading on ;
exposed cartridge. Again, estimate distance in meters. DR = R/hr d = m
- b. Calculate the release rate from the ecuation:
07 (C1/sec) = 1.3 x (DR1 x (d)2 x (RR)
\^* RELEASE)
= 1.3 x ( )x( .
32 x ( )
\ )
= Ci/sec W: The reason the equations are cifferent is because there is less shielding when the cartridge is exposed.
O DC0219 291
l I AND 2 NUMSER EP R-2 DiABLO CANYON POWER PLANT UNIT NO(S)' REVISION 4 OATE 7/6/83 7,7tg. RELEASE OF AIRBORNE RADIOACTIVE MATERIALS APPENDIX 4 USE OF CONTAINMENT AIR SAMPLE DATA TO ESTIMATE RELEASE RATE APPLICABILITY Many postulated accidents first result in a release to containment. From there the activity may go to the environment via the containment purge (if it is not isolated), or via some unspecified leak path. If a containment air sample is obtained and the leakage flow rate is know, or can be estimated, the release rate is easily determined. INSTRUCTIONS
- 1. Obtain air sample and analyze for noble gas and/or iodine. The results will be given as concentration, C (in aci/cc), in the containment atmospnere.
TIME AT C WHICH SAMPLE NOBLE GAS IODINE WAS TAKEN (uCi/cc) (uCi/cc)
- 2. Estimate flow rate from containment, Rcont ( n cfm).
NOTE: If there is no obvious leak path, assume containment leaks ! at cesign value of 0.1*/ day, which translates to F cont
- l'8 Cf**
F
- C*
cont
- 3. Calculate Release Rate l
The expression is as follows: 0 (Ci/sec) = C (uCi/cc) x Fcont (cfm) x (4.72 x 10%) DC0219 301
1 AND 2 NUMBER P R-2 DIABLO CANYOP3 POWER PLANT UNIT NO(S) DATE 7/6/83 PAGE 310F 60 9 7,7 g RELEASE OF AIRBORNE RADIOACTIVE MATERIALS APPENDIX 4 (Continued) TIME (CIODINE) x (FCONT) x (4.72 x 10"") = OIODINE (Ci/sec) 4.72 x 10 " 4.72 x 10 - 4.72 x 10 - 4.72 x 10 - 4.72 x 10 - TIME (CNOB GAS) x (FCONT) x (4.72 x 10 ") = ONOB GAS (Ci/sec) 4.72 x 10 " 4.72 x 10 - 4.72 x 10 - 4.72 x 10 - 4.72 x 10 - O DC0219 311
N b2 DIABLO CANYON POWER PLANT UNIT NO(S) p DATE 7/6/83 RELEASE OF AIRBDRNE RADI0 ACTIVE MATERIALS TITLE. APPENDIX 5 l ACCIDENT
SUMMARY
SHEETS This attachment contains sumary sheets for the various postulated accidents which have been analyzed in the FSAR. THese sheets contain both the " design basis" and " expected" case variables which were assumed in the FSAR analyses. The sheets can be used to compare actual measurements with assumed numbers from the FSAR, in order to help evaluate how things are going in relation to predictions, or they can be used as a source of data to supply unavailable numoers in calculations which are performed at the time of the accident-Two sets of data are included. The " design basis" case is expected to be hignly conservative, where every variable is at a worst-care condition. The "expi.cted" case is the best estimated prediction of what mignt actually occur. When FSAR values are used to make calculations or predictions at the time of the accident, the " design ! I basis" values can be used to provide a quick upcer limit result, but as soon as data becomes available which tends to confirm one case or the otner, the one which best agrees with the data should be used. , The accident classifications icentified in this attacnment are based on the activity releases. Other emergency procedures may have different classifications which are based on the initiating event. The summary sheets provided are: A. lA MAJOR LOCA B. 18 MAJOR STEAM LINE BREAK C. 1C MAJOR FEEDWATER LINE BREAK D. 10 BLACKDUT (OR PLANT C00LDOWN WITH ATMOSPHERIC DUMP) E. 1E SMALL LOCA F. 1F TUBE RUPTURE G. 1G LOCKED ROTOR H. 1H FUEL HANDLING ACCIDENT IN FUEL HANDLING BUILDING I. II FUEL HANDLING ACCIDENT IN CDNTAINMENT J. IJ RCD EJECTION ACCIDENT K. 1K GAS DECAY TANK RUPTURE L. IL LIQUID HOLDUP TANK RUPTURE M. 1M VCT RUPTURE I DCU219 321
1 AND 2 NUMBER EP R-2' DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 4 DATE 7/6/83 O 7,7tg. RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS PAGE 330F 60 l
SUMMARY
SHEET 1A
~
MAJOR LOCA FSAR FSAR PARAMETER DBA EXPECTED ACTUAL
- 1. Total Release to Contain-ment Free Volume, Ci
- a. Xe-133 2.03x108 1.36x106
- b. Other Noble Gases 5.73x10s 4.27x105
- c. f-131 2.21x107 1.82x105
- d. Other Iocine 1.90x108 2.73x105
- e. Effective Age of 0 20 Mixture (br)
- f. Release Assumption 100% of core 100% of gap N.G., 25% of N.G., 25% of O core iocines gap iodines
- 2. Containment Scray Effectiveness
- a. Removal half-life 0.022 0.0075 (hrs)
- b. Number of operable 1 2 spray pumps
- 3. Containment Leak Rate 0.1 for 1st 0.05 for 1st
(%/ day) day, 0.05 day, 0.025 after 1st day after 1st day (O DC0219 33I
1 AND 2 NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 4 DATE 7/6/83 RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS Tira
SUMMARY
SHEET 1A (Continued 4 Total Release to Environs, First 2 Hours, Ci
- a. Xe-133 16,840 56
- b. Other Ncble Gases 25,930 21
- c. 1-131 191 0.05
- d. Other Iocine 1,325 0.08
- e. Effective Age of 1 40 Mixture
- f. Release Mechanism Containment Containment
- 5. (x/6) CL (sec/m3 )
- a. 800m (site boundary) 5.29x10'" 5.29x10 5 b, 10000m (6 mi. LPZ) 2.20x20 5 2.20x10 6
- 6. Whole Body Dose Results
- a. Total SCCm cose for 5,600 0.365 1st two hours (mR)
- b. Total 10000m' dose for 567 0.06 l 30 days (mR) t
- 7. Thyroid Dose Results
- a. Total 800m dose for 95,900 1.25 1st two hours (mR)
- 8. Accident Classification General Alert Emergency
- 9. Miscellaneous
- a. Containment-free 7.36x1010 volume cc
- b. RCS Coclant Mass (gm) 2.4x10e DC0219 34I
. 1 1 AND 2 NUMBER P R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
DATE 7/6/83
*O 7,7 g RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS PAGE 35 CF60
SUMMARY
SHEET 1A (Continued
- 9. Miscellaneous
- a. Containment-free 7.36x1010 volume CC
- b. RCS Coolant Mass (gm) 2.4x10s Oi l
DC0219 35I ,
)
i i 1 /.ND 2 eER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 PAGE 360F 60
- RELEASE OF AIRSORNE RADI0 ACTIVE MATERIALS 7,77
SUMMARY
SHEET 1B FAJOR STEAM LINE SREAK FSAR. FSAR DBA EXPECTED ACTUAL _ PARAMETER
- 1. Initial Ccnditions and Assumptions
- a. Primary Coolant Activity (uCi/gm)
- 1) Xe-133 270 67.2
- 2) I-131 2.6 0.65
- 3) Other Iodine 7.9 2.0
- b. Secondary Water .
Activity (uC1/gm)
- 1) I-131 0.015 0.44x10~~
- 2) Other Iodines 0.037 0.90x10~-
- c. Assumed Fuel Defects
(%) 1 0.2
- d. Primary to Secondary Leakage (gpm) 1 0.014
- e. Steam Release, 1st Two Hours (lbs)
- 1) Failed Generator 97,000
- 2) Other generator (atmospheric dump) 520,000 j
- f. Total Steam Release During 8-Hour Cooldown (1bs) 1,600,000 l
- g. Liquid Release Fraction for Iodine i 1) Failed Generator 0.1
- 2) Other generators 0.01 Os DC0219 36I
1 AND 2 NUMBER EP R-2 OtABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 e PAGE 370F 60 7,7g - RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
SUMMARY
SHEET 1B (Continued) FSAR FSAR PARAMETER DBA EXPECTED ACTUAL
- 2. Activity Release to Environs, First 2 Hours (C1)
- a. Xe-133 56.8 0.172
- b. Other Noble Gases 5.2 0.016
- c. 1-131 0.157 0.00045 1
- d. Other Iodines 0.047 0.0013
- e. Effective Age of Mixture (hrs) 65 65
- 3. (x/h) CL (sec/m3 )
- a. 800m (site boundary) 5.29x10 " 5.29x10 5
- b. 10000m (6 mi. LPZ) 2.20x10 $ 2.20x10 6 4 Whole Body Dose Results
- a. Total 800m dose for 1st two hours (mR) 1.8 0.0006
- b. Total 10000m dose for 30 days (mR) 0.03 0.0010
- 5. Thyroid Dose Results
- a. Total 800m dose for 1st two hours (mR) 65 0.012
- b. Total 10000m dose for 30 days (mR) 66 0.012
- 6. Accident Classification Alert Alert
( DC0219 371 1 _. __
i - l 1 AND 2 NUMSER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 4 t DATE 7/6/83 PAGE 380F 60 7,7g RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS l
SUMMARY
SHEET 18 (Continued) FSAR FSAR PARAMETER OBA EXPECTED ACTUAL
- 7. Miscellaneous
- a. Fluid Mass /Stm Gen (lbs)
- 1) Water 95,100
- 2) Steam 6,620
- b. Safety Valve and Steam Dump Valve Capacities (lb/hr/ valve)
- 1) 5.G. safety valve 800,000
- 2) 10% atmospheric dump 380,000
- 3) 35% atmospheric dump 597,000 0
l l l O DC0219 381 l
1 AND 2 NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 4 DATE 7/6/83 PAGE 390F 60 7,g RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
SUMMARY
SHEET 1C MAJOR FEEDWATER LINE BREAK The release from this accident comes from release of steam by safety valves and/or atomospheric steam dump of steam generator water during cooldown if the condenser is not available. The steam generator water is contaminated if there is tube leakage. The feedwater itself which is released has very little activity in it and is ignored. This accident is basically the same as a steam-line break and sumary sheet 98 can be used. Note, however, that the steam release will be through relief . valves and so the iodine liquid release fraction should be 0.01 for' the entire release. This will reduce the thyroid dose somewhat from the steam-line break case.
SUMMARY
SHEET 1D BLACKOUT (PLANT C00LDOWN WITH ATMOSPHERIC DUMP) The release from this accident comes from release of steam by safety valves and/or atmospheric steam dump of steam generator water is contaminated if there is tube leakage. This accident is basically the O same as a steam-line break and sumary sheet 98 can be used. Note, however, that the steam release will be through relief valves and so the iodine liquid release fraction should be 0.01 for the entire release. This will reduce the thyroid dose somewhat from the steam-line break case. l l
)
C l
)
DC0219 391
l
. l 1 AND 2 NUMSER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 4 7/6/83 RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS DATE PAGE 400F 60 g Tir e l
SUMMARY
SHEET 1E SMALL LOCA (RELEASE OF COOLANT TO CONTAINMENT) FSAR FSAR PARAMETER DBA EXPECTED ACTUAL
- 1. Initial Coolant Activity (uCi/gm)
- a. Xe-133 270 45.7
- b. Other Noble Gases 30 5.6
- c. I-131 2.62 0.45
- d. Other Iodine 7.88 1.35
- e. Effective Age of Mixture (hr) 60 60
- f. Fuel Defects (%) 1 0.2
- 2. Initial Release to Containment (Ci)
- a. Xe-133 65,430 16,280
- b. Other Noble Gases 7,950 1,980
- c. 1-131 63 16
- d. Other Iodine 193 48 i
- e. Assumption 100% of Coolant 100% of Coolant
- N.G. activity N.G. Activity
+10% of coolant +10% of coolant iodines iodines
- 3. Containment Spray Effectiveness
- a. Removal Half-life (hrs) 0.022 0.0075 l
S OCO219 401
1 AND 2 NUMBER EP R-2 DiAsLO CANYON POWER PLANT UNIT NO(S) REVISION 4 DATE 7/6/83
' PAGE 410F 60 7,7g RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
SUMMARY
SHEET 1E (Continued) FSAR FSAR PARAMETER DBA EXPECTED ACTUAL
- b. Number of operable spray pumps 1 2
- c. Containment Leak Rate
(%/ day) 0.1 for 1st 0.05 for 1st day, 0.05 day, 0.025 after 1st after 1st day day . 4. Containment Leak Rate (%/ day) 0.1 0.05 ! 5. (x/h) CL (sec/m3 )
- a. 800m (site boundary) 5.29x10 " 5.29x10 $
j b. 10000m (6 mi. LPZ) 2.20x10 5 2.20x10 6
- 6. Whole Body Dose Results
- a. Total 800m dose for 0.004
- ist two hours (mR) 0.18
- b. Total 10000m dose for 30 days (mR) 0.05 0.001
- 7. Thyroid Dose Results
- a. Total 800m dose for 5 1
1st two hours (mR) 0.2 0.0009
- b. Total 10000m dose for 30 days (mR) 0.03 0.0001 l '
- 8. Accident Classification Alert Alert i
. l DC0219 411
N R R-2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83
^
RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS 7,7
SUMMARY
SHEET IE (Continued) FSAR FSAR PARAMETER DBA EXPECTED ACTUAL
- 9. Miscellaneous
- a. Containment-Free Volume (cc) 7.36x1010
- b. RCS Coolant Mass (gm) 2.4x108
- c. Liquid Release Fraction for Iodine 0.1 9
g DC0219 42I
1 AND 2 NUMBER EP R-2 OtABLO CANYON POWER PLANT UNIT NO(S) REVISION 4 DATE 7/6/83 ' RELEASE OF AIRBORNE RADIDACTIVE MATERIALS 7e
SUMMARY
SHEET IF j TUBE RUPTURE l FSAR FSAR PARAMETER DBA EXPECTED ACTUAL
- 1. Initial Conditions and Assumptions
- a. Primary Coolant Activity (uCi/gm)
- 1) Xe-133 270 67.2
- 2) 1-131 2.6 0.65
- 3) Other Iodine 7.9 2.0
- b. Secondary Water l Activity (vCi/gm) l
- 1) 1-131 0.015 0.44x10 "
- 2) Other Iodines 0.037 0.90x10 "
O c. Assumed Fuel Defects (*.) 1 0.2 l
- d. Primary to Secondary Leakage (gpm) 1 0.014
- e. Steam Release, 1st Two Hours (lbs)
- 1) Failed generator 31,000
- 2) Other generators (atmospheric dump) 380,000
- f. Total Steam Release Ouring 8 hour Cooldown (lbs) _
1,600,000
- g. Liquid Release Fraction for Iodine
- 1) Failed generator 0.01
- 2) Other generators 0.01 DC0219 43I
1 AND 2 NUM8En EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 4 DATE 7/6/83 PAGE 440F 60 7,77 RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
SUMMARY
SHEET IF (Continued) FSAR FSAR PARAMETER DBA EXPECTED ACTUAL
- 2. Total Release to Environs First 2 hours (Ci)
- a. Xe-133 10,980 2,383
- b. Otner Noble Gases 1,067 234
- c. 1-131 0.75 0.14
- d. Other Iodines 3.1 0.62
- e. Effective Age of Mixture (hrs) 65 65
- 3. (x/h) CL (sec/m3 )
- a. 800 m (site boundary) 5.29x10 " 5.29x10 5
- b. 10000m (6 mi. LPZ) 2.20x10 5 2.20x10 6
- 4. Whole Body Dose Results
- a. Total 800m dose for 1st two hours (mR) 360 7.7
- b. Total 10000m dose for 30 days (mR) 15 0.3
- 5. Thyroid Dose Results
- a. Total 800m dose for 1st two hours (mR) 340 4.3
- b. Total 10000m dose for 30 days (mR) 15 0.2
- 6. Accident Classification Alert Alert 1
DC0219 441 i
1 AND 2 NUMSER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 4 DATE 7/6/83
*O 7,7 g RELEASE OF AIRBORNE RADIOACTIVE MATERIALS
SUMMARY
SHEET IF (Continued) FSAR FSAR PARAMETER DBA EXPECTED ACTUAL
- 7. Miscellaneous
- a. Fluid Mass / Stem Gen.
(lbs)
- 1) Water 95,000
- 2) Steam 6,620
- b. Safety Valve and Steam Dump Valve Capacities (lbs/hr/ valve)
- 1) S.G. safety valve 800,000
- 2) 10% atmospheric dump 380,000
- 3) 35% atmospheric dump 597,000 O
O DC0219 451 f l
1 AND 2 NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 4 DATE 7/6/83
- PAGE 4.60F 60 7,7g RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
SUMMARY
SHEET 1G LOCKED ROTOR ACCIDENT FSAR FSAR PARAMETER DBA EXPECTED ACTUAL
- 1. Total Release to Environs, 1st Two Hours (Ci)
- a. Xe-133 97 0.73
- b. Other Noble Gases 19.6 0.21
- c. I-131 0.24 0.003 l d. Other lodines 0.36 0.003
( e. Effective Age of Mixture 50 50
- f. Assumptions
- 1) Coolant Activity 1% fuel defects 0.2% fuel defects
+3% of gap +3% of gap activity activity
- 2) Primary to Secondary Leakage (gpm) 1 0.014
- 3) Secondary Steam Release, 1st Two Hours (lbs) 617,000 617,000 l
- 4) Total Steam i
Release During 8 Hour Cooldown (lbs) 1,600,000 1,600,000
- 2. (x/6)CL(sec/m) 3
- a. 800m (site boundary) 5.29x10~ 5.29x10~5
- b. 1000m (6 mi. LPZ) 2.20x10 5 2.20x10~$
I DC0219 461
l 1 AND 2 NMR EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 PAGE 470F 60 O TITLE. RELEASE OF AIRBORNE RADIOACTIVE MATERIALS
SUMMARY
SHEET IG (Continued) FSAR FSAR PARAMETER DBA EXPECTED ACTUAL ,
- 3. Whole Body Dose Results
- a. Total 800m dose for 1st two hours (mR) 4.4 0.004
- b. Total 10000m dose for 30 days (mR) 0.5 0.0004
- 4. Thyroid Dose Results
- a. Total 800m dose for 1st two hours (mR) 82 0.06
- b. Total 10000m dose for 30 days (mR) 27 0.02 i'
- 5. Accident Classification Alert Alert
- 6. Miscellaneous
- a. Fluid Mass /Stm Gen.
(1bs)
- 1) Water 95,100
- 2) Steam 6,620
- b. Safety Valve and Steam Dump Valve Capacity (lbs/hr/ valve) 800,000
- 1) 5.G. safety valve
- 2) 10% atmospheric dump 380,000
- 3) 35% atmospheric dump 597,000
- c. Liquid Release Fraction for lodines 0.01 O
DC0219 471
1 AND 2 NUMBER EP R-2 DiABLO CANYON POWER PLANT UNIT NO(S) REVISION 4 DATE 7/6/83 PAGE 480F 60 RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS TITLE.
SUMMARY
SHEET 1H FUEL HANDLING ACCIDENT IN FUEL HANDLING BLDG FSAR FSAR PARAMETER DBA EXPECTED ACTUAL
- 1. Initial Conditions
- a. Radial Peaking Factor of Damaged Assembly 1.65 1.26
- b. Elapsed Time Since Reactor Shutdown (hrs) 100 100
- c. Type of Release to Pool 100% of assembly 100% of assembly gap activity gap activity f
1
- d. Bundle Submergence (ft) 26 26
- e. Pool Decontamination Factor for Iodine 100 760
- f. Total Assembly Gap Activity at Time of Accident
- 1) Xe-133 100,000 8,137
- 2) Other Noble Gases 4,500 1,500
! 3) I-131 52,670 5,282
- 4) Other lodines 7,000 220 l
- 5) Effective Age of Mixture (br) 600 600
- 2. (x/6) CL (sec/m3 )
- a. 800m (site boundary) 5.29x10 5.29x10 5
- b. 1000m (6 mi. LPZ) 2.20x10 $ 2.20x10 6
- 3. Total Release to Environs, 1st Two Hours (C1)
- a. Xe-133 100,400 523
- b. Other Noble Gases 4,100 101 0
DC0219 481
1 AND 2 N R EP R-2 OlABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 O (/ RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
-PAGE 490F 60 7,7 g
~
SUMMARY
SHEET IH (Continued) FUEL HANDLING ACCIDENT IN FUEL HANDLING BLOG FSAR FSAR l PARAMETER DBA EXPECTED ACTUAL
- c. I-131 80 0.005
- d. Other Iodines 10 0.0002
- e. Effective Age of Mixture (hrs) 600 600
- 4. Whole Body Dose Results
- a. Total 800m dose for 1st two hours (mR) 2,450 - 1. 5
- b. Total 10000m dose for 30 days (mR) 102 0.06
- 5. Thyroid Dose Results
- a. Total 800m dose for 1st two hours (mR) 22,200 0.08
- b. Total 10000m dose '
for 30 days (mR) 923 0.003
- 6. Accident Classification Site Emergency Alert
- 7. Miscellaneous
- a. Fuel Handling Building Volume (ft3 ) 435,000 b.
Fuel ExhaustHandling (Building Rate cfm) 35,700 35,700
- c. Filter Cleanup Factor 0.10 0.01 4
D DC0219 491 l
~ ~-
1 AND 2 NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 PAGE 500F 60 RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS Tir a
SUMMARY
SHEET II FUEL HANDLThG ACCIDENT IN CONTAINMENT _ FSAR FSAR PARAMETER DBA EXPECTED ACTUAL
- 1. Initial Conditions
- a. Radial Peaking Factor of Damaged Assembly 1.65 1.26
- b. Elapsed Time Since Reactor Shutdown (hrs) 100 100 l c. Type of Release to 100% of assembly 100% of assembly Pool gap activity gap activity
- d. Bundle Submergence (ft) 26 26
- e. Pool Decontamination Factor for lodine 100 760
- f. Total Assembly Gap Activity at Time of Accident (Ci)
- 1) Xe133 100,000 8,137
- 2) Other Noble Gases 4,500 1,500
- 3) 1-131 52,670 5,282
- 4) Other Iodines 7,000 220
- 5) Effective Age of Mixture (hrs) 600 600
- 2. (x/ ) CL (sec/m3 )
- a. 800m (site boundary) 5.29x10 " 5.29x10 5
- b. 1000m (6 mi. LPZ) 2.20x10 s 2.20x10-)
- 3. Total Release to Environs, 1st Two Hours (Ci)
- a. Xe-133 12,460 38 DC0219 501
1 AND 2 NUMBER EP R-2 DIABLO CANYON POWG PLANT UNIT NO(S) DATE 7/6/83 PAGE 510F 60
- s. 7ggg; RELEASE OF AIRBORNE RADIOACTIVE MATERIALS
SUMMARY
SHEET II (Continued)
- FUEL HANDLING ACCIDENT IN CONTAINMENT FSAR FSAR PARAMETER DBA EXPECTED ACTUAL 557 7
- b. Other Noble Gases
- c. 1-131 65 0.033
- d. Other Iodines 8.7 0.0013 l e. Effective Age of Mixture (hrs) 600 600
- 4. Whole Body Dose Results
- a. Total 800m dose for 1st two hours (mR) 0.31 0.0001 s b. Total 10000m dose for 30 days (mR) 0.013 4x10 6
- 5. Thyroid Dose Results
- a. Total 800 m dose for 1st two hours (mR) 18.4 6x10~"
- b. Total 10000m dose for 30 days (mR) 0.76 3x10 5
- 6. Accident Classification Site Emergency Alert
- 7. Miscellaneous Activity Release Mechanism Activity released from cavity to containment atmosphere is confined directly above the cavity water level. It is picked up by the fan coolers and sent out through the containment purge.
O id DC0219 511 e
1 AND 2 NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 l PAGE 52OF 60 RELEASE OF AIRBORNE RADIOACTIVE MATERIALS y7g
SUMMARY
SHEET IJ R00 EJECTIDN ACCIDENT FSAR FSAR PARAMETER DBA EXPECTED ACTUAL
- 1. Total Release to Containment Free Volume (Ci)
- a. Xe-133 2.01x105 1.52x105
- b. Other Noble Gases 6.82x10" 6.22x10"
- c. 1-131 7.32x103 7.28x103
- d. Other Iodine 1.11x10" 1.09x10"
- e. Effective Age of Mixture (hrs) 40 40
- f. Release Assumption Coolant activity Coolant activity
\ (1% defects) (0.2% defects) plus 10% of core plus 10% of core gap activity gap activity times a liquid times a liquid release fraction release fraction of either 0.1 of either 0.1 (for I) or 1.0 (for I) or 1.0 (forN.G.) (for N.G.)
- 2. Containment Spray Effectiveness
- a. Removal half-life 0.022 0.0075 (hrs)
- b. Number of operable spray pumps 1 2
- 3. Containment Leak Rate
(%/ day) 0.1 0.05 4 (x/0) CL (sec/m3 )
- a. 800m (site boundary) 5.29x10~" 5.29x10 5
- b. 1000m (6 mi. LPZ) 2.20x10-) 2.20x10 s 1
i DC0219 521 l
1 AND 2 N R EP R-2 oiAsLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 PAGE 530F 60 7g RELEASE OF AIRBORNE RADIOACTIVE MATERIALS
SUMMARY
SHEET IJ (Continued) ROD EJECTION ACCIDENT FSAR FSAR PARAMETER DBA EXPECTED ACTUAL
- 5. Total Release to Environs, 1st 2 Hours (Ci)
- a. Xe-133 11.2 5.6
- b. Other Noble Gases 4.1 2.0
- c. 1-131 0.0098 0.002
- d. Other Iodine 0.015 0.002
- e. Effective Age of Mixture (hrs) 40 40 Release Mechanism Containment Containment O f.
Leakage Leakage
- 6. Whole Body Dose Results
- a. Total 800m dose for 1st two hours (mR) 0.73 0.04
- b. Total 1000m dose for 30 days (mR) 0.13 0.006
- 7. Thyroid Dose Results
- a. Total 800m dose for 1st two hours (mR) 3.3 0.04
- b. Total 10000m dose for 30 days (mR) 0.14 0.002
- 8. Accident Classification Alert Alert
- 9. Miscellaneous
- a. Containment free volume (cc) 7.36x1010
- b. RCS Coolant Mass (gm) 2.4x108 DC0219 531
\
DIABLO CANYON POWER Pt. ANT UNIT NO(S) DATE 7/6/83 PAGE 54Op 60 RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS TITLE: SUFNARY SHEET IK_ GAS DECAY TANK RUPTURE FSAR FSAR DBA EXPECTED ACTUAL PARAMETER
- 1. Total Release to Environs, 1st Two Hours (Ci)
- a. Xe-133 65,400 16,300
- b. Other Noble Gases 7,300 2,140
- 2. (x/ ) CL (sec/m3 )
- a. 800m (site boundary) 5.29x10 ' 5.29x10 5
- b. 10000m (6 mi. LPZ) 2.20x10 5 2.20x10 5
- 3. Whole Body Dose Results 4 a. Total 800m dose for 1st two hours (mR) 2,010 44
- b. Total 10000m dose for 30 days (mR) 84 2
- 4. Accident Classificaticn Site Emergency Alert
- 6. Miscellaneous
- a. Tank Volume (cc) 2.18x10 7
- b. Tank Press 100 psi
- c. Volume Released (cc) 1.48x10ecc Gi l
OC0219 54I l
=
1 AND 2 N R EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 O 7,7g RELEASE OF AIRBORNE RADIOACTIVE MATERIALS PAGE 55oF 60
SUMMARY
SHEET IL LIOUID HOLDUP TANK RUPTURE I FSAR FSAR PARAMETER DBA EXPECTED ACTUAL
- 1. Activity in Holdup Tank (C1)
- a. Xe-133 51,000 10,200
- b. Other Noble Gases 4,710 930
- c. 1-131 492 98.3
- d. Other Iodines 1,086 217
- e. Effective Age of Mixture (hrs) 60 60
- 2. Cleanup Parameters
- a. Liquid Release Fraction for lodines from Tank to Auxiliary Building Atmosphere 10~" 10~"
- b. Charcoal Filter Cleanup Factor 0.1 0.01
- c. Release Duration (hrs) 2 2
- 3. Activity Release to Environs, 1st Two Hours (C1)
- a. Xe-133 51,000 10,200
- b. Other Noble Gases 4,710 930
- c. 1-131 0.00492 0.0098
- d. Other Iodines 0.01086 0.00217
- 4. (x/0)CL(sec/m3)
- a. 800m (site boundary) 5.29x10~" 5.29x10 s
'( b. 1000m (6 mi. LPZ) 2.20x10~5 2.20x10~$
DC0219 551
- - - - - - - - -e
1 AND 2 N M DiABLO CANYON POWER Pt. ANT UNIT NO(S) p _ DATE 7/6/83
. PAGE 560F 60 7,7 RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
SUMMARY
SHEET IL (Continued) LIQUID HOLDUP TANK RUPTURE FSAR FSAR PARAMETER DBA EXPECTED ACTUAL
- 5. Whole Body Dose Results
- a. Total 800m dose for 1st two hours (mR) 1.440 37
- b. Total 10000m dose for 30 days (mR) 60 1.6
- 6. Thyroid Dose Results
- a. Total 800m dose for 1st two hours (mR) 1.93 0.003
- b. Total 10000m dose for 30 days (mR) 0.08 0.0001
- 7. Accident Classification Site Emergency Alert
- 8. Miscellaneous
- a. Tank Volume (cc) 3.03x10s l
O l DC0219 561 1
1 AND 2 NUM6En EP R-2 otAsLO CANYON POWER PLANT UNIT NO(S) REVISION 4 DATE 7/6/83 PAGE 570F 60 O 7,7tg. RELEASE OF AIRBORNE RADIOACTIVE MATERIALS
SUMMARY
SHEET IM VOLUME CONTROL TANK RUPTURE FSAR FSAR PARAMETER DBA EXPECTED ACTUAL .
- 1. Activity in VCT (Ci)
- a. Xe-133 3,330 828
- b. Other Noble Gases 198 42 ,
- c. 1-131 12.1 3.0
- d. Other Iodines 35 8.7
- e. Effective Age of Mixture (hrs) 60 60
- 2. Cleanup Parameters O a. Liquid Release Fraction for Iodines frem Tank to Auxiliary Building Atmosphere 10 " 10 6
- b. Charcoal Filter Cleanup Factor 0.1 0.01 -
- c. Release Duration (hrs) 2 2
- 3. Activity Release to Environs, 1st Two Hours (C1)
- a. Xe-133 3,230 828
- b. Other Noble Gases 198 42
- c. I-131 0.00012 0.000003
~
- d. Other Iodines 0.00035 0.00009 3
- 4. (x/Q)CL(sec/m)
- a. 800m (site boundary) 5.29x10~" 5.29x10~5
- b. 1000m (6 mi. LPZ) 2.20x10~5 2.20x10 5 0C0219 571
1 AND 2 N R EP R-2 DIABLO CAFYON POWER PLANT UNIT NO(S) DATE 7/6/83 PAGE 580F 60 RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS rit u
SUMMARY
SHEET IM (Continued) VOLUME CONTROL TANK RUPTURE FSAR FSAR DBA EXPECTED ACTUAL PARAMETER
- 4. (x/ ) CL (sec/m3 )
800m (site boundary) 5.29x10'" 5.29x10~5 a. 1000m (5 mi, LPZ) 2.20x10~5 2.20x10~5 b.
- 5. Whole Body Dose Results
- a. Total 800m dose for 1st two hours (mR) 465 9.3
- b. Total 10000m dose for 30 days (mR) 19 0.4
- 6. Thyroid Dose Results
- a. Total 800m dose for 1st two hours (mR) 0.03 0.00004
- b. Total 10000m dose for 30 days (mR) 0.001 0.000001
- 7. Accident Classification Site Emergency Alert
- 8. Miscellaneous
- a. Tank Volume (cc) 1.1x10 7 i
i
1 AND 2 N EP R-2 g DIA8LO CANYON POWEA PLANT UNIT NO(S) om 7/6/83 PAGE OF N l RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS ' vf) TITLE. APPENDIX 6
SUMMARY
OF FIELD MONITORING FORMULAE THAT ARE USEFUL IN CLASSIFYING ACCIDENTS
- 1. Relationship Between Whole Body Dose Rate an'd Noble Gas Release Rate If a whole body dose rate measurement is taken in the environment, it can be related to the release rate using the equation:
DR yg,g
=
9 x 10$ xEyx0NGx(X/6)g Where: DR = Whole body dose rate at location L WB'L (mR/hr.) Ey = average gamma energy (mev) (default value - 0.1 mev) D NG
= noble gas release rate (Ci/sec)
(X/0)L dilution factor at downwind location L
=
f0TE: This equation can also be used to calculate downwind dose rate IT'the release rate is known.
- 2. Relationship Between Thyroid Dose Rate and Iodine Concentration Assuming all iodine is I-131:
DR THY,L
= 1.85 x 106 [X133]L Where: DR THY,L = Thyroid dose rate at location L (Rem /hr).
= I-131 Concentration at Location L (pCi/cc
[X131)L or Ci/m3 )
- 3. Relationship Between Thyroid Dose Rate and Iodine Release ' Rate-Assuming all iodine is I-131:
DR THf,L = (1.85x106)(0)(X/0)g g (OG DC0219 591
1 AND 2-DIABLO CANYON POWER PLANT UNIT NO(S) RE DATE PAGE 7/6/83 600F 60 h 97g RELEASE OF AIR 8ORNE RADI0 ACTIVE MATERIALS APPENDIX 6 (Continued)
~
Where: DR = Thyroid dose rate at location L M 'l (Rem /hr). Og = iodine release rate (C1/sec) 3 (X/0)g = dilution factor at location L (sec/m )
- 4. Extrapolation of Dose Rates, Doses or Concentrations to Other Locations If a dose or dose rate value is available at one location in the environment, it may be extrapolated to another location if the respective (X/ ) values are known.
(X/h)A(DR)B (DR)A (X/Q)B or (D)A IX/ )A (D)B (X/0)B or (X/0)A XB
^
(X/0)B Where: DR = dose rate (uR/hr, mR/hr, R/hr) D = dose (uR, mR, R) X = concentration (uci/cc or Ci/m3) l A,B = locations A and B Os OCO219 601
69-11105 7/83 (50) Page 1 of 8 PACIFIC GAS AND ELECTRIC COMPANY
. DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 I
TITLE: WORKSHEET FOR USE OF MAIN STEAM LINE MONITORS, OR RCS COOLANT SAMPLE RESULTS DURING S/G TUBE RUPTURE ACCIDENT ATTACHMENT 1 PERFORMED BY DATE TIME APPLICABILITY One of the most difficult accidents to estimate the release rate for is a S/G Tube Rupture. This is due to uncertainties in primary to secondary leak rate and in steam release rate to the atmosphere. The release pathway for a secondary system release will largely depend on identifying the affected Steam Generator and whetner or not it's associated Main Steam Isolation Valve (MSIV) has been closed. When the MSIV is open and the condenser is used as the principal heat sink, the condenser air ejectors release via the Plant Vent, which is a monitored release point. If the Condenser is unavailable or if the MSIV is closed, steam flow from the affected Steam Generator should be assumed to be releasec via atmospheric steam dumps. The instantaneous release rate (Q) may be calculated below using the radioactivity concentration of the primary or secondary system. INSTRUCTIONS
- 1. Determine the effluent stream concentration, C(pCi/cc) by one of the two following methods:
1 1.A. Main Steam Line Monitors (RE-71, 72, 73 & 74). This is the preferred metnoc, Dut it is poss1 Die that radioactivity levels in secondary system steam (or water if the steam-line is flooded) may be too low for Monitors RE 74 to come on-scale. Otherwise, enter appropriate data below and perform the indicated calculations: TIME Main Steam Line Monitor Channel
- BY RE-71 RE-72 RE-73 RE-74 (1) Reading (CPM)
(2) Total Conc (CTotal) From Figure A**
- NOTE: Re-71 corresponds to Steam Generator (S/G) number 1. RE-72 to S/G-2, RE-73 to S/G-3, and RE-74 to S/G-4
**Use emergency (Initial Release Curve) values.
O OCO203 11
Page 2 of 8 69-11105 7/83 (50) TITLE: WORKSHEET FOR USE OF MAIN STEAM LINE MONITORS, OR RCS COOLANT SAMPLE RESULTS DURING 5/G TUBE RUPTURE ACCIDENT ATTACHNENT 1 To calculate the fraction of total steam line activity attributable to Noble Gases, Iodines, and Particulates, some assumptions and calculations have to be performed. If the FSAR design basis steam generator tube rupture is assumed, then the fraction . of the total activity in the steam line can be broken dowr as follows: x 0.9990(Figg) CNOB GAS
- TOTAL
=C TOTAL x 0.000195(F17) - DEFART VALUES C
IODINE C =C TOTAL x 0.000005(FI PART I PART However, these fractions should be adjusted based on reactor coolant sample analyses, and partitioning factors. To accomplish this, first determine the relative concentrations of noble gases, iodines, and particulates in the reactor coolant as described below: Calculate Fractional Reactor Coolant Activity F gg = (Total Noble Gas Activity of Reactor Coolant) = (Total Reactor Coolant Activ1ty)
=
Fg = (Total Iodine Activity of Reactor Coolant) (Total Reactor Coolant Activity) _ F PART=(TotalParticulateActivityofReactorCoolant]= (Tctal Reactor Coolant Act1vity) Calculate Fractional Steam-line Activity FI = NG[NG) NG L(F3g)(PF NG) + (Fg )(PFg ) + (FPART)(PFPARTIl (Fg )(PF;) F1 g= I3 L(FNG)(PFNG)
- Yi I I*I PART)lEEPART F1 = ( PART)(PFPART)
PART ((FNG)(PF NG) ' Y )(PF I )g+(FPART IkPfPART3 I OCO203 21
j ,..- 69-11105 7/83 (50) Page 3 of 8 TITLE: WORKSHEET FOR USE OF MAIN STEAM LINE MONITORS, OR RCS COOLANT SAMPLE RESULTS DURING S/G TUBE RUPTURE ACCIDENT
,( -
ATTACHMENT 1 VALUES OF STEAM GENERATOR PF (PARTIONING FACTOR) Steam Generator Water Level l Radionuclide Group Empty Nonnal Flooded Noble Gases (PFgg) 1.0 1.0 1.0 Iodines (PFg ) 0.1 0.01 1.0 0.01 0.01 1.0 Particulates (PFPART) Calculate Steam-line Concentration x FI " CNOB GAS = CTOTAL NG " C =CTOTAL x Fl y = uCi IODINE " O CPARTICULATES = CTOTAL PART = x F1 u l Proceed to Section 2. 1.B. Steam line activity can be estimated using an analysis of reactor coolant activity. This method is not as preferable as using RE-71, 72, 73, or 74, but it can provide a conservative methodology for calculating steam line concentration. f ' Calculate Fractional Reactor Coolant Activity
=
F,g = (Total Noble Gas Activity of Reactor Coolant) (Total Reactor Coolant Activity) F = (Total Iodine Activity of Reactor Coolant =- I (Total Reactor Coolant Activity)
=
FPART = (Total Particulate Activity of Reactor Coolant) l (Total Reactor Coolant Activity) O W DC0203 31 l
Page 4 of 8 69-11105 7/83 (50) TITLE: WORKSHEET FOR USE OF MAIN STEAM LINE MONITORS, OR RCS COOLANT SAMPLE . . RESULTS OURING S/G TUBE RUPTURE ACCIDENT 9, ATTACHMENT 1 Calculate Fractional Steam-Line Activity FI , = ( NG)( NG) l3 llfNG)(PFNG}
- I I II I I*I PART II PART N
Fi g = (F;)(PFy ) IJ ((FNG)(PFNG)
- l I ll I l * (f9 ART)(PFPART FI RU(bART)
PART = L(F NG MPF gg) + (F )(PF g )y + (FPART)lffPART Id PF Values are the same as providea in section 1A. Calculate Steam-Line Concentration (Use if Steam Generator is not flooded) x 0.056* = uCi C N08 GAS = (Total reactor coolant activity) x FI NG CC
= (Total reactor coolant activity) x F1; x 0.056* = uti C CC IODINES x 0.056* = uCi C PARTICULATES = (Total reactor coolant activity) x FI PART CC Calculate Steam-Line Concentration (Use if Steam-Generator h flooded)
= pCi C NOB GAS = (Total reactor coolant activity) x FI NG CC
= uCi C IODINES = (Total reactor coolant activity) x' F1 g CC
= uCi C PARTICULATES = (Total reactor coolant activity) x F1PART CC
- 2. Once the radioactive steam or water concentration is detennined in the steam-line using either section 1A or IB, the release rate from the affected steam generator can be calculated in three different ways. They are cescribed in this section. If the steam generator is flooded (solid) proceed directly to section 2C.
- Factor to account for density differences between steam and water, at approximately 558'F and 1115 (psia). This corresponds to the highest lift setpoint for the safety valves. This value will overestimate the concentration of radioactive material in steam for any lower pressure and temperature.
G DC0203 di
Page 5 of 8
. 69-11105 7/83 (50)
TITLE: WORKSHEET FOR USE OF MAIN STEAM LINE MONITORS, OR RCS COOLANT SAMPLE RESULTS DURING $/G TUBE RUPTURE ACCIDENT O ATTACHMENT 1 2A. Steam Flow Rate Monitors Each steam line at DCPP has a flow rate monitor which is capable of
- providing steam flow in pounds per hr (lbs/hr) and which will read on-scale if any steam line relief valves are open. Detennine this release from the operators for the appropriate channel (512, 522, 532, 542).
FR = (lbs/hr) Release Rates for noble gases, iodines, and particulates can then be calculated as: Ci uti x 3.1 x 10~8* = Tic QNG = FR lbshr x C N08 GAS cc Ci lbs xC IODINE uti x 3.1 x 10~6 = He QIODINE = FR hr CC lb$ x 3.1 x 10' PARTICULATES = FR hr PARTICULATE j Tic l
- Factor to convert 10s/hr to cc/sec and uCi/cc to Ci/ set based on specific volume of steam.
- 28. Operation of Relief and/or Safety Valves Each steam line has six relief valves. Detennine which valves are open and total the relief capacity of the open valves.
O DC0203 SI
69-11105 Page 6 of 8 7/83_(50) TITLE: WORKSHEET FOR USE OF MAIN STEAM LINE MONITORS, CR RCS COOLANT SAMPLE RESULTS-0URING S/G TUBE RUPTURE ACCIDENT ATTACHMENT 1 O Valve Relief Capacity (If Open) in (lbs/hr) 10% Steam Dump 4.0 x 105
#1 Safety 8.5 x 105
#2 Safety 8.5 x 10 5
#3 Safety 8.5 x 105
#4 Safety 8.5 x 105 v5 Safety 8.5 x 105 Total relief from open valves = FR = (lbs/hr)
. Ci Q = FR lbs x C NOB GAS uCi x 3.1 x 10 6* = He NG hr cc
. Ci lbs xC IODINE uCi x 3.1 x 10 6 = He QIODINE = FR nr cc lbs xC PARTICULATE uC x 3.1 x 10~6 =
PARTICULATES = FR e Ci HC
- Factor to convert lbs/hr to cc/sec and uCi/sa. Based on the specific volume of steam.
2C. Primary to Secondary Leak Rate l Atmospheric release of steam can be estimated if the primary to secondary i leak rate is known. If direct determination of this value is not I possible, the default value for a steam generator tube rupture is 600 l gpm. l l FR = (gpm) Calculate Equivalent Steam Flow (Use if Steam Generator is not flooded) cc FR1 = FR x 1.13 x 103* = He l
- Factor to convert gpm (water) to cc/sec (steam)
DC0203 61 O
;.. Page 7 of 8 69-11105 7/83 (50)
TITLE: WORKSHEET FOR USE OF MAIN STEAM LINE MONITORS, OR RCS COOLANT SAMPLE RESULTS DURING S/G TUBE RUPTURE ACCIDENT O ATTAC)NENT 1 Calculate Ecuivalent Water Flow (Use if Steam Generator is flooded) FR A = FR x 63.08" = (C) (Ci T A CC xC x 10 s = (sec / QNG = FR seC N08 GASCC (uci h!ODINE = FR1 (g g x CIODINE (uci) x 1 x 10 6 = (Ci)sec
\seC/ \ CC/
C4 ge\j PARTICULATE = FR3 PARTICULATE ( c) x C (")1x10-s.
** Factor to Convert gpm (water) to CC/sec (water)
O l lO 0C0203 71 i f - -
Page 8 of 8 69-11105 7/83 (50) TITLE: WORKSHEET FOR USE OF MAIN STEAM LINE MONITORS, OR RCS COOLANT SAMPLE RESULTS DURING S/G TUBE RUPTURE ACCIDENT ATTACHMENT 1 FIGURE A - O StamLine Monitors Response Curve * (RE-71,72,73 & 74) 2 - a I
- , .. 4 ... .t ,,,, ,...... , ,,, ,,,-4
,; i Hli i !!: Ilil" Ii!lill i Ill Iililiq 3g 5 t
i ,..,.., ,, e i. .. ,4n,... .i.... .
# II I I"I' IUE 10 o ,.-_-.
$ , , . . ,$ , , 4,, J ,...,,6 I N/[ . . . .. . . . .
[ jo 3
~
I I HM i HIH I I Hihi - M i ! Hui i i 1. c
% bnergency ,
oc Initial , i> w , - ( Rel ease Curve! '' 2 I' IIIN I I' ' I 10 . M 6.0 CPM /uCi/cr_N . :-- : I Ik !I # ' .[ lllhL f f I 'i i o il ll l A ' i- No m i s I I'I M I 7_'.~ Operations (Equilibrium T* ,,,g f
,', Curve) g 1.0 _
WR liil 34.5 CPM /uCi/cc * ' ' "'l 8 ' y M
/ _
i * , , ii i . . ...i 10*I !I I I I UU' I II'M 3 I I ' 5 M i
,iihF
.1 t , n ,i ;i...- . .g I
i,..i. ..i.ir j 10-2 ) ; ,,;;. ; , , jii! ; , ; g,,ij gg;;g , ,;; g, g , ,,,q 2 3 4 6 10 10 10 10 10' 10 Net Counts Per Minute (CPM)
- Isotopic Composition Based On Average Values from FSAR Tables 11.1-11, 12 and 17 for Normal Operations and for Emergency Conditions the Carryover Factors Applied to Normal lodine Values are 0.13% Volatile Plus 0.25% Mechanical and only 0.25:
Mechanical for Particulates. O, DC0203 81
69-10262 7/82 (100) Sheet 1 of 4 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2
, PART A: RADIOLOGICAL EMERGENCY STATUS FORM Provide as much information as is available and appropriate at the time of the status report. Date: / / Time: AM/PM Status Report # (Fom Completed) (Numoer Sequentially) Person Authorizing Report: (DCPP only) Site Emergency Coordinator Person Transmitting Report: Location (DCPP only) TSC DIST: (9 copies) EOF DIST: (10 copies)
- 1. Site Emergency coordinator 1. Recovery Manager
- 2. Emergency Evaluation & Recovery Coord. 2. UDAC
- 3. Emergency Liason Coordinator (2) 3. Advisor To The County
- 4. Emergency Maintenance Coord. 4. Radiological Emerg. , R.M.
- 5. Emergency Operations Coordinator 5. Operations and Analytical, R.M.
- 6. Emergency Radiological Advisor 6. Engineering and Logistics, R.M.
- 7. NRC Office 7. Public Information, R.M.
- 8. TSC File 8. Coporate Law Dept. Coord.
- 9. TSC Status Board 9. EOF Status File
- 10. EOF Emerg. Status Board O 1. Emergency Classification: Unusual Event Site Area Emergency Alert General Emergency
- 2. Update on Incident: Date / / Time Incident Began: AM PM
- a. Site Emergency Signal Sounded YES [] NO []
- b. What Happened:
- 3. Radiological Release Information: (attach isotopic breakdown if available)
- a. Time Data Collected: AM/PM Unit Involved 1 2
- b. Release: Occurring Anticipated--When: AM/PM
- c. Location of Release: Plant Vent Steam Surface Liquid Dch,
- d. Estimated Duration of Release: Hours O DC0042 8V
Sheet 2 of 4 69-10262 7/82 (100) PACIFIC GAS AND ELECTRIC COMPANY DEPARTNENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2
- e. Release Monitored: by monitors #
Ci/sec, f. Iodine: Est.IotalQuantity _Ci Release Rate Ci Release Rate C1/sec.
- g. Particulates: Est. Total Quantity Cf/sec, Noble Gases: Est. Total Quantity Ci Release Rate
- h.
2 dpm/100cm Where:
- i. Estimate of Surface Contamination:
(attach form 69-10296 for cut of plant contamination readings) mR/hr:
- j. Unusual Radiation Levels in Plant: Where; Radiation Level at site boundary (downwind) mR/hr:
- k. (sector)
- 1. Meteorological Date (Use 10m elevation on primary met tower or designate other )
Source mph Direction (from): deg.
- m. Wind Velocity: m/secx2.2=
Rain Clear Fog Cloudy
- n. Weather Conditions:
- o. Stability: degrees C/-
Sigma A (deg): Delta T: Class (10m to 76m or ) & E Mixing Depth m. MF X/0 800m=
- p. Projection Time DOSE RATE INTEGRATED DOSE CENTERLINE (EARS 52cTOR ) mR AFFEiiEC DOSE PROJECTIONS PLUME ARRIVAL mR /hr W.B. THY SECTOR TIME W.B. THY (Circle Which)
Site Boundary (800m) 2 Miles (2-5) 6 Miles (5-10) 10 Miles (10-20) EARS PLUME CENTER DOSE radius ' 4. Reconinended Emergency Actions / Protective Measures for SLO County or California Department Radiation Health (Provide only new reconsnendations): i
- 5. Emergency Response Actions Underway by PGandE:
a
- 6. Prognosis for Escalation or Tennination of Accident:
OC0042 9V
. 69-10262 7/82 (100) Sheet 3 of 4 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 PART B: MISCELLANEOUS EMERGENCY INFORMATION FORM Provide as much information as is available and appropriate at the time of the status report.
Date: / / Time: AM/PM Status # (Report Completed) (Numoer sequentiallyJ Person Authorizing Report: (DCPP only) Site E.mergency cooroinator Person Preparing Report: Location (DCPP only) Time Data Collected AM/PM
- 1. Personnel Injuries: How Many? -
- a. Type: Contamination: _ Yes No
- b. Injured Person Location: Plant Ambulance Hospital (wnicn)
Other (wnere)
- c. Ambulance requested _ Yes No. Location .
- 2. Fires:
- a. Lo::ation: Time Reported: AM/PM
- b. Type: Electrical Fuel (wnat kina)
- c. Contamination Present: Yes _ No
- d. Fire Assistance Requested: Yes No
- e. Fire Assistance Onsite: Yes _No
- 3. Security / Safeguards:
- a. Bomb Threat: Search Conducted: _ Yes No Search Results:
Site Evacuated: Yes No
- b. Intrusion: Insider: Outsider Point of Intrusion: Extent of Intrusion:
Apparent
Purpose:
I DC0042 10V
l l 69-10262 7/82 (100) Sheet 4 of 4 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 Part B: Miscellaneous Emeroency Information Form -
- c. Strike / Demonstrations: Size of Group:
Purpose:
. d. Sabotage: Radiological: Yes No Arson: Yes No Equipment / Property:
- e. Extortion: Source (phone, letter, etc. ):
Location of Letter: Demands:
- f. General: Firearms Involved: Yes No Violence: Yes No Control of Facility Compromised or Threatened: Yes No Stolen / Missing Material:
Agencies Notified (FBI, State Police, County Sheriff, etc.): (circle agencies onsite) 4 Press Information: Location of Press Release: San Francisco /___ San Luis Obispo Other: (wnere) Time of Press Release: AM/PM News Media Interest: Yes No Local / National: Data Received By: Date: / / Time: AM/PM RETAIN THIS FORM FOR EVENT EVALUATION l l O 0C0042 11V
O T E E S lE i N S O - P S E R E T A D S N N E O V I I T G A D R R E ET O G PN C A OA E S L R S T P E N N M AR O LE I PW T O A RP C A I EN F l O I CY T l iN O NA N C f Y Y OO C B L N T B E l l A G El R Ml i E T t t D R E E A l l P C E A D E R E M I T N O I T A 4 I N L O I I F T F
' A A " C " I F l u I T D , ' N E u E L e D L s I A C
Y
. C N - N O ' E S > G R - R E O s E P u M %
E
i NWBER EP R-6 P(BE/E Pacific Gas and Electric Company REVISICtr 6 . A DATE 7/5/83 DEPARTMENT OF NUCLEAR PLANT OPERATIONS 1 AND 2 PAGE lOF 10 DIABLO CANYON POWER PLANT UNIT NO(S) EMERGENCY PROCEDURE TITLE: RADIOLOG! CAL FIRE APPROVED: b [3 DATE PLANTMAgdER SCOPE This procedure discusses the actions which are taken in the event of a fire which involves radioactive materials or radiation. This procedure and changes thereto requires PSRC review. GENERAL
. A radiological fire is one which involves either radiation or radioactive materials. Examples of this type of fire are fires in the solid radwaste storage facility, the drunming station, contaminated ventilation filters, and electrical or lube oil fires in radiation areas. The primary hazard (after plant safety and personnel injury) is the spread of contamination. All reasonable attempts to prevent the spread of smoke-borne contamination should be made.
SYMPTOMS
- 1. A fire is discovered in the auxiliary building, fuel handling building, containment or solid radwaste storage facility.
- 2. The fire detection system annunciator indicates a fire in any area where radioactive materials or radiation areas are present.
AUTOMATIC ACTION The fire water sprinkler sys ems may activate. IMMEDIATE ACTION
- 1. - '"XX" is a code which Activate gives thethe fire signal location by(dialing useeTable1).bhefiresignalisa of fire 30-second blast on the fire sirens. The signal will be followed by the location code of the fire on the code call system repeated 8 times. The first five persons to dial 76 will be connected into a conference call. The priority for the conference call is:
- a. Shif t Foreman (Interim Site Emergency Coordinator).
t l b. Senior Control Operator (Fire Brigade Leader). t . ) < f DC0009 111
. e
N R P R-6 1 AND 2 , DIABLO CANYON POWER PUNT UNIT NO(S) l ATE 7/5/83 PAGE 20F 10 m LE. RADIOLOGICAL FIRE , 1
- c. Assistant Fire Brigade Leaders (two).
4 d. Plant Superintendent / Manager ,
- e. Fire Marshal
- 2. The Shift Foreman and Senior Control Operator will dial 76 and be given full details regardin'g the fire. These should include exact locations, severity, potential danger to the safety of the plant and any special radiological hazards present. The Shift Foreman shall coordinate the emergency action.
- 3. Members of the on-shift fire brigade should report to the control room to pick up their equipment and receive instructions from the Shift Foreman. The Shif t Foreman is responsible for establishing an appropriate on-shift emergency organization and assuring that Technical Specifications for control room staffing are not violated.
- 4. If the fire occurs during nonnal working hours, members of the -
maintenance fire brigades should go to the cold machine shop. I The Assistant Fire Brigade Leaders should enter the conference call to receive their instructions.
- 5. If appropriate, change the control room ventilation system to the isolation mode (Mode 3) to prevent the entry of smoke and airborne activity.
- 6. Clear the area affected by the fire. This may be done by sounding the Site Emergency Signal, or other appropriate means.
- 7. Fire fighters should wear supplied air breathing apparatus.unless air samples have been taken and indicate that there is no airborne activity hazard. Supplied air breathing apparatus should also be used when smoke inhalation is a hazard. When self-contained breathing apparatus (SCBA) is used, a crew should be dispatched to an air bottling refilling station and prepare to refill the backpack bottles as required. The stations are located at the northwest end of the Unit 2 component cooline water heat exchangers on the +85-foot elevation and on the
+140-foot elevation behind the Control Room.
SUBSEQUENT ACTIONS The Shif t Foreman, acting as Interim Site Emergency Coordinator, shall direct all subsequent actions from the Control Room until relieved by the long-tenn Site Emergency Coordinator if the emergency warrants it. ,
' Such actions should include the following: )
n DC0009 211 9
1 AND 2 N R P R-6 DIA8LO CANYON POWER PLANT UNIT NO(S) ,
% DATE 7/5/83 PAGE 30F 10 l 7,7a RADIOLOGICAL FIRE j
)
- 1. If a fire cannot be physically contained and controlled promptly
~
with available resources, assistance from the California
- Department of Forestry should be requested. Their assistance should also be requested at any other time the Fire Brigade Leader feels that they may be needed. Refer to Appendix 1 for telephone numbers.
M: 1) If outside assistance has been requested notify the Security Department ((3330 or 336Q an,d have l them notify the Avila Gate. One or more plant operating personnel shall be dispatched to the Security Building to escort and provide radiological monitoring to CDF personnel.
- 2) Maintain a record of notifications made to offsite personnel, Form 69-922 " Emergency Notification l Record" may be used to provide this record.
- 2. If CDF is called to respond, insure that the person calling CDF l gives a name and number to call the plant back. Provide CDF with details concerning location and the type of fire. Also give CDF O/ an update of the fire conditions even before they arrive as they may decide to send more support.
- 3. If CDF responds, their first responding Chief Officer will identify himself. He may initially decide to go to the scene of the fire. He will eventually decide to contact the PGandE Site Emergency Coordinator. Therefore, escort and access should be provided to him to reach either the control room or TSC, depending on where the Site Emergency Coordinator is located.
- 4. During the course of the fire, the Control Operator and those at the scene should pay particular attention for signs that the operability of the various engineered safeguards equipment is reduced below minimum Technical Specification limits, or if such damage is insninent, shut down the unit insnediately.
g: Operating Procedure K-2C provides the operator with listing of safeguards equipment which may be affected by fires in various locations. This procedure should be consulted to assist in determining the operating strategy during the fire.
- 5. Establish an initial emergency :lassification based on the criteria in Appendix Z and perform the actions required by the classification.
i O DC0009 311
1 *AND 2 NUMBER EP R-6 DIABLO CANYON POWER PLANT UNIT NO'S) REVISION 6 l DATE 7/5/83 l ~ PAGE OF 10 ' mLE. RADIOLOGICAL FIRE t f
- 6. If the Control Room must be evacuated, follow the instructions given in Emergency Procedure OP-8.
- 7. If a sprinkler system was activated, the thermal element must be replaced before the system can be resei..
- 8. Investigate to see whether any radioactive material release limits were violated.
- 9. Close out with verbal sumary to offsite organizations and complete the following written reports:
- a. Plant Problem Report (See Nuclear Plant Administrative l Procedure C-12)
- b. Written sumary to NRC within 24 hours for an Unusual Event or 8 hours for a higher classification.
- 10. If a fire has been put out before CDF arrives, they may still request to send one engine company to visit the site for their close out.
~
l 1 l s 6 G
' ^
DC0009 4II
1 AND 2 N R P R-6 OiABLO CANYON POWER PLANT UNIT NO(S) . DATE 7/5/83 PAGE 5 OF 10
,,7 7 RADIOLOGICAL FIRE ,
REFERENCES
# 1. Emergency Procedure M-6, "Non-Radiological Fire." ,
- 2. Emergency Procedure G-1, " Accident Classification and Emergency Plan Activation."
- 3. Emergency Procedure G-2, "Establishmert of the Onsite Emergency Organization.
4 Emergency Procedure G-3, " Notification of Offsite Organizations."
- 5. Diablo Canyon Power Plant - Fire Protection Plan.
- 6. General Operating Order 1.300 and 1.301.
- 7. PGandE Fire Prevention Manual.
- 8. Accident Prevention Rule 23.
ATTACHMENTS
- 1. Form 69-9221. " Emergency Notification Record," 7/80.
a . DC0009 SII i N
NUVDEA EP R-6 I bb0 2 DIABLO C AP4YOP4 POWER PLN4T tJtitT PJO(S) RENISION 6 OATE 7/5/83 PAGE 6 or 10 RADIOLOGICAL. FIRE rir g TABLE _1_
- FIRE CODE CALL LOCATIONS LOCATIONS CODE Control Building No. 1 Containment No. 1 Turbine Building No. 1 Auxiliary Building No. 1 Fuel Handling Building Package Boiler Area Hot machine shop area No. 2 Containment No. 2 Turbine Building I No. 2 Auxiliary Building l' No. 2 Fuel Handling Building Security Diesel Area Grass Fire Outside Transformer Fire Intake Structure 1 500 kV Switchyard i
i 230 kV Switchyard
- Radwaste Stcrage All Clear
'I .. Fire Drill
.__ x j i
i
'- OC0009 611 c
j EP R-6 NUM8ER 6 1 AND 2 REVISION 7/5/83 . OATE 7 OF10 PAGE oueLO CANYON POWER PLANT UNIT PC(S)
- RADIOLOGICAL FIRC I 7,7g .
TABLE I (Cont'd) FIRE CODE CALL LOCATIONS LOCATIONS Cg Test Fire Code Administration Butiding Security Building Training Building Assently Building Technical Support Center g i I l l t
.,,11
( DC0003 711 9: 1 I
\
NUMBER EP R-6 REVISION 6 DIAOLO CANYON POWER PtN4T UNIT NO(S) DATE 7/5/83 i PAGE 8 0F 10 RADIOLOGICAL FIRE , Tirut. AFPENDIX 1
-a flRE ASSISTANCE COMMUNICATION California Department of Forestry 543-4242 (Emergency Only) 1.
543-4244 (Business) SE San Luis Obispo County Sheriff 1. Automatic Tie Line (Request they dispatch the (Control Room and TSC) California Department of Forestry) 2. Radio (Control Room, TSC or Security) SE
- 3. 543-7911 (Emergency Only) 543-2850 (Business)
Plant Extension: ,'
- 2. Fire Marshal Randy Kohout Home Phone:
SE t HP Freq. Pager Call No. (Group Call 411) _j-f e 4 DC0009 811
N R M DiABLO CANYON POWER PLANT UNIT NCMS) DATE 7/5/83 i O 7, RADIOLOGICAL FIRE PAGE 9 OF10 l i APPENDIX Z
. EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been implemented, and upon direction from the Shift Foreman, proceeds as follows:
- a. Designate this event a Notification of Unusual Event if a verified fire is not under control within 10 minutes of initiating fire fighting efforts or if California Division ,
of Forestry Assistance is requested, or for any fire in radioactive material causing an uncontrolled increase in airborne activity. 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 Organizations" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation."
- b. Designate this event an ALERT if a verified fire is not under control within 10 minutes of . initiating fire fighting efforts and the fire is located in one of the following areas containing safety systems:
- 1) Containment
- 2) Control Room
- 3) Cable Spreading Room
- 4) Diesel Gener& tor Room
- 5) Auxiliary Building
- 6) Intake Structure Pump Room Notify Plant Staff and response organizations required by EP G-2 and EP G-3 in accordance with EP G-1.
- c. Designate this event a Site Area Emergency if a verified fire is not under control within 10 minutes of initiating fire fighting efforts in an area containing safety systems,
! and causes a confirmed loss of a safety system function that
- causes entry into a technical specification action statement. Notify plant staff and response organizations l required by EP G-2 and EP G-3 in accordance with EP G-1.
- d. Designate this event a General Emergency if the fire causes massive damage to plant systems which, in the opinion of the Site Emergency Coordinator, is likely to lead to a core melt
,O) situation. Notify plant staff and response organizations l V required by EP G-2 and EP G-3 and implement the instructions l
f in EP G-1 regarding on and offsite protective actions. DC0009 91I l 1 l 1 1
O 1 ND 2 NUMBER EP R-6 oiAsi.o CANYON POWER Pt. ANT UNIT NO(8) REVISION 6 OATE 7/5/83 ! PAGE 10oP 10 7,7g RADIOLOGICAL FIRE l
- 2. In addition to personrel required to be notified by EP G-2 also notify the following:
- a. Fire Marshal (See Appendix 1)
- b. System Dispatcher (if load may be affected)
NOTE: In off-nonnal working hours, consid:retion should also be f given to calling in additional members of the Plant Fire Brigade. l This should not take precedence over calling CDF. O l l l O. DC0009 10l!
]
)
e - l l I i i l l A
^
f 9 1 W . I e z 5
- 4 w-E e 8 bka W m m
-= y km sw 5
== v 4 -
u, b - Sz C zC 2 i w > - oc v cc ' J z x " WE
- W e
= w w 4 2 m W W
W E N 4 5 3 C w W O 4 O- a* 1
- w Q
= w S
~
W
- d u
~
u 5 m N E I
$ @ w g
u\ L \
- w
' NuusER EP R-7 HDGY4E Pacific Gas and Electric Company REVISION 3 " DEPARTMENT OF NUCLEAR PLANT OPERATONS DATE 7/5/83 1 AND 2 PAGE 10F 10 DIABLO CANYON POWER PLANT UNIT NO(S)
EMERGENCY PROCEDURE 1 TITLE: 0FFSITE TRANSPORTATION ACCIDENTS W
- APPROVED: YO DATE PLANTMANAy 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 procedure and changes thereto requires PSRC review.
DISCUSSION Once a shipment of radioactive materials 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 Company. However, if an accident occurs in the vicinity of the plant, O local officials may request the assistance of plant personnel for l radiological monitoring because of their knowledge and experience and I because of the monitoring and other equipment at their disposal. Plant l 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. IWEDIATE OPERATOR ACTIONS
- 1. In the initial contact, the individual receiving the message should try to gather the following infonnation:
- a. Location of' accident. ,
d DC0009 111
l i
. l NUMBER EP R-7 l DiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 i
DATE 7/5/83 PAGE 2 OF10 TITLE- 0FFSITE TRANSPORTATION ACCIDENTS
- b. Type of material involved:
i
- 1) New fuel
- 2) Spent fuel
- 3) Solid radwaste
- 4) Liquid radwaste
- 5) Phannaceuticals
- 6) Sources .
- 7) Special Nuclear Material
- 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
- g. The results of any measurements which have been made.
- h. Who is on the scene and who is in charge?
- i. What recovery actions are planned or being taken?
l
- j. The identity of the carrier.
l
- k. Origination point and destination of the shipment.
- 1. The name and phone number of the caller.
- 2. Notify the Shift Foreman.
l
- 3. The Shift Foreman should insure that a record is kept of the initial contact as well as all subsequent contacts with offsite persons. Fonn 69-9221, " Emergency Notification Record," is J
provided to assist in this. 1 l l OC0009 2II
N
- EP R-7 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 3
~
DATE 7/5/83 Tri m 0FFSITE TRANSPORTATION ACCIDENTS SUBSEQUENT ACTIONS
~
- 1. Perform the notifications required 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 retention of smear samples.
- i. Pocket dosimeters and (if time permits) the team members' personnel dosimeters (film badge or TLD).
J. Survey foms (Foms 69-9315 and 69-9316 preferred, but Fom 69-9259 is also okay). f0"E 1: 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 submerged in water) a neutron dose rate meter (such as the PNR-4or5) could be taken if readily available. This instrument is not necessary, however, since gama radiation always accompanies a criticality. lf%b DC0009 311 l l
R-7 OtasLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 7/5/83 mLE. OFFSITE TRANSPORTATION ACCIDENTS
- 3. Close out with a verbal sumary to offsite authorities in step 1 above. If classified as an unusual Event, follow with a written summary to NRC within 24 hours.
f INSTRUCTIONS FOR MONITORING TEAM
- 1. Make gama dose rate measurements since this is the most likely hazard. If any significant gama dose rate is measured, erect a barrier 50 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.
g: 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. I
- 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 d'pm/100 cm2 if Pu-239 may be present.
- b. 1000 dpm/100 cm2 if Pu-239 is not present but uranium, I-131 or Sr-90 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 cm2 by the following formula: [dpm/100cm].(CRnet) 2 epsiloni l l i DC0009 411 l
NUMBER EP R-7 DU@LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 , DATE 7/5/83 PAGE 5 OF10 (, TITLE. OFFSITE TRANSPORTATION ACCIDENTS where:
. CR = net cpm on instrument net
* (CP"} gross, Shi'Id Off ~(CP"Ibackground epsilong = probe efficiency factor from Table 1 NOTE 1: The alpha probe is sensitive to sunlight. Therefore, shield the probe to the extent practical.
NOTE 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 detennine whether smearable contamination is present. If alpha contamination is likely, use 2" filters for taking the smears. Retain all smear samples for subsequent
/. laboratory analysis.
2 Count the samples and detennine the [dpm/100 cm ] in accordance with the following fonnula: 1 [dpm/100 cm 2 ] . (. )(CRnet) (epsilon 2) (A) where: (CRnet) = net cpm as above 1 epsilon 2 = probe efficiency factor from Table 1 A = area smeared (ft2 ) t DC0009 511
N R EP R-7 CIABLO CANYON POWER PLANT UNIT NO(S) 1 AND' 2 DATE 7/5/83 PAGE 6 OF10 TITLE. OFFSITE TRANSPORTATION ACCIDENTS
- 4. If criticality or fuel melting is a possibility, erect barriers at least 100 yards from the scene.
A criticality is accompanied by a blue flash which is E :le even when a person is not looking at the source. visib
- 5. 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 Emergency Coordinator. Try to prevent any unbadged person from 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 benns and rocks.
- 9. Advise and assist in the treatment of any injured and/or cnntaminated 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 Oose Rate Survey Record"
- 4. Form 69-9259, " Emergency Environmental Monitoring Field Data Sheet" O'
OC0009 6II L_____-._ _ _._ _ _ _ _ _ _ _ . . _ _ _ . . _ _ _ _ _ _ _ _ _ _ - - - - -- ---M
N n EP R-7 DIABLO CANYON POWER PL. ANT UNIT NO(S) 1 AND 2 g DATE 7/5/83 I TITLE. OFFSITE TRANSPORTATION ACCIDENTS 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 RB-4 Access to anc Establishment of Controlled Areas Under Emergency Conditions. RCP G-6 Release of Materials from Controlled Areas. EP RB-6 Area and Equipment Decontamination. r O n (
- DC0009 711 l
l I ! l l _
i NUMBER EP R-7 olASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 7/5/43 TITLE OFFSITE TRANSPORTATION ACCIDENTS TABLE 1 l
- PROBE EFFICIENCIES FOR SURVEY INSTRUMENTS l
l l PROBE EPSILONI (direct survey) EPSILON 2(smear) (com/dpm/100 cm2 ) (cpm /dpm) I l HP-240 0.011 0.018 HP-260 0.040 0.20 HP-210 0.040 0.18 HP-230A 0.0029 0.016 l Alpha 0.056 0.095 l l l l e DC0009 811
N R R-7 1 AND 2 OtABLO CAP 4YCr4 POWEA PLN4T UNIT P O(S) DATE 7/5/83 PAGE 9 OF 10 I rarts 0FFSITE TRANSPORTATION ACCIDENTS APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS When this emergency procedure has been implemented, and upon 1. direction from the Shif t Foreman, proceed as follows:
- a. Notify the following plant staf f personnel, or their designated alternates:
Plant Manager Plant Superintendent
, Supervisor of Chemistry and Radiation Protection
' Power Plant Engineer-Supervisor of Operations Technical Assistant to the Plant Manager
- b. Report the situation to the County Sheriff's Office and California Office of Emergency Services. They may already be aware of the situation, so this may be a courtesy call.
s
- c. If the shipment originated or had a distinction at the piant, designate this event a Notification of Unusual Event.
Notify plant staff and response agencies required by Emergency Procedures G-2 " Establishment of the 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 perfonted under 1 above, also notify the following company personnel:
- a. Supervising Nuclear Generation Engineer (Person.nel and Environmental Safety): -_
Mr. W.H. Fujimoto f PGandE office , Office / Home
-J If the above cannot be promptly reached request the
[QE: system dispatcher to contact alternate personnel.
\
i(
/
DC0009 911
~
>f -
g , 3 1 AND 2 DI ABLO CA?4YCN POWER Pt.N4T UNIT PA3(S) DATE 7/5/83
- PAGE lOJF 10 Tarts 0FFSITE TRANSPORTATION ACCIDENTS
- b. Los Padres District Manager:
-. 7 Mr. D.L. Kennady
. Office Office Home J If the above cannot be promptly reached request Morro IM: itching Center to contact alternate personnel.
Bay Sw M 5 o i t# % t
O
/
l W W Y 5 m W O
~,
w W l e E 5 *
; G g C b
t~ S 4 J N W
-m ,
E= aw 5 Ea O 4 =
, wX W JG =
C l
=v
=
COJ O 433 e E E4 " WE W W D E w w 4 Z L w b w E t I i m r 5 c -
^
8 5 e
- W W D E w 8 8
~
y I l t <. R >. w r t\' u E C t
~ E e
E ; N. = w - 1 U\
- h w i
69-9315 7/80 (100) DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT CONTAMINATION SURVEY RECORD SURVEY NO. TIME _ SWP/RWP NO. ()DATE W AREA DR EQUIPMENT DIRECT SURVEY RESULTS _ EFFI. dom TYPE INST. DETECT 0p GROSS BKG NET CIENCY Hm CPM CPM ITEM DESCRIPTION , gy jyk USED CPM s O REMOVABLE CONTAMINATION SURVEY RESULTS INSTRUMENT USED TOTAL GROSS BKG NET EFFI- d or. TYPE AREA, COUNT cpm cpm CIENCY ITEM DESCRIPTION ,- sv dm2 TIME COUNTS cpm am'___
- COMMENTS DATE/ TIME COUNTED BY l SURVEYED GY - DATE REVIEWED BY SUPERVISOR
DEPARTMENT OF NUCLEAR PLANT OPERATIONS 69-9316 7/80 (100) DIABLO CANYON POWER PLANT j RADIATION DOSE RATE SURVEY RECORD SURVEY NO. TIME SWP/RWP NO DATE
,f AREA OR EQUIPMENT SHEET OF TYPE OF SURVEY GAMMA NEUTRON BETA ITEM ND.
DESCRIPTION m rad /hddistance mR/hrldistancemrem/hr l distance t i a SURVEYED BY -n SERIAL NO. DATE CALIB. DUE SURVEY TYPE INSTRUMENT TYPE DETECTOR BETA GA M NEUTRON C019 TENTS __ RECOMMENDATIONS (O DATE SURVEY REVIEWED SUPERVISOR
69-9259 7 /83 (1000) Page 1 of 2 PACIFIC GAS AND ELECTRIC COMPANY NUCLEAR PLANT OPERATIONS DIABLO CANYO3 POWER PLANT UNIT N05. 1 AND 2 EMERGENCV E~VIR0fMENTAL MONITORING FIELD DATA 5HEET Team Leader Memoer nitoring Location i
- 1. THREE FOOT BETA-GtM% RADIATION FIELD READINGS
- a. Count Rate Calibration Due Date CPH[ Shield off(UP)] CPM [ Shield on(down)]
. Type of Time Probe Gross BKG* Net Gross BKG* het
- b. Dose Rate Calibration Due Date mR/hr(Window Open) mR/hr(Window Closed)
Time Instrurent Gross BKG* Idet Gross BKG* het
- c. Integral Dose g g g g g Time Time i Dura t An(HR) Total Dose Rate (mR/hr)
Instrument Started Complete (0-u) Dose (mR) @; G
- 2. AIR 5 AMPLE DATA Calibration Due Time Time uuration Flow .h te Sample Volume Sampler --
Started Completed (Minutes) (CFM) (FT3)
- 3. PARTICULATE DETERMINATION
@ @ @x}.59x10~
c, sype of CPM (Shield off) G Q E (d *(M " O Tu iimi) Probe Gross BKG* Net 8: J. Volume (FT 3)
- 4. IODINE DETERMINATION Type of CPM (Shield Off) @ g C timl)
_!1che., Grcss. EG* g c, Volume (FT 3 )
' NUMERICAL VALUE FOUND IN DiERGENCY PROCEDURE RB-7 OR RB-B o
Page 2 of 2
- 5. D4VIRONMENTAL MONITOR READIES Calibration Due b. 1*!C-4 Reading Calibration Due
- a. PIC Reading Time DoseRate(ed/hr) @ @
Count Scaler Time @i@ (mR/hr) Count (SecL
- 6. GROUhD SURVEYS 79 ,
Probe Gross CPM (Shield off) BKG* M h gg) (uC1/ml Description
- 7. VEGETATION SAMPLES NOTE: USE HP-240 OR EQUIVALENT PROBE CPM (Shield off)
'" g @(x2.5x10'g uC1/ml)
Description Gross BKG* M
- 8. SMEAR SAMPLES 3 _
m Area 0.11 x(I) Tim W Smeared xQ) Net @ (Ft?) (u i/dm,) Description _ Probe Gross B3* 3
- 9. LIQUID SAMPLES Imersion Data Tim Volume of Gross Het Sample Counted CPM BKG* CPM Description
- 10. REMARKS G.
. NUM ER EP M-1 FGseE Pacific Gas and Electric Company REVISIOr4 10 m DATE 7/5/83 DEPARTMENT OF NUCLEAR PLANT OPERATIONS , PAGE lOF 4 DIABLO CANYON POWER PLN4T UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE TITLE: EMPLOYEE INJURY OR ILLNESS (NONRADIOLOGICAL)
APPROVED: Y- DATE PLANTMAtyER SCOPE This procedure describes the actions which are to be taken in the event of an illness or injury to an employee which does not involve radioactive contamination or overexposure. Injuries in which radiological considerations are involved are discussed separately in the R series of Emergency Procedures. This' procedure and changes thereto requires PSRC review. APPLICABILITY This procedure is to be followed for incidents involving Nuclear Plant Operations personnel, or other company employees at the plant site at the request of the Nuclear Plant Operations Department. In the event of an incident involving any other company employee (such as a General Construction Employee), perfonn only the asterisked (*) steps in this procedure. [FtiEDIATE ACTIONS The employee (s) who are at the scene shall:
*1. Render all necessary first aid.
*2. Notify the control room (Shift Foreman) as soon as practical.
SUBSEQUENT ACTIONS The Shift Foreman shall direct all subsequent actions until relieved by the long term Site Emergency Coordinator if the emergency warrants it. Such actions should include the following:
*1. Sound emergency signal, code override, or other gene.al warning signal to clear the area if the situation warrants it.
*2. Dispatch addition first aid personnel such as the project construction EMT Extension to the scene of the injury or illness if required. " Personnel whN'have not been instructed to provide assistance at the scene should remain on their jobs and stay clear of the affected area.
! 's C OC0152 IX
. e t
N N 01ABLO CANYON POWER PLANT UNIT NCMS) 1 AND 2 , DATE 7/5/83 PAGE 2 op 4 mm EMPLOYEE INJURY OR ILLNESS (NONRADIOLOGICAL)
. *3. Transport the injured person to a Company panel physician or
[ hospital if the situation warrants it (refer to the attached
.-- list). If possible, the employee is to be accompanied by a supervisor. The practices which are to be followed if this step is necessary are given in the following section of this procedure.
4 Secure the names and addresses of all witnesses (both Company and non-Company).
*S. Perfom the notifications 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 where no medical treatment was required other than minor first aid at the plant,
- b. Form 62-4586, " Employer's Report of Occupational Injury of Illness" in all cases requiring medical treatment (including doctor referral) other than first aid or results in lost time beyond the ' day of injury.
- c. Fom 62-5542, " Report of Automobile Accident" if appropriate.
TRANSPORTATION OF INJURED PERSONNEL
- 1. The preferred mode of transportation for injured persons is by Company panel ambulance service. Company or private vehicles should only be used in cases where the delay associated with securing an ambulance might result in significant deterioration of the injured person's condition, or when the injury is of a minor nature where use of an ambulance is not warranted.
- 2. When requesting ambulance service (refer to the attached list),
provide the following information to the ambulance service.
- a. Name of caller
- b. Company affiliation
- c. Phone number of caller (where he can be reached)
- d. Name of injured or ill person DC0152 2X
ogn E 10
- 1 AND 2 sto cAnyoT4 PCWER PLN47 UNIT NO(S) , DATE 7/5/83 osa PAGE 3 op 4 Tsia EMPLOYEE INJURY OR ILLNESS (NONRAD10 LOGICAL) e.
Where the patient is located Where the patient is to be transported
.. f.
Nature of injury or illness g. h. Any other medical information which might be pertinent to transporting the injured person fication Record this information on Form.69-9221, " Emergency Noti Record", or other log. t
*3.
If ambulance or medical gersonnel a are_to enter the site, contac the Security Department E, San Luis entrance. It is necessary the to security force at the Porthave an escort accompany the ambulance ; Security Building to the patient. 4. If possible, have a supervisor If thisaccompany is not practical,the ital injured person t the hospital (or doctor's office). call a supervisor and have him meet the patient at the hospT (or doctor's about office). light duty program. the Company's 5. If possible, call ahead to the hospital (or doctor) and provide the following information:
- a. Name of caller
- 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 Medical history (if known) 9 h. Radiological conditions.I If the injury or illness is involved bsence with ofradiation, such see "R"Ho Emergency Procedures. h when radiation is not involved, because in t e aknowled ( o DC0152 3X s
- l 1 AND 2 I DIAsto CANYON POWER PLANT UNIT NO(S) ,
DATE 7/5/83 PAGE 4 OF 4 ( TITLE. EMPLOYEE INJURi OR ILLNESS (NONRADIOLOGICAL) , 3 Record this infomation on Fom 18-9221 "Erergency Notification 7 Record", or other log. r
- 6. A medical referral, Fom 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 foms 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"
- 3. Fom 62-6015. " Medical Referral"
- 4. Form 62-4542, " Report of Automobile Accident"
- 5. Fom 69-9221, " Emergency Notification Record"
- 6. Light Duty Program Letter
- 7. Company Panel of Physicians, Ambulance, and Hospitals serving the imediate 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. i l 10. Appendix Z, Emergency Procedure Notification Instructions l . i ! 4X DC0152 i
es.aee7 mee. trye PACIFIC GAS AND El.EC@lc COMPANY
' Report of Industnal irjury to Employee Name 6. Division 1.
ZIP
- 2. Address
- 7. Deperiment 1 heischone No.
Socal Security No. 8. Dats of Accu $ent I 4. Occupanon 9. Time of Ac=ident 5.
- 11. Nature of injury
- 10. Location of Accident
- 12. Wnst were you doing and how did accident occur?
11 Descnbe First Aid rendered: 1 l 14 Witnesses to acz:ident: l
- 1. l 2.
1 15. Sgnatureof Employee
- 16. Cate injury reported:
- 17. Date 30 days elapses: 18.
- See Over 5gnature of Supervisor INSTRUCTIONS: This report (ltems 1 mru 1S should be wrrrten and specf by the amo/cyee person-
! af/v and countersgned by me supervmor. It is for all Industnal Injuries and is in duplicats. The original is to be retained for Company recortes es copy is to be detactied after completion and given to the emolayee. Before ogning in lam 18.-tlTe supervisor should flit in me date of the report (item 16) and compute and notate me date J0 days from me data me injury was reported (item 17). If me employee later requires trustrnent by a doctor or becomes disabled, Form 62-4586 must be prepared and forwerced to me Safer /, Heeftn and C: aims Department /MMED/ATELY accompanied by me original of mis report if the emotoyee is unable to fill out or sign this report, it should be prepared, sogned by me sucervisor and the employee should be given a cocy within 5 days as required by law. If the injured e.3cloyee cannot write English, me recort may be made according to a versal statement. If necessary, me emotoyee may sign by a mark and a witness to the report should sign below me em-cloyee's mark.
?
~ . .
1 1 r l ' ~ mponesAtton Pom Tut mJunto assPtovat 1 1 Thas etM Wism urves sie I Casseervise baser Case . I The Cameeny has an entonow asfety orogrwn te noe res arreovene swomi wourv.The In me swert of :s a mort. L *< Sensral les8ernamesens Corveisny very romens wmay rueuerme messmas cas, esoas prove.en nas neon meme for tne test musicas servues seen=maa f s for
,smam sensomes w,tm re ensures amesovens. ans; is oreiss se erung me enes. cme program ossemens over vaars o as ernwic,
( Your 1 Benefit. Every reemrsese effort nett tse esweems in ansnanagwig trte grearrt aus eurerman of your enenssTiel innsry. The Ceneeny a ermevev soif ineares for inehsmias inesrae a tts arnseovens wason arise out of ans osmar in the oeurs of one mervi. Alt centenantion tow 1sta, swusung mesme wumament. ~ z t--m - proyene, ens saammiDtv povmmerte are somemsseres l e. .n.n v., -e-v.m-ev me Come ,v. if aus sons n.. l r IL temahome assiseu. Throup contwwarg eftern, me Ceneeny mas et 8.ame me teams of nors Jv ausstras onveces ans esecamists tnroureut PG4E sysumm. A sense cf esctors fameiner wrm me verseus Carreev trograre ans Denefvta. moussang me 6gm outy j were orogrwn, nas been . _- m to orowsee a resene nervue to the .nwes anosevue l reeuwes te care or roseswa veu f rorn true I You are entrikeuf a rousswa messant, estysati. c.vf steenstas serviess w=3 sucesses russensspy ef9ects of veur seasrv. entSustrig emerang cure erstl mesn they as crutaWien arid artlPacas trnets. Rosmanmas tranghortetsori arterise we.
- - - wi... -
i W of Taumasig Ptevuemen. Truserrent of insusviameurus empacrvsse er scorsmaa try me amenover et tne errosover's smoenia Ill. worn the amenovue merce me osseroentry as cnerius oorsonne if enerus. Casttorms ta= carna eneeovese uno mastamos en in-ausmas meurv is ne trustus try a envocasi er er a tess tr of tnmer emosme woman a ,summen.a gamerson.c ores emmmencent Jo es afsar one emme msnary a nuser1muf, or evemas.seov Oy veur perusr.ar anyonen.orvresas vont nortf ame tne Ceruney grier a veur meurv. If veu saan a carmnus veur orumm trascenent. veu mer se so, tt is rummemowresse *ner vene normnua arth ene enveems true mes been omvees, out tf veu ensi to cnaries easiert notefv veur ensarvisor. The Cornemov's est.orurse n tnis arms is swassces to as-est you en sanscung the orcost massians cure. If you mest to ensige to enetner tremong anymoe er *mmirty ofter 30 Youaows. sneuM3 you must nottfv vour sueerviser of one mene anal assrWW of me anytten er futHity veu mort 1Eissstes tR centtreue trWtrnent anose mis occumem to me onvenan or tammtv se inov enst tse nettres of trui wwwresnees outv is rueert to tne Cenemnv ou rus av Sarnen 48tI2.2 of tme Lamor Cees.19 me tacitrry or onvecie rueumers.vea are ruaunus to agre e wwasse enfermenon re-iemme to osemrt runerts of trusuww vt to the evnesras se tne Camoney. l t if your usesary wage emaasts $23140, veu are arrttians to me mesanum Tamemarory Dimeinty in-IV. Aeneissue of knemmassev Pevees: ownnery of $154.00 one wess, cmummunone en the em Nat sev stier sneorv. If me wort reemens ineury remarts m noortunissam or more men 21 core of samanistv permarro =da mmmerne the is fun any of simodriv. If veia semeserty rematis in eser erne for oaer vise vers or veu home tune evner reee vaars, von west on oss urwoorary simedity et the rem eurventry in effect. Thw aseses CWHY to ensurums on or efter 1.t.7$. Permariarrt sisW630tV *t see et true rem of $7CfG Wr tuumE. I
- v. Renmodeissen: Effectrve Januarv 1.1975. tne enosever must provuse e ieneseliteten croywn for en, amoseven waere tne trasmens onvoc an asemme me Caneany yest the arnoeeves w.at ne unenes te mm to nie umass ans customerv osometaan et tne tune of .n-tury, on e esmiensert nema.
The orografn ortrweges services assi as wesetsonst swesnaEasn. csuneeserig. M. irumudwg on qrie-,ee ;tresnerig wem PG&E.run olesomem The Can. n==-ww to russere me miurus amonovas to ma tsene omosovaunt, wasen e not conf 6nes is _c_. omnv ==orme e aantuncnon wren tne CasHerme Rer.enientstaan Eurums. ' . VI. Demen Senastes if veur witurv gessu en esem ans veu nees a teinsiv oserusent sous, me een of 350.000A0 is me mensviurn
-. mener en Mron, tres arusimurn e 350.00040. There es esse a monstet, ensart si camms enerving a soeum ans one er more -
momenien aunes assousunse et 31.900.00. la comme of osmas _
- u. the seem asseAt unu as e esm soums to 1our tenue true ammant annusty aerosms a me massert of me _ _ not to ammeur 20 nrirt 'in vtL Purener lasmsammesas if vos wesi hariner informeten en veur ourtesnar cams,in sesstion to wnst your susarmuer nas orerness een1mst me Werumrs' Comammention Clasvu Secoon (4153 791-4211 f.msnnen 3171.
infoemenon ans Amstense Offlamre nessus e the otremas of tne Olvemen of lacsuertaf Asesema, warmers Camaanseren Assess Sours are a hatner seneres of saformarsen ens services. The Werners' Compenssuen A&ammes Beers is ttie firuel ernster of camme to l wormers cameensursen . O
e t,,.e . ,, - ,. ,n r -.m. m et.e = _ _ - - Wu-e= *e mee . me N st gg year asumma spyumumb t i b e e 6 was wumrewme e eroves traumast misesse to Lamar Case sacean 4400 met: M Mh MM E U gee rumne usus aceums of maan trummag servumman er %umaftv.aus 34 WHrun 9 m esve esteammig nuuns ensnessman scan marme e armee remmet a tres em pupvW W dnGM (1) The e and assums of inesrus enamsves (2) The emaarves*e enessus nummrv a estamies Dv tree --- 133 Ptnesagm on .._ , MI The seemmerne omsnonne rumorems try true enmasves: S The OAlsuumE GabarWB,summe apud euruman af tremenest: W ff ammreareme, see amanuma rw emme: (7) An omsman a em asemeur w surwisimme casamutty e e se _ - ame, if semese,an aumenmus of It s eusset: _ p ame :smag swervaus a tres eene of latwv. (ej At ummmmmuneinvemms aseig ameNo trumumswe marnet greyes rumoris a tne emmesve ans, SWOmasenv.temart preNummTV to tfte assummever wwumet ut The amuseves's assumaan ammune rummm to immrus (23 The asnessveurs suuntaan remare non er ne a musimers: (31 _ er margurv is inelemums or . _. _ _ _, WB The amensves's senesteen Damamme gewussent asas _ _ , , Sl The enseves's curistion unmegne a orevous, w-- ' symftamsse arousso: twee l remert snad ampumun e amenmaust of true greemans oowes of treatmevernmeares .f may, j av tems anmusme: tGB The eunussven e th te anmurter gnvocume for - 1 ^ (7) The emaneves _ , rueuena amartiene amarearmes .._.. _ . l l l f pw -m e - __ 6- M 9
L . '. . l i . l J
. e i m. tne e factPIC GAR ans ELSCTmc COASANY Emotover's Resort of Ccasoscones Irgury or Lttaines i
' CCNFIDENTI AL-kr f.ise av Cm oany A rroraevs ouvosaan !.. GENeRALOppiCE Ge 45JeepiAL CosWT1buCTicas 1
- e. .
acA ..c...ca
- w. m.- ...
i AC".awseT s.as . .sr s w.u. g g", Acc.;osper ataca? wasosa
. . . . w= . . . u * = * .u . __ g 4- -
7 T- -
-. __2.... i. .s j
.wo .,.4: _ _ _ ~. . . _ .o s
..e
.nw..es 48 .t 8.
- w. .
(
".N=.as me
.r c.
a.
. . ae.n.e e. me.s ma
. .w e
.n.e m u.
.l
...w.
..i. .
- 4. E2l "
l '**- etmaas oc
=o m m l!1. O N e CDLwase
! PACnPlc asu.a GA8 smetAND s m ram.cww.c4E.LEC'T74l': esses CCasPANY PUSUC U11UTY-Gas & Bearse l ,
~ us =
l i. 2.273 si w sm. 2m
. . _-a c.a. . 4. y_ _ . . _- -
! 7 007 -P 99 e
- i
.***** I 7..**'*****'** '
- 6. ' *"* No n g 1R a.**"""*'" = -- .
,g,- ! " i
. ' '** * " " 12.J*- - 3*" '"
,'g*s" l10'i= l 11' ** ! '
o CMALE CFEMALK ':*'*' -
* :- - w .a.
a ha=*= S n .e. wee.
; .e s
==='**
l h "-*'*"'*G- * * '*- ge, .s_-_ yI.A RS e _ = _ _ I n r .. . . _ " - - ~ g,, . 9 C WJb'""" OCo %w ACii . "." E .
* * - * *'s==' =='=. wi a.ma ==
14 , . I"."." e_- l15.*CV13 CNC s
'"' f 2l'"." 7 . e.
.e ,
g . c. -n
'
- T7.--==-"-'==*=='= n ea si
.u ---
e es.,+ avv 15/*"'***=="***"""==-- g.. e . ei.es j g,. . . _ __ _
.ssus. .
* - ~ '
A " ***
. 20.'*******"*"**-- l m.#
e,
'er S .u.s
- a. m u. =e us 3 a g 1.u. . o { gem -
g3.m .c , .s, a 8 MOURS 1 CYt5 o_ _ CNC .,
.a . = . - ,..
. _ _ . y mI . ....: -
s g CVC5-e =- CNC w-._-- QYS5
- n= , y , , , ,
73,s. .- Ovf 5 -o.- CNC . .. se _ . - _ = 1 q Fe re e sres . ., g .u s es e
**ie g of see remert : w an aumemen at unassw.
.ime. PAC FIC GAS at ELEC"Mtdll COMPANY I
. 9e
. . w eeemrt er nuv m= wee to se sans av en eso. ....
misver y annsrer sv mis cesnar meel as annesmess as e.senner -e anv as.wierv arenesang assure trie Aos ossi W .$sf*W. M & CassisOset . , , ,, me, ,,,,r, ha,, Acomens Sears *" Tsurwosse M1-dE'!1 8L_: 3171 a w g w gan taf se l k
I
)
i
.Y Report = Date ; 19-Dr.
Kinciv Srve to oearer, Mr.lMs. medicaJ attention, ed forward a complete detailed report immeci. acety to Manager. Safety Healtn and Cams Deot. 245 Market Street. San Francaco.94106. Your eills saould be itemized ed all bills and reports rendered in tritHicate. PACIFIC GAS AND ELECTRIC COMP ANY By l*** !
.. .. tesv s,se "er. . r-= . m PLEASE COMPLETE AND RETlJRN TO LMPt.OYEE tsaart.ovas wust nava conspuTto caso to a Tuan to woman Pacific Gas and Electric Co.. Date ,19 Mr.lMs.
Occupanon Report e Etnosovec Bv I ** * ! Divesson. Intured at . .T: on ,19 C aenarn to us .ers .mmseavy C ween 9ed .erm uned C unaws a . era unal C Essecoons er Gnwoudens C tearn Aess. - Timme C Dissnersus from eumenes Sigued -- 40.
, 0
l
"'"**"**"""*~
[ co<ifio.nti.: J For Use by Company Attorneys Only REPORT OF AUTOMOBILE ACCIDENT
" * " " " "
- j
@ OTHER,,,0 RIVER Nerne O ^~
"* ~
i-,. s ..
** ** ACCIDENT REPORT NUMSER . .-
Ope <ator's Date of State Alphe Year Soc. Number [Orv Use Birth Lic. No. Insurance Company
@ OTHER VEHICLE OR PROPERTY OWNER Name Phone No.
S Address Color Type Year *. ic. No. Venicle Make PwCNE No mecem nitats [.T."t'.$ NAME ADOntss C C C
- 1. -
- O C PASSENGERS C IN OTHER 2- C ',
VEHICLES. 3 -
~ c CITNESSES. ,
C C 7 OR INJURED PERSONS 5 C C C 6 a PHONE No. vYs ou NAus Acomiss C C 1
- M P ,
- 1. " ~ ~
PASSENGERS 2' O C C IN COMPANY VEHICLE 3- C C ! 4 c- t - on ... .. -
,,,@,,, .. m.
'n - ,s. .
~ ic.,
y,o,tgy,p .i._.,_.=.__... _ on at Other vencie was C stopped C moving ,
'- it on at Corr.pany vehicle was O stopped C moving ,
OESCRIPTION OF ACCIDENT ._ Compl ote detedt
,e
'I
- ie - . . . a.i n.m i _ _ ;
accident _ D'SCf'be weather. road and light conditions occurred Number of seet belts in use at time of accicent Number of seat belts in Corepany veic6e ine.cate om.cn invest gating agenev will prepare a report- O cwP O She." C c.m Pei.ce C None C ome Coetif known or estire. ate DESCRIBE DAMAGE 70. C Unoer $50( Other Vehicletsi or Procerty C Over $50C h VEHICLE S a o,,, or sotimato s3oor DESCRIBE DAM AGE TO. O Company Vehicle C Lesse/ Rental Vehicle C Personal Vencle Cost if known
& C Unoer $10t PROPERTY OAMAGE C Over $10C S C Over $50C we., onotes tamen of acciavat sceae ano cemenet O vee O No Home Accrees Company Phone No Company Onver Age Occupation Reporting to Local Office at COMPANY DRIVER Class Empirstion Dete g Cal. Drtver's Lc. No.
U"on or G O Dept. Danct N_ wat CFOR T 05 Lec. No Tvoe Year Ooometer Renoing l Ven cle No Lic. N3. Driver's Sqnature Cou ntersagneri - Company Phone No. _ of this report 19
._r _ ,, ,,,,.3,s,.m, _ i.mo,,,. . s .... , e l
_ .r ._ . . . s 1 l
I ? l lil5TRUCT10lls All acesdents arising out of the operet6on of Company owned, lease'd or rented vehicles, as well as employee-owned leased or r ( l veh*fes used on Company business. must be reported to the Superwsor en charge immediately. Allinjunes to persons or serious l osmage to property of others involving above vefucias must be reported to the Safety. Health and Claims Department Field Investiga or, ef he is unavailable, the General Office Safety. Health and Claims Department. Such notification shall be by the f astest means l communication and this report prepared the same day Answer each question fully When blank spaces are not sufficient for full I statements, answer each on separate sheets are attach hereto. I PREPARE A SKETCH OF ACCIDFNT BELOW: Sketch should show- ! 1) POSITION OF VEHICLES. BUILDINGS. STRUCTURES. ETC.
- 2) STREET NAMES. DIRECTIONS OF TRAVEL STOP OR WARNING SIGNS ETC.
30.ANE WIDTHS. SKID MARKS. POINT OF IMPACT, INCLUDING MEASUREMENTS AS APPROPRIATE! O 1 l l 1 I 1 1
e e 9 t e-i =
.4 i
e-r = U W
=
4 m G w- b 8E S 5 t y Em E Ul E 5e 5E
- v- -
EE E 5 2E = WE @c E @ f C E 5
=
=
5
=
5 5
=t w
e 4 8 2
= t.- a N E w e g w a -
g N s a, a
=
=
w b 4 Q@
- w
e C C E E1h~Y f ' "=A O !
~
! C' G A S A .N. ~ C E 1.E C 7 E-.E C
- C- 4 - ::Aa:.: c2mes -c ;s. =>.x 555.11
.. = 0. 1: 2 !! . A..a 8sa:- Cm.::. : 3::: . (!:51
. ?..
z=:.w
- . 2:=m?.
w-Daar Dr. Tnank you f5r being one of our panel enysicians that true: cur emoicyees. Our prir1 y g:al is to provida arrelayees wne sustain indust-ial injurias Your recuiringmecical at antien with pec:n;;, firs:-class : ta=ent. assisunca in :nts encaavor is appreciatad. While the nuc::er of emolcyees ma: Thers is an area cf c:ncarn te us. ricuire : ta=an by a pnysician has rs::ained su:le er in scue casas esclinsc, :na nc-:ar of 21sacling injurits recui-ing tira away '-c::: .scrt, - i.a., 1:s: time injuries, has dramatically incnasec. We believe that s=me of :nis time away frem wert sign: ;cssibly be avoided (modified) duty or dask-ty;a wort ert :::cm if tne availamility widely known. of lign:Some pnysicians have statad that in some casus the pation: will rescene more rapidly n trea: ment if kect busy in a light-duty cacacity. P-ccuctive, lign:-outy assignments art almes: always availasle for ec:cicyees raiensac fcr wort within ma c:acical restrictions esublisned by the physician. It our solicy Oc have an injured emcloyes accamcanied by athere Should sucerviser be anyor cuss-outr re:rtsantative
- n accu: on =aorfirst
=t availantli:y typedoc =r's duty of lign: visit. : a: can ca provicac, as or sne will be anle to answer for us.
Should you have any cuestions cur amoloyees' welfare is our main c=ncarn. a:cu: our program, I will be glac to call on you at your ccavenienca. Sincarely. R. C. THORN 3GRY RC~:kg: l
, 0 -
DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT Company Panel of Physjcians, Ambulances, and Hospijals Servino the Immediate Area Around Diablo Canyon _ . Ambulance _2 Remarks Phone Address _ hime Radiation Exposurt 358 Santa Rosa Patients San Luls Ambulance San Luis Obispo Service CENTRAL DISPATCH 135 South Halcyon Rd. Five Cities Ambulance
- Arroyo Grande Service j
CENTRAL DISPATCH i 2315 Bayview Heights South Bay Fire / Ambulance Los Osos t CENTRAL DISPATCH i l 510 Bonita Bay Ambulance Morro Bay , i Hosfftais Radiation Exposurc 1911 Johnson Avenue l , Patients-Extern French Hospital San Luis Obispo , Defib. Equip. {. i External 5,ierra Vista Hospital 1010 Murray Avenue - Defibrillation San Luis Obispo ! Equipped (?.0 minutes to clear for helicopter) l
. External 345 South Halcyon Rd Defibrillation
' Arroyo Grande Community Arroyo Grande l1 Equipment Hospital and Medical Center i
DC0152 8VII
/
/ :
l Physicans_ ' c San Luis Medical Clinic 1235 Osos Street San Luis Obispo
- Industrial Injury P.ichard E. Fleming 1235 Osos Street Treatment
" San Luis Obispo
- . i Eye .'
.T. A. Beresky 100 Casa Street San Luis Obispo Physicians' Exchange s
- 1. This list extracted from Standard Practice No. 251.1-1 Panel of Physicians, Ambulances, and Hospitals, Coast Valleys Division, dated 6/16/82.
- 2. See also EP OR-1 "Offsite Support and Assistance" for Air Ambulance and Medical Support.
l l
'. I DC0152- 9VII 1 h
l 4 ^, . - , . . , - -- , ..
PACIFIC GAS AND ELECTRIC COMPANY SAFETY, HEALTH, AND CLAIMS DEPARTHENT PANEL OF PHYSICIA,NS, AMBULANCES, AND HOSP COAST VALLEYS DIVISION . f SP 251.1-1 Page 2 _ 4-Issued: 6/16/82 TELEPH0fiE SERVICE ADDRESS TOWN ARROYO GRANDE f Physicians's Exchange Ambul. 135 South Halcyon Road Five Cities Ambulance Service Ambul. CENTRAL DISPATCH Hosp. DEF 34S South Halcyon Road A.G. Community Hospital and Medical Center I ATASCADER0_ ; See PASO ROBLES Doctors i ', Ambul. 3886 El Camino Real North County Medical l i Services (Emergency , Medical Technician) Actul . CENTRAL DISPATCH lHosp DEF 1500 Las Tablas, . Twin Cities Community Templeton Hospital : BAYWOOD PARK *- LOS OSOS .bul 2315 Bayview Heights South Bay Fire / Ambulance 'fnbul _._.. -l CENTRAL DISPATCH
- Industrial Injury Treatment I - Preemployment Physical Examinations
' E EYE Eye Injuries
- Paramedic Services
', kj PM - Hospital Equipped with External Defibrillators
- > "DEF" - Willing to Fly
,.1
- s
'{ **
- Helicopter Landing Facility Available
- Radiation Exposure Incidents
~
RAD _( i
~
DC0152- 10VII
ch -:; y y : ; % ; G M 'i t # ~
?
, l' PACIFIC GAS AND ELECTRIC COMPANY \
SAFETY, HEA1.TH,
\
AND CLAIMS DEPARTMENT ~ PANEL OF PHYSICI/NS, AMBULANCES, A'iD HOSPITALS
\
# C0AST VALLEYS DIVISION 1
SP 251.1-1 '
, .i- Page 2 Issued: 6/16/82 \
_ TOWN ' ADDRESS TELEPHONE SERVICE ARROYO GRANDE Physicians's Exchange ' Five Cities Ambulance 135 South Halcyon Road "I* Service CENTRAL DISPATCH "I* A.G. Community Hospital 345 South Halcyon Road H sp. DEF and Medical Center ATASCADERO Doctors See PASO ROBLES North County Medical 3886 El Camino Real j Ambul. Services (Emergency Medical Technician) ,! CENTRAL DISPATCH "I* Twin Cities Corm: unity 1500 Las Tablas, H sp DEF Hospital Templeton - BAYWOOD PARK '- LOS 0505 South Bay Fire / Ambulance 2315 Bayview Heights " CENTRAL DISPATCH u1 I - Industrial Injury Treatment E
- Preemployment Physical Examinations EYE - Eye Injuries PM
- Paramedic Services "DEF"
* - Hospital Equipped with External Defibrillators
** - Willing to Fly RAD
- Helicopter Landing Facility Available
- Radiation Exposure Incidents
\
DC0lS2 10VII ! e _ ____ ___ _-- i
L, L-- tssucc.
. Hospitals ~
t SP 251'.1 Panel of Physicians, knbulances Qnd l Coast Valleys Division . SERVICE TELEPHONE ADDRESS ;, l pin
- x, Ambul
. f CAMBRIA ..
1460 Main Street f !Cambria Ambulance 'Ambul Service i j CENTRAL DISPATCH .i i Ambul CARMEL (AreaCode408) , Carmel Fire House, ! Red Cross Ambulance 6th & Delores Streets l f Hosp DEF [ Cannel & Pacific Grove Comunity Hospital of Highway the Monterey Peninsula l CARMEL VALLEY (Area Code 408) I-E Village Medical Center C. Winter Van Horn I-E ' l 10 Del Fino Place I Paulino E. Tocchet I CASTROVILLE (Area Code 408) I-E 10349 Merrit Street I-E i Donald M. Crosiar 11272 Merrit Street Joseph L. Kirch 10349 Merrit Street Bert Clair Eliason i I-E HOLLISTER (Area Code 408) I-E 390 Seventh Street N.L. Currie 931 Sunset Drive . Ambul Martin M. Bress ; 328 Four,th Street Stephens & Poletti Hosp DEF Ambulance 911 Sunset Drive Hazel Hawkins Hospital I-E KING CITY (Area Code 408) ! 210 Canal Street ) i Duane F. Hyde ! l Ambul 124 North Second Street Hosp DEF South County Ambulance 300 Canal Street George L. Mee Memorial . Hospital S DC0152 11VII
r.rs
- Issuca: 6/16/SZ SP 251.1 Panel of Physicians, Ambulances and Hospitals
( -- Coast Valleys Division . i SERVICE _ TELEPHONE _ ADORESS TOWN : LOMPOC_ (Area Code 805) Ambul Cornunity Ambulance 410 East Locust - Service Hosp DEF 508 East Hickory Avenue-(empocHospitalDistrict
' 1 LOS 0505_ (Area Code 805) Ambul Bayview Height's South Bay Fire Department / Ambulance CENTRAL DISPATCH MONTEREY (Area Code 408) 1-E 464 Pacific Street I-E W.A. Carnazzo 1010 Cass Street I-E Nello P. Torri 172 El Dorado Eye Howard Press 880 Cass Street Eye John J. D' Attilio 2010 Cass Street George S. Campion :
Physician's Exchange Ambul 561 Redwood Avenue f Peninsula Medics Sand City ; i Hosp DEF 576 Hartnell Street Eskaton Health Care Center (24-hour Emergency Service) Hosp DEF Peninsula Coninunity Cannel & Pacific Grove Highway, Carmel MORRO BAY (Area Code 805) _ Antul 510 Bonita Bay Ambulance 'I DC0152 12Vil
s -- __ - _ w ,,,
-_____m___.c Safety, Health and Claims Personnel to be Contacted for Reporting of Injuries,at Diablo Canyon Page 2 of 2 Non-Errployee injuries C. O. Schreil, San Luis Obispc office)
(office) (home) _ ;
; If he cannot be reached, contact one of the folicwing in order of
.. preference-During working hours:
- 1. John C. Echols < !
- 2. Doug G. Keeler
- 3. George G. Perry (collection only)
After working hours on Monday through 8:00 a.m. on Friday, except holidays:
- 1. John C. Echols Pleasant Hill
- 2. Douglas G. Keeler Concord
- 3. John C. Vocke Layfayette
- 4. Donald A. Rushton San Mateo
- 5. William H. Bingaman Novato '
- 6. E. Anthony Giudici San Carlos '
- 7. J. Alec McCorquodale San Ramon
- 8. Stanley W. Johnson Fairfield
- 9. George G. Perry Hayward (collectio.n only)
- 10. Bruce P. Sadler Belmont After 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." l DC0152 71X
J. ,T._... _ _ .- __1..,___. _- . l r . . 1/83 PACIFIC GAS AND ELECTRIC COMPANY Page 1 of 2 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DI ABLO CANYON POWER PLANT UNIT N05.1 AND 2 Safety, Health and Claims Personnel to be y 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: T. B. Honey (If Mr. Honey is not available, the person answering the telephone will take the message and notify Mr. Honey or any other parties necessary in the Safety, Health and Claims Department). , Any Other Time: l Report to one of the persons on the following list, trying each in order until one is contacted: O 1. T. B. Honey Pinole San Francisco
- 2. A. Thomas
- 3. C. B. Powell San Francisco
- 4. P. S. Benitez San Rafael
- 5. T. G. Scott Oakland
- 6. L. Lasagna Albany
- 7. C. W. Allen San Francisco
- 8. B. L. Wade '
Larkspur
~
- 9. J. A. Glime Danville .'
- 10. J. C. Vocke Lafayette
- 11. W. A. Hutchison San Carlos
- 12. M. C. Dolan Oakland
- 13. M. W. Johnson Walnut Creek
- 14. R. W. Hall Richomod.
- 15. 1. H. Crawford Hercules
- 16. R. G. Schumaker El Granada
. , ' 17. R. D. Fagg San Rafael
- 18. P. C. Boettcher Moraga
- 19. H. W.' Reynolds Sunnyvale
- 20. B. P. Sadler Belmont lThis listing extracted from Safet'y, Health, and Claims memo regarding Personnel to be Contacted for Reporting of Accidents, dated 01/13/83.
( DC0152 61X
- u.-- . -- - . .- -- _ _- - - - - -- - - -
I* . Page 7 SP 251.1 !ssued: 6/16/82 ' Panel of Physicians, Ambulances and Hospitals , ( Coast Valleys Division ADDRESS TEIrrh0NE SERVICE TOWN SOLVANG - - - F.A. Pedersen 2030 Viborg Road lI-E W.B. Van Valin 2030 Viborg Road 1-E Physicians' Exchange Santa Maria I CiastAmbulance 361 Alisal Road Ambul Service i Santa Ynez Valley 700 Alamo Pintado Rd. Hosp DEF l Hospital TEMPLETON Peter S. Davis 1400 Las Tablas, I-E Suite 2 ] Willard Osibin 1400 Las Tablas 1-E
*R.A. Greenman 1400 Las Tablas E l CENTRAL DISPATCH Ambul Twin Cities Hospital 1500 Las Tablas Hosp DEF G
WATSONVILLE, l
*E.H. Eiskamp 850 Freedom Boulevard I-E I P.K. Gilman 850 Freedom Boulevard 1-E David E. Bushman 30 Brennan Street I-E Douglas A. Liddicoat 274 Green Valley Road Eye W. Webb Wilson 272 Green Valley Road Eye Physicians' Exchange A-1 Watsonville 1046A Freedom Boulevard Ambul Ambulance j "Watsonville Comunity Green Valley Road at Hosp DEF t Hospital Holohan Road l
k i l l DC0152 15VII
.. _. _._. _ ._~ _ _ _ . _ . - - - - - - - - -
f . SP 251.1
- Page 6 Panel of Physicians, Ambulances and Hospitals Issued: 6/16/82 Coast Valleys Division TOWN ADDRESS TELEPHONE SERVICE SANTA BARBARA St. Francis Hospital 601 East Micheltorena Hosp DEF S/INTAMARIA
'Jules Bertero 201 West Cook Street I-E
- Harry K. Lienke 217 East Fesler 1-E
- Donald E. Reiner 1414-0 South Miller St. 'I D.D. Shepard 1414 South Miller St. : Eye Industrial Medical Group of Santa Maria Valley Dr. Betty Suits Tibbs '3130 Skyway Drive, I-E
. Suite 702 f 5 Dr. William J. Tibbs 3130 Skyway Drive, : I-E Suite 702 l Physicians' Exchange 911 Ambulance Service j PM Santa Maria Ambulance 602 East Cook Street '. Ambul Service Police Department Santa Maria Ambul (For Emergency Only) I, Marian Hospital 1400 East Church St. i Hosp DEF Valley Comunity 505 East Plaza Hosp Hospital SOLEDAD Soledad Ambulance Soledad Ambul Service (County Emergency Services) G G - l DC0lS2 14VII
SP 251.1 Page 5 Panel of Physicians, Ambulances and Hospitals Issued: 6/16/82 Coast Valleys Division TOWN ADDRESS TELEPHONE SERVICE h _ PASO ROBLES (Area Code 805)
- Stanley J. Kirk 1305 Vine Street I-E Physicians' Exchange Professior,al Ambulance 1035 Vine Street Ambul Sirvice CENTRAL DISPATCH Ambul Twin Cities Hospital 1500 Las Tablas Road Hosp DEF Templeton SALINAS (Area Code 408) '
W.H. Lawler, Jr. 110 John Street I-E Howard C. Miles 535 East Romie Lane I-E Stanley G. Parker 535 East Romie Lane I-E George J. Hinn 505 East Romie Lane I i Glenn H. Smith 230 San Jose Street Eye l E.0. Dong 535 East Romie Lane Eye Physicians' Exchange A-1 Ambulance Service 241 East Market Street Hosp DEF ' Salinas Valley 450 East Romie Lane Hosp DEF Memorial Hospital SAN LUIS OBISPO (Area Code 805)
- Richard E. Fleming 1235 Osos Street I-E T.A. Beresky 100 Casa Street Eye !
i SLO Medical Clinic 1235 Osos Street Physicians' Exchange ' San luis Ambulance 385 Santa Rosa Ambul RAD Service l CENTRAL DISPATCH Ambul french Hospital 1911 Johnson Avenue Hosp DEF RAD l 1
" Sierra Vista Hospital 1010 Murray Avenue Hosp DEF (20 Minutes to clear i I
for chopper) . DC0152 13VII
- _ _ _ - _ _ _ - _ _ - _ _ _ _ _ _ - _ _ _ _ _ . ._ b
o Page 1 of 1 PACIFIC GAS AND ELECTRIC CCMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS m DIABLO CANYON POWER PLANT UNITS NOS. I ant 2 ) TITLE: EMLRGENCY PROCEDURE NOTIFICATION INSTRUCTIONS APPENDIX Z i
*. 1.
When this emergency procedure has been implemented for injuries or illnesses , occurring within the site boundary, and upon direction from the Shift ' Foreman, proceed as follows:
*a. Notify the Plant Manager, Plant Superintendent, Supervisor of Chemistry and Radiation Protection or their designated alternates.
- b. Notify the Compensation Claims Representative, Department of Safety Health and Claims, per the attached list of personnel.
*c. Designate this event a significant event if, in the opinion of the Shift Foreman, the injury will require treatment or observation which will last longer than 48 hours, or in any case of a fatality. Nctify the NRC Bethesda Operation's Center within one hour, as a minimum, using the red phone in the Control Room. Gather sufficient information from all sources so that the phone call is meaningful. Refer to Operating Procedure 0-4 " Operating Order (One hour report requirements to NRC)" for a suggested fonnat for reporting. Notify the NRC that your call is pursuant to 10 CFR Part 50.72 (Notification of Significant f Events).
pd
*d. In addition to the notification perfonned above, also notify the f following if NRC is notified, Supervising Nuclear Generation Engineer \
(Personnel and Environmental Safety) or his alternate in the Department of Nuclear Plant Operation:
"Mr. W. H. Fujimoto PGandE Plant Extension jiome K)TE: If the above General Office personnel cannot be promptly '
reached, request the Systems Dispatcher to contact alternate personnel.
- 2. When this emergency procedure has been implemented for injuries occurring outside the site boundary such as along the plant access road, and upon direction from the Shift Foreman, proceed as follows:
a
*a. Notify the Plant Manager or his designated alternate,
- b. Notify the Compensation Claims Representative, Department of Safety Health and Claims, per the attached list of personnel.
J' . DC0152 SIX
l 2 NwsER EP M-2 LU)(G si E Pacific Gas and Electric Company REVISION 9 m DATE 7/5/83 i DEPARTMENT OF NUCLEAR PLANT OPERATIONS 1 AND 2 PAGE lOF 3 DIABLO CANYON POWER PLANT UNIT NO(S) EMERGENCY PROCEDURE f o NONEMPLOYEE INJURY OR ILLNESS (THIRD PARTY) TITLE: V
~f* APPROVED: YOY
DATE
<T MANA ER u
l SCOPE ' i This procedure describes the actions which are to be taken in the , 1 event of an ' injury or illness involving a nonemployee which is ' incurred in connection with Company operations either cn or in the vicinity of the plant site. This procedure and changes thereto requires PSRC review. APPLICABILITY This procedure is to be followed for incidents involving non-employees who are on or near the site at the request of the Nuclear Plant Operations Department (such as a Xerox serviceman). In the event of an incident involving)other a construction worker , perfonnnon-employees only the asterisked at (*) or steps near in the site (such as this procedure. IMMEDIATE ACTIONS The employee (s) who are at the scene shall:
*1. Render all necessary first aid.
*2. Notify the control room (Shift Foreman) as soon as practical.
SUBSEQUENT ACTIONS The Shift Foreman shall direct all subsequent actions until relieved by)the it . SuchLong Tenn actions Siteinclude should Emergency Coordinator (if the situation warrants the following:
*1; Sound emergency signal, code override, or other general warning signal to clear the area if the situation warrants it. l
*2. Dispatch additional first aid rsonnel such as the project construction EMT to the scene of the injury or illness if required. Personne who have not been instructed to provide assistance at the scene should remain on their jobs and stay clear of the affected area.
\D U DC0A10 IX
~ ~
l
=
N R EP M-2 DIABLO CANYON POWER PLANT UNIT NO(S) . 1 AND 2 DATE 7/5/83 O TITLE: NONEMPLOYEE INJURY OR ILLNESS (THIRD PARTY) PAGE 2 OF 3 . i *3. Call an ambulance or physician if the situation warrants it. The
.; practices which are to be followed if this step is necessary are given in the following section of this procedure.
- 4. Secure the names and addresses of all witnesses (both Company and noncompany).
*5. Perfom the notifications required by Appendix Z.
- 6. Ari accident report should be completed as soon as practical either on Fom 62-6226 " Report of Miscellaneous Accident," or Form 62-4542, " Report of Automobile Accident," as is appropriate.
The accident report should be forwarded to the plant clerk for processing. POLICIES TO BE FOLLOWED WHEN REQUESTING OUTSIDE ASSISTANCE If a third party requires medical care, the following policies should be followed by Company personnel who secure assistance.
- 1. If the injured or ill individual is in a condition where he can speak for himself, call the physician which he requests. If an ambulance is required, call the ambulance which he requests.
- 2. If the injured or ill individual cannot speak for himself, but friends, relatives, or his employer are present, leave the matter of his care to them.
- 3. If an injured or ill individual cannot speak fer himself, and friends, relatives, or employer, or public officials are not present or will not take change, call a local ambulance service and have the injured or ill person sent to the San Luis Obispo General Hospital for treatment. .
- 4. Whenever a physician or an ambulance is called, it should be clearly stated by the employee making the call that this is not Company responsibility and is made not on behalf of the Company but of the injured or ill person or for his benefit, or until' family, friends, employer, or public officials can take charge.
- 5. An injured or ill third party should only be transported in a Company vehicle in the event of an extreme emergency when the delay associated with securing an ambulance might result in a significant deterioration of the injured person's condition.
O DC0A10 2X
' N R M-2 1 AND 2 p DIABLO CANYON POWER PLANT UMT NO(S) , DATE 7/5/83 ' NONEMPLOYEE INJURY OR ILLNESS (THIRD PARTY) TITLE. g POLICIES TO BE FOLLOWED IN THE EVENT OF RADI0 ACTIVE CONTAMINATION 4 If the injured or ill individual is significantly contaminated with radioactive material or overexposed, the matter will be treated in the same manner as would a similar incident involving a Company employee (see Emergency Procedure R-1 " Personnel Injury (Radiologically related) and/or Overexposure). REFERENCES
- 1. PGandE Standard Practice 250.
- 2. PGandE Claims Department Circular Letter No. 19, 10/1/49.
- 3. NRC Infonnation Notice 80-06, " Notification of Significant Events."
ATTACHMENTS
- 1. Form 62-6226, " Report of Hiscellaneous Accident."
- 2. Form 62-4542, " Report of Automobile Accident."
- 3. Appendix Z, Emergency Procedure Nctification Instructions
,O -
DC0A10 3X t
~ . _ . . .
.. PGwE REPORT OF MISCELLANEOUS ACCIDENT
* * " ~~
CONFIDENTIAL POR USE BY COtSPAMt' ATTORNEYS 300LY
% AsPonY NuMSEm
'988 8'E "- Drw wSE 1 ene macTiec FEMe umTWt CDG8 WI I
{ *
- ' s a a a EIEa'v?#EP:nL*.EE e,
~
- 1. LO,CATIONAcCioEuT:
''"T****""***""*M"""'"""~""*#
0 " ' ~ ' ' * * ' i
*""'-o^'-*' I CATE CCMPANY DATE sours t 4. wAS NOTmEo:
b Or ACCIDENT: I 3. Teis ._
- 5. isCioesT saiso saposTeo: O CAR.POtE CTRip-*Att C riRE C EtscTRic ccNTAcT i C EXPLOSION O MOTOR SURNOUT C STORM C OtG-4N OOTHER REPORT: rt m, use e,.orm man at sw wm
- ernmensory inseen or =+=a~m nwormaman.
I i
#%E=J^.e* O YES O NO N'"T^AN*. NcWP O YES O NO '
NAME ANO ADORE 55 OF
,,,gg, p g,yg ,,gg ._
t INJumED PE7tSON 2. PERSON ,,,,, CAMAGlNG COMPANY pmCPWITY OR 10wNER OF DAMAGED PROPERTY OTHER THAN PG4E C sussa assume cnv paft =-. ;- ammann PmOpstTY .... .. .. .... ...... acongas CFv 57 aft 8s'oet amassem (INCH". ATE NUMGER IN SQUAM) samme
.w===eas-- an sve ==== e=e .=== a o== == == s== - -
enemens assontant - nea y ass ===
~
PGaret EMPLOYEE'S NAME. DEPT. PHONE NUMBER NVEE3 NA84. ACCESS. PHONE NUMSER
' IF YES. ESTIMATE ESTIMATED TOTAt DOLLAR WAS THERE ANY DAMAGE a TO PROPERTY OF OTHERS7 TOTAL DOLLAR a DAMAGE TO PGandE 5. C YES O NO C UNKNOWN DAMAGE.
- GoCOMPANY PROPERTY t Q sus ouvinct
=ane or am N u'ut C umse o.
Q couwrv om o- ee 11. 6w~, %c.&- gyms eNo l los
. _ ~ _ .
% % =g,__ ,,_,
l, _ Ostenct 4 f0use OAft g M ennae s=ceia ; m.oes ia Tg cg,g, == AC. oc , mfiore aft iT9s no aCC0Wurt een , en g *1ae op eW me oc ==.
- - ~ - - - -
= = _ = . - _._ __:. ;._- e- -- - -
. eee<
#e . . es.
.- __m.______ . _ _ _ _ _ _ _ _ _ . . _ _
~ e ~ ~ .~ l g,,y,,,,,, l For Use by Comp:ny Attorneys Only
=^""'**"* REPORT OF AUTOM,OBILE ACCIDENT
, h OTHER ORIVER Name Addreas is- . c.ev. s .
; *
- ACCIDENT REPORT NUMBER -
Operator.s Year Sec. Number .Osw. Use Date of State Alphe Birth L ac. No. insurance Cornpeny l
. @ OTHER VEHICLE OR PROPERTY OWNER
- N.m.
Addregs Phone No. Lie. No. Color Type Year _ Vehicle Mak e isuJu t paesecan witviess on s.8'T.D L PHONE No. AcomEss Naug C C C
\:/ i. C C C PASSENGERS 2-IN OTHER VEHICLES. 3. C C CITNESSES. 4~ -
- C OR INJURED PERSONS 5. C C C t-PLOvEE 'NJ PHCNE No was e oa 5.ma.cT 6 Naut Acomsss C C D PASSENGERS h 1. C C C
C 2' " " i IN COT PANY C VEHICLE 3- : C .- 4 at Hours. On '*""'"***"""' 5 On "'"* DATE. IME in 'Cdv* L- ,.su. ANO LOCATION at/near -
"*"'""""""**""="**"""'""'*'
0F ACCIOENT **P H on at Otner venicle was C stopped C moving _ at H GhOESCRIPTION Company vehicle was O stopped C movmg on , OF ACC10ENT
~
Complete detseis m .. a .n i._ _.. m occident Describe weather road and light conditions occurred Numbe' of east belts m use at time of accident Number of test belts m Company vehicle ladicate wNea investigatmo agencv will prepare a rooort- C CHe C SeeiH C C ev esiim C Now C omer Cost if known or estimate DESCRIBE DAMAGE TO. C under $50C Other Venicle(s) or Procerty C Over $50C S C ov,r siocc VENtCLE Cost if knowr. or estimate.
& DESCRIBE DAMAGE TO. O Company vehete O Leses/ Rental Vehele O Personai vehici.
C under $10C PROPERTY g o,,, gioc OAMAGE I - 0 Over $50C Were pactos totea of accident sceae end damese? C Yes O No Company Phone No Company Drrver Home Address Age Occupation Reporting to Local Offee et CD' PANY ORfvER Class Empiretion Dete g Cal. Driver's Lc. No. VEHICLE Distnet Department 1.ese or G.O Dept. INFORMATION Type Year Odometer Reeding - vehicie No. Lic. No. Lic. No. Dnver's SWture Company Phone No
^ 19 Counterssener' o' this recort --
{ n....s a c. . soc ..ici o. as- . . .cco - . ,,ggocfg ;g g, m. % i.g;o,cgv
CSTRUCTIONS . j I All accidents arising out of the operation of CompanMwned, leased or rented vehicles, as well as employeo-owned, leased or rented I veh<les used on Company business. must be reported to the Superwsor in charge irnmediately. All injuries to persons or serious i damage to property of others mvolving above vehicles must be reported to the Safety. Health and Claims Copertment Field investigator j or,** he is unavailable the General Office Safety. Health and Claims Department. Such notification shall be by the fastest means of communcation and this report prepared the same day Answer each question fully When blar* spaces are not sufficient for full statements, answer each on separate sheets and attach hereto. PREPARE A SKETCH OF ACCICENT BELOW: Sketch should show: 11 POSITION OF VEHICLES. BUILDINGS. STRUCTURES. ETC.
- 2) STREET NAMES. 01 RECT 10NS OF TRAVEL STOP OR WARNING SIGNS. ETC.
t 34.ANE WIDTHS. SKID MARKS. POINT OF IMPACT. INCLUDING MEASUREMENTS AS APPROPRIATEI i ( O i i l l l
w .
, _ - 1 Page 1 of 2 1 P
PACIFIC GAS AND ELECTRIC COMPANY l DEPARTMENT 0F NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. I ant 2
- TITLE: EMERGDiCY PROCEDURE NOTIFICATION INSTRUCTIONS APPENDIX Z T. When this emergency procedure has been implemented for injuries or illnesses
_? occurring within the site boundary, and upon direction from the Shif t Foreman, proceed as follows:
*a. Notify the Plant Manager, Plant Superintendant, Supervisor of Chemistry and Radiation Protection or their designated alternates.
- b. Contact the Division Field Claims Investigator:
Er. C. O. Schreil l at Office Home If the Field Claims Investigator cannot be promptly reached (at office, home, or on mobile division radio), the General Office Department of Safety, Health, and Claims shall be inrediately notified in his place. A list of appropriate personnel is attached to Emergency Procedure M-1 or notification of appropriate personnel will be handled by the System Dispatcher if requested.
*c. Designate this event a significant event if, in the opinion of the shift forman, the injury will require treatment or observation which will last longer than 48 hours, or in any case of a fatality. Notify the NRC Bethesda Operation's center within one hour, as a minimum, using the red phone in the Control Room. Gather sufficient information from all sources so that the phone call is meaningful. Refer to~
Operating Procedure 0-4 " Operating Order (One Hour Reporting Requirements to tiRC)" for a suggested fonnat for reporting. Notify the NRC that your call is pursuant to 10*CFR Part 50.72 (Notification of Significant Events).
*d. In addition to the notifications perfonned above, also notify the following, if NRC is notified, Supervising Nuclear Generation Engineer (Personnel and Environmental Safety) or his alternate in the Department of Nuclear Plant Operation:
' Mr. W. H. Fuji
'PGandE Plant Ext.
Home ' NOTE: If the above General Office personnel cannot be promptly reached, request the Systems Dispatcher to contact alternate personnel. O (O DC0A10 4VIII l l
Page 2 of 2 ' TITLE: EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS APPENDIX 2 (Continued)
- 2. When this emergency procedure has been implemented for injuries occurring l outside the site boundary such as along the plant access road, ana upon I direction of the Shift Foreman, proceed as follows:
j *a. Notify the Plant Manager or his designated alternate. -
" b. Contact the Division Field Claims Investigator as in 1.b above.
8 O l O DC0A10 SVIII l
.o. . - . . , _ _ - _ . _ . - . , . ._ - - . _ . _ . _ _ _-. _ _ _ _ .
u m ER EP M-4 Pacific Gas and Electric Company UD(Grst3 REVISION 7 DATE 7/6/83 ( DEPARTMENT OF NUCLEAR PLANT OPERATIONS 1 AND 2 PAGE 10F 40 DIABLO CANYON POWER PLANT UNIT NO(S) ENERGENCY PROCEDURE l TITLE: EARTHQUAKE W APPROVED: 7E. d & ~9 b45 DATE MAN" MANAGER
=
n SCOPE g This procedure and changes thereto requires PSRC review. GENERAL Earthquakes affect the plant by producing ground motion which causes plant buildings and equipment to be stressed by induced vibration. This vibration is defined by a spectrum consisting of acceleration, frequency and duration. The values of these parameters used in the design of the Diablo Canyon Plar.t are given in Section 3.7 of the FSAR. Instrumentation at the site neasures and records acceleration frequency and duration, but only the maximum acceleration along three perpendicular axes is indicated. The seismic instrumentation which O a meets the requirements of Technical Specification Table 3.3-7 is described in Appendix 1. Only accelerations of greater than 0.01 g's on the containment base slab are recorded on the triaxial time-history ' accelographs. For purposes of this procedure, earthquakes are classified by the maximum acceleration indicated by the triaxial accelerometer located on the containment base slab. NUREG-0654 NUREG-0654 DCPP Maximum. Earthquake Classification . Action Classification Criteria Level Acceleration (g's) Not detected None Unmeasured to 0.01 Micro in plant. Moderate Detected or felt Unusual event 0.01 to 0.1 in plant Strong Detected Unusual event 0.1 to 0.2 Large Greater than Alert 0.2 to 0.6 OBE levels Greater than Site emergency Greater than 0.6 Major SSE levels DC0036 III ~ - _ _ _ _ _ _
N R EP M-4 DIABLO CANYON P(7#ER PLANT UNIT NO(S) iAND2 DATE 7/6/83 PAGE 2 Op40 TITLE: EGTHQUAKE Unmeasured to moderate earthquakes are expected at Diablo Canyon
; during the life of the plant. A strong, large or major earthquake is
. not' expected. This is based on geological explorations and on the recorded seismic history of the site.
This procedure is to be followed in the event that an earthquake occurs which triggers the recording instruments or is felt in plant. In the event that damage occurs, follow the appropriate Emergency Operating Procedure to mitigate the consequences of the damage first, then follow this procedure for investigation of the plant for further damage and reporting. The operator response is graduated, based on the local acceleration indicated by the Earthquake Force Monitor (EFM) up to 0.5g or on the SMP-1 playback if greater than 0.5g. A verified earthquake undetected by the basic or supplemental monitoring systems but felt "in-plant" should be handled as a moderate earthquake. M: "In-plant" is inside the double fence (Plant Protected Area). MICR0 EARTHQUAKE (Unmeasuredto0.01gl Symptoms O
- 1. The supplemental system (SS), Terra Technology DCS-302, is triggered but the basic system (BS) Kinemetrics SMA-3, is not triggered. This means alam input no.1186 is in alam and alarm input no.1112 is not in alam on PK 13-24 (" Seismic Instr.
System"), a Automatic Actions 4 None expected. Is.ediate Operator Actions None. Subsequent Actions t0TE: Triggering of the Terra Tech Supplemental System alone (that is, the kinemetrics System does not trigger) does not necessarily put the plant in an emergency condition. If ground motion is felt in the plant, discontinue this section and proceed to the " MODERATE EARTHQUAKE" section. O DC0036 211
o N R EP M-4 1 AND 2 O!ABLO CM4 YON POWER PLANT UtMT NCXS) DATE 7/6/83 PAGE 3 op40 l re EARTHQUAKE
; 1. Subsequent Optrator Action a) Detemine if the supplemental system trigger was real or false. False triggers are known to be caused by Circulating l -
Water Pump or Auxiliary Saltwater Pump transients or l i accidental impact of a vehicle or other object near the trigger package or electronic ncise. b) . Notify a Power Production Engineer (Nuclear) by the next working day of the event.
- 2. Subsequent Power Production Engineer Action a) Have the ! & C Dept. record strip charts of the three free field tapes and transmit them to the PPE (Nuclear).
b) Compare the three free field' recordings with each other and with known plant conditions at the time of the event.
~ Detemine if a real earthquake has been recorded. A real earthquake will be evident when all accelerometer channels show similar readings.
c) If the triggering event was false, reset the event counter and determine if a least half of the tape cassette's tacording time is still available. If so, leave the tapes in place. If not, replace tapes with a fresh set. ( d) If the triggering event us a real earthquake, then. j
- 1) Perform a post-event calibration of the SS Tapes (I & C Dept.)
- 2) Remove the complete tape set and replace with fresh j
tapes (I &'C Dept.).. l
- 3) Forward a copy of the three free field tapes to the Civil Engineering Dept. and await their disposition.
J The "used" tapes are held on file until the Civil h Engineering Dept, decides they may be erased and reused or sent to Terra Tech. Corp, for analysis. i ll < l i l l 0~ '
, 'DC0036 311 U r(f ~ w. _
\
i N AND 2 OtABLO CANYON POWER PLANT UNIT NO(S) RE DATE 7/6/83 M LE: EARTHQUAKE MODERATE EARTHQUAXE (0.01g to 0.1g) Symptoms
- 1. The maximum acceleration on the containment base slab is indicated to be between 0.01 and 0.1g by the EFM.
- 2. The " Seismic Instr System" annunciator is activated (PK 15-24).
- 3. Ground motion is felt "in-plant" (inside the double fence).
Automatic Actions None expected. Immediate Operator Actions
- 1. Notify the Shift Foreman (Interim Site Emergency Coordinator).
- 2. Make a general survey of the control room instrumentation, with particular attention to annunciator and computer alanns, to verify that no apparent damage has occurred.
- 3. Notify the RPM on shift to make preparations for entering Containment to conduct a quick inspection for fires.
Subsequent Actions
- 1. General
- a. Establish the onsite emergency organization for an unusual Event as specified in EP G-2 " Establishment of the Onsite Emergency Organization."
- b. Notify offsite organizations as specified in EP G-3
" Notification of Offsite Organizations."
- c. Instruct one Power Production Engineer (Nuclear) to come onsite and retrieve seismic data. .
Si DC0036 4II
m EP M-4 1 AND 2 otAst.O CANYON POWEPI PLANT UNIT NO(5) DATE 7/6/83 p mtE: EARTHQUAKE l l A 2. Subsequent Operator Action
~
- a. If a unit trip has occurred, maintain the unit in HOT STANDBY (Mode 3) until the Plant Manager authorizes a return to power.
- b. Within two hours following an earti. quake exceeding 0.02g, inspect all zones listed in Technical Specification Table 3.3-11 for fires. If the Kinemetrics SMA-3(BS) was not triggered assume the earthquake to be less than 0.02g.
- c. Complete the " Post-Earthquake Level Indicator Check List,"
(Form 18-9249) and give it to the Shift Foreman,
- d. The Unit (s) will be placed in HOT STANDBY if investigation reveals physical damage which could impair the operation of any Seismic Class I equipment.
- e. Call the U.C. Berkeley seismograph station (415) 642-2160 and obtain the epicenter location and magnitude of the earthquake. This recording is updated each weekday at 11:00 O, a.m. and on Friday afternoons. It also has special updates following most earthquakes that are felt in California.
- 3. Subsequent Power Production Engineer Action
- a. Initiate retrieval' of seismic data from the Kinemetrics SMA-3 basic seismic monitoring system (85). (See STP I-37C)
- 1) Perfonn a post-event calibration of the BS tapes.
- 2) Replace the tape cassettes in the SMA-3 and perform a pre-event calibration.
- 3) Reset the EFM.
- 4) Play back the tapes removed from the SMA-3 on the SMP-1.
(a) Det'ennine if the earthquake exceeds 0.02g. If so, l imediately notify the Shift Foreman and comence l an engineering evaluation of the fire detection l instrumentation in accordance with Technical Specification 3.3.3.8, ACTION b. This evaluation may include the perfonnance of applicable system functional tests, but must be completed within 72 hours following the earthquake. (O ' DC0036 SII ( l
NUMBE EP M-4 DIABLO CANYON POWER PLANT UNIT NCKS) 'l AND'2 7/6/83 DATE PAGE 6 OF 40 g TITLE: EARTHQUAKE (b) Send a copy of the record play back to the Chief
; Civil Engineer.
(c) Retain the cassette tapes for further analysis.
- b. Initiate retrieval of additional seismic data from the supplemental seismic monitoring system.
- 1) Perfonn a post-event calibration of the SS tapes.
- 2) Do not play back any channels unless requested by the Chief Civil Engineer.
- 3) Forward the tapes by registered mail to Terra Technology Corp. for normal processing including the time and date of earthquake (with copy of transmittal letter to the Chief Civil Engineer).
- 4) Install a new set of tapes in the SS recorder and perform a pre-event calibration.
- c. Notify Kinemetrics that an onsite recalibration of SMA-3 ad SMP-1 equipment is required. This must be performed within five days following the initial event.
- d. Gather local data in accordance with Appendix 1.
4 Close out with verbal sumary to offsite authorities followed by a written summary to NRC within 24 hours. STRONG EARTHQUAKE (0.1 to 0.2g) Symptoms
- 1. The maximum acceleration on the containment base slab is indicated to be between 0.19 and 0.2g by the EFM.
- 2. The " Seismic Instr System" main annunciator is activated (PK 15-24).
- 3. The ground motion is strongly noticeable to operations personnel on shift.
Automatic Actions The Unit may trip due to induced vibration or spurious relay actuation. D00035 6II
N M*4 l 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) _ DATE 7/6/83 , q O, PAGE 7 OF 40 I 7 ng: EARTHQUAKE f. Immediate Operator Actions . Notify the Shift Foreman (Interim Site Emergency Coordinator). 1.
- 2. Make a general survey of the instrumentation in the control room with particular attention to the main annunciator and computer alams, to verify that no readily apparent damage has occurred.
- 3. Notify the RPM on shift to make preparations for entering Containment to conduct a quick inspection for fires.
Subsequent Actions
- 1. General l
- a. Establish the onsite emergency organization for an Unusual Event as specified in EP G-2 " Establishment of the Onsite Emergency Organization."
- b. Notify offsite organizations as specified in EP G-3 O#
" Notification of Onsite Organizations."
Instruct at least two Power Production Engineers (Nuclear) c. to come to the plant to assist in the post earthquake evaluation. l 2. Subsequent Operator Action
- a. If a Unit has tripped, maintain the Unit in the HOT STANDBY condition until the Plant Managar authorizes a return to power,
- b. Follow-up Investigation The follow-up investigation involves the performance of various tests and inspections of the plant. As each check is completed, the appropriate check or data sheets should be fomarded to the Shift Foreman for his review. Since some of the surveillance tests will take a considerable period to complete, the Shift Foreman has been provided with a sununary sheet (Fom 18-9248) to help keep track of the progress of the investigation.
- 1) Complete the " Post-Earthquake Level Indicator Check List" (Form 18-9249). Return it to the Shift Foreman.
<O _
DC0036 711
N R M DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 7/6/83 PAGE 8 OF 40 TITLE: EARTHQUAKE l
- 2) Within two h)urs following the earthquake, inspect all zones listed in Technical Specification Table 3.3-11
- l for fires.
- 3) Complete the following " Post-Earthquake Level Indicator Check Lists," checking all indicated areas for structural and equipment damage. When inspecting the various areas, pay particular attention to chipped paint at pipe restraints and hanger clamps indicating pipe movement; spauled grouting at equipment support anchors attached to walls or floors; concrete cracks, especially near equipment support anchors; damaged pipe snubbers as evidenced by leakage from hydraulic reservoirs and/or broken or bent hardware, a) Containment (outside missile shield) b) Containment (inside missile shield, if unit is shutdown) c) Auxiliary building (main area) d) Auxiliary building (penetration areas) e) Fuel handling building (main area) f) Fuel handling building (vent. equipment areas) g) Turbine building h) Outside areas
- 1) Intake structure The areas referred to on the check lists are shown on the plant drawings included as Attachment 1 to this procedure. Return the completed checklists to the Shift Foreman.
- 4) Complete the Post-Earthquake Surveillance Test Checklist. Fonvard all completed data sheets the Shift Foreman.
O, 1 DC0036 811 l
N R M 1 AND 2 OtA8LO CANYON POWER PLANT UNIT NCKS) 7/6/83 DATE PAGE 9 OF 40 O.- TirtE: EARTHQUAKE i 5) The Unit (s) will be placed in HOT STANDBY if
- investigation reveals physical damage which could impair the operation of any Seismic Class I equipment.
- 6) Call the U.C.' Berkeley seismograph station (415) 642-2160 and obtain the epicenter location and magnitude of the earthquake. This recording is updated each weekday at 11:00 a.m. and on Friday afternoons.
It also has special updates following most earthquakes that are felt in California.
- 3. Subsequent Power Production Engineer Action
- a. Initiate retrieval of seismic data from the Kinemetrics SMA-3 basic seismic monitoring system (BS). (See STP I-37C)
- 1) Perfom a post-event calibt stion of the BS tapes.
- 2) Replace the tape cassettes in the SMA-3 and perfom a pre-event calibration.
- 3) Reset the EFM.
- 4) Play back the tapes removed from the SMA-3 on the SMP-1.
a) Send a copy of the record play back to the Chief Civil Engineer. b) Return the cassette tapes for further analysis.
- b. Initiate retrieval of additional seismic data from the supplemental seismic monitoring system.
- 1) Perfom a post-event calibration of the SS tapes. ;
- 2) Play back all channels (retain on site).
- 3) Forward the tapes by special courier to Terra Technology Corp. for nomal processing including the time and date of earthquake.
- 4) Install a new set of tapes in the SS recorder and
= perform a pre-event calibration.
Q 911 DC0036
~
1 AND 2 N R EP M-4 otAsto CANYON POWER PLANT UNIT AS) OATE 7/6/83 PAGE 10 op 40 TITLE: EARTHQUAKE
~
- c. Notify Kinemetrics that an onsite recalibration of SMA-3 and SMP-1 equipment is required. This must be performed within five days following the initial event.
- d. Gather local data in accordance with Appendix 1.
- e. Cormnence an engineering evaluation of the fire dctection instrumentation in accordance with Technical Specification 3.3.3.8, ACTION b. This evaluation may include the perfomance of applicable system functional tests, but must be completed within 72 hours following the earthquake.
- 4. Close out with verbal surmiary to offsite authorities followed by a written sumary to NRC within 24 hours.
LARGE EARTHOUAKE (between 0.2g and 0.6g) Symptoms
- 1. The " Seismic Instr System" main annunciator is activated (PK 15-24).
- 2. The maximum acceleration indicated by the earthquake force monitor or the SMP-1 tape playback strip chart is greater than 0.2g's but less than 0.6 g's.
- 3. Seismic reactor trip (PK 04-15).
Automatic Actions
- 1. The Unit may trip due to induced vibration.
- 2. Seismic Reactor trip at greater than or equal to 0.35g.
Imediate Operator Actions
- 1. Notify the Shift Foreman (Interim Site Emergency Coordinator).
- 2. Make a general survey of the instrumentation in the control room, with particular attention to the main annunciator and computer alams.
- 3. Begin appropriate action to place the unit (s) into HOT STANDBY on a controlled basis.
O. DC0036 1011
EP M-4 1 AND 2 OlA8LO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 TnLE: EARTHQUAKE
- . 4. Notify the RPM on shift to make preparations for entering Containment to conduct a quick inspection for fires.
': Subsequent Actions
- 1. General
- a. Sound the Emergency Signal.
- b. Declare an ALERT.
- c. Establish the onsite emergency organization as specified in EP G-2 " Establishment of the Onsite Emergency Organization."
- d. Notify offsite personnel and agencies as specified in EP G " Notification of Offsite Organizations."
- 2. 10CFR100 requires the unit be placed in a shutdown condition following earthquakes in excess of the OBE. Plant shutdown to COLD SHUTDOWN should cormence at the direction of the Site Emergency Coordinator.
' O 3. Subsequent Operator Action. .
- a. Perform the same procedure as for a STRONG earthquake (0.1 to 0.2g).
- 4. Subsequent Power Production Engineer Actions
- a. Perform the same procedure as for a STRONG earthquake (0.1 to 0.2g).
- 5. Close out with verbal sumary to offsite authorities followed by a written sumary to NRC within 24 hours. .
MAJOR EARTHQUAKE (GREATER THAN 0.6g's) Symptoms i
- 1. The " Seismic Instr System" main annunciator as activated (PK 15024).
- 2. The maximum acceleration indicated by the earthquake force monitor is pegged at 50%g.
O 0C0036 1111
N N 1 AND 2 p DIABLO CANYON POWER PLANT UNIT NCMS) DATE 7/6/83 PAGE 12 Op 40 M LE: EARTHQUAKE
- 3. The maximum acceleration on tne SMP-1 playback strip chart is
. greater than 0.6g's.
~
- 4. Seismic reactor trip (PK 04-15).
Automatic Actions Seismic reactor trip. Innediate Operator Actions Check reactor tripped and unit in HOT STANDBY. If not, trip 1. reactor manually.
- 2. Notify the Shift Foreman (Interim Site Emergency Coordinator).
- 3. Make a general survey of the instrumentation in the control room, with particular attention to the main annunciator and computer ala nns.
- 4. Notify the RPM on shift to make preparations for ertering Containment to conduct a quick inspection for fires.
Subsecuent Actions
- 1. General
- a. Sound site emergency signal.
- b. Declare a SITE ENERGENry.
- c. Establish the onsite emergency organization as specified in EP G-2 " Establishment of the Onsite Emergency Organization."
- d. Notify offsite personnel and agencies in EP G-3
" Notification of Offsite Organizations."
- 2. 10CFR100 requires the unit be placed in a shutdown condition I
following earthquakes in excess of the OBE. Plant shutdown to
~
1 COLD SHUTDOWN should connence at the direction of the Site Emergency Coordinator.
- 3. Subsequent Operator Actions
- a. Perform the same procedure as for a STRONG earthquake (0.1 to 0.2).
4 DC0036 1211 l
NM N 1 AND 2 DIA8LO CANYON POWER PLANT tJNIT NO(S) DATE 7/6/83 I PAGE 13 or 40 EARTHQUAKE 7:yts; g 4. Subsequent Power Production Engineer Actions
. I- a. Perform the same procedure as for a STRONG earthquake (0.1 to 0.2g).
- 5. Close out with verbal sunnary to offsite authorities followed by a written sunnary to NRC within 24 hours.
REFERENCES
- 1. 10 CFR 100, Appendix A. Section VI (a) (3).
- 2. AEC Regulatory Guide 1.12, " Instrumentation for Earthquakes."
- 3. ANSI Standard N18.5, " Earthquake Instrumentation Criteria for Nuclear Power Plant."
- 4. Diablo Canyon FSAR, Section 3.7.
- 5. PGandE Drawing No. 443296, " Seismic Instrumentation."
- 6. PGandE Drawing No. 452417. " Diagram of Connections, Seismic Instrumentation System."
- 7. " Seismic Instrumentation System," Record Print No. DC683697.
- 8. NUREG-0610, " Draft Emergency Action Level Guidelines for Nuclear Power Plants," September 1979.
APPENDICES
- 1. Post-Earthquake Inspection Area Identification
- 2. Seismic Instrumentation Description and Post Earthquake Checklist ATTACHMENTS
- 1. Fom 18-9221, " Emergency Notification Record."
- 2. Form 18-9248, " Post-Earthquake Evaluation Sunnary."
- 3. Fom 18-9249, " Post-Earthquake Level Indicator Check Lists" ( 3 pages).
DC0036 13II , i l
N R M-4 1 AND 2 p otAsLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 PAGE 14OF 40 Trrts: EARTHQUAKE
- 4. Form 18-9250, " Post-Earthquake Area Inspection Check Lists" (10 pages).
- 5. Fom 18-9251, " Post-Earthquake Surveillance Check List."
- 6. Form 18-9252, " Post-Earthquake Electrical Power Check List."
- 7. Fom 18-10291. "Cata Sheets for Peak Shock Recorders S/N 701, 710, 728."
- 8. Form 69-9283, " Data Sheet for Engdahl Peak Acceleration Recorder."
l 0 I O. DC0036 1411
NUMBER EP M-4 1 AND 2 7 OtA8LO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 l PAGE 15 op 40 l. 4 TITm EARTHQUAKE
& APPENDIX 1 POST-EARTHQUAKE INSPECTION AREA IDENTIFICATION
, . - . ~ .
= =- n:
qq g g e- +- 2 ____ _ y ;;' ( g
! T _j _ . _ _ gaan, - 7,: y es- p; --r i
__m. l, 'ay a Qo T:s L
, . T i w " =I-Gy4,
- n i w a ;2=-. i Jp. e, m. gi, n, rg,
--- _44W -WI
- 2.. g m.. . . . , .
p ; I1l4'. 3. _M___ _h _ _ - - _ _ _ .
- 3dl %_i F5E . -.(_
P ,
; .;l p ' a , . s._ c 9 -
.r. s t , y c , pg.j :, --
i
-- 1 i:q Jl
- 1 l $ 1
\ ~3 ... . -t .a h __ _.*:,.
. 4..h k i
I l J
.__'[ 2.
~,=&_ .__ (. * * ' !
- - c ' I E
g, ' ::w--g ' \ ,.' *:_s i . . ]
'-_- _., 4 f L-- ,
n o / .. . p 1 $.D, d; -
=@ " 7 -
~ ,
.- 1' -
Ol! Q.{ m m
- - \
=
EC
.as gM 1 E;.- e c.ii drusu =5
. P ,
~ '""
. . . ... , .l- ,
W, I
.l
".'.Q a--_._
c 3
. c==3 . :
n c J" =' f ' A F. h j }. - T j (r . - M- '1[
~
u- . l R 4 - -- ,
~5. h}A'~_ h$l-h.h.I :
_ =- -
-F _ _ _ _ _ , _- -- ...._--.a ,
i j i 10A - ROOF AREA AND EQUIPMENT ABOVE CONTROL ROOM (ELEY. 167') l t UNIT 1 - CONTAINMENT, AUXILIARY & FUEL HANDLING BUILDINGS, ELEV. 140' i DC0036 1511 t
._ I
NW8ER M-4 OtABLO CANYON POWER PLANT UNIT NO(S) iAND2 , p DATE 7/6/83 PAGE 16 op 40 M LE: EARTHQUAKE APPENDIX 1 (Continued) r 4p y p1 ; j ~ V-r--sq a 2 7 Mi
,, gW 24 j-- l . -- .
.g ky t k___1, .k va..-:.w" Ta = *e l
=
1 C1 '. wpf;*ig.re'.a--;
-a,
- n a : .ss u
4F = "
- =jl fb A A M<--a : 4 i -,,,,,,_
<.gL T ,,,,,m,-E*$' - - -
-~ _; -
f _
]
*h
, ?l* ", ,
} ,
I_ N f %. Sj Y l,. .l R ,,j' y,' f Q'(' Q_ E 5&
~' ~'
l y , ... 4sg, n . 4 -- m, , 84 .' A' ;e 1
, qu .h j :
I)Y('I ,- N py . /r ,
,6
., gg,
~
g.sp 3 lT J~ ml < l :
~g Q
=s -
//
gn ? . ./
~'
9 W v. Ny $ L s.g .:=. - vc 'n
//*~ ~
~.c -
s*
-,y _1 ., [ ..
q-w - 7 7,,;
.-M .. g m.,T.'
_..;,)_. _ _ . _.MEM:iM"*"!> UNIT 2 - CONTAINMENT & FUEL HANDLING BUILDINGS, ELEV. 140' O. DC0036 16II 4
N P M-4 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 lJOt PAGE 17 OF 40 l e
- Ting: EARTHQUAKE EI f I
APPENDIX 1 (Continued)
~ 8 -
. %a l[y, g,p '.
n .. e R. h. s 4lbud!,. . . ~ , ly f'{;Q- - i' 9 si ,Rif WW$ s{ .., =+,r.w g:=rg=. y
- d. ;r3;73g , ,3
= a-*-e6 -
]). J,; iMir'a is -,5$g IiL3{,N
{g,1
; - ,r % -f(
/
y i
~%pphakJ:gw,1 g' y g;4g.p;r,, y
? J'
;R$ '
s,. q ;
.g ,; E O u -- .m mam u i . i
" 1, nAnsggas.N g r Livev 4
7 Er ! MlMi$ #a d%a4 ,IW 1 _ M (d ! pam.i, 9, [i 9.-i l g g. m i ,
- Il f
/ 3 Y,L m e,
}
//s ;, ;
- i. l. . .' l W- NQi;
- - j' =eV h&_ $ $tgh, ;,
l
$,s _1N ,
i
, '; Em s M,,] -
p gg 4
- l ,
5 : N
~ '
; Ee .. 'u -
1_ M
, m E
simi g, e iim i liG
, F,' .1 il l
l
,[;_p,[f f f -[ l]wE !
^"bNIT1-CONTAINMENT, AUXILIARY &FUELHANDLINGBUILDINGS,ELEV.115' DC0036 1711 L
_ __ _ _ _ , - - _ . - _ _ . . _ - _ - _ . _ _ . . _ . - - , ____.m. _ - _ . - - -..
NUMBER EP M-4 . 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 7 DATE 7/6/83 PAGE 18 OF 40 nrLE. EARTHQUAKE APPENDIX 1 (Continued) Y m a! - =l* Y .,,. . s c $ 11 . .Y .. . .- ._ . mL _Y Wl _j g _. ._ g c .: _ - -_ .,, , , 3.. r ;
-y -
. - --r;
- g fi
\
5,-_M~e.. p
- ~. & \ f..
Mi m , r e* .:. - v -- - -
\
sw g n. d
=- sL 4
j =-d7; i: -
%92 v~ :.....,.o_
- z r
m - I .
* *Y j . _ - ' ' '
f
' i I
9 l , b TF l g @*'l
' l l
-msr F . -
- h. - ca _s
;hy -- _
.-2.,
l T- "N - e g p*~3 j g4_ , .
~g.
i j g : l
, s 1
, /
/j .
~
g.a .x:- I J. 2W. le T *. : f k,. l L ' n~ E;=a lT=--i i% i I iL-.N Fi s J ! ii 2
- _. m - , , ,
d- . u
, 3 -{ .,
- i "m" , k, . _, .
g g L . West - x 2* r *--
.l il
]a 1 q
=,
l .&
- p a .,
t , i h h- \k -
) l. ' _ _"4 Y . .
r' I _%2 ~ j .
~' ' " * *
- c 4
= ;
c l-- m g
- c: . 3 .. . . . _
- I
'i UNIT 2 - CONTAINMENT, & FUEL HANDLING BUILDINGS, ELEY. 115'
;t i
I o 000035 1811 < l 9 l l
NUMBER EP M-4 1 Ai:0 2 REVISION 7 J DIABLO CANYON POWER PLANT UNIT NO(S)
- 7/6/83 DATE l PAGE 19 OF 40 TITLE. EARTHQUAKE
~
APPENDIX 1 (Continued)
- =
g - s-n --g D~ J"h WM - , I-n ! y _ _ * ,2 O b '"u .. y' 1-I 15l I i 't e -e Q _ j
~-
.h' AtBE% d Fr,B *$
~ bw-Twdi$Ne r-s~
Nn $-- t-7 as 1-, 5"*- =c T $ ~ d_F a j LL: g; -~ Y .
'E p
~
=- 46 .J e W i
~
N ~O s
- r. ,
n, M tir a (
=
I
~ '
dj D 3 (, j lyr - 3 { ' N-l an - jaE . Ihg 7 -- ga t _. - s I 3
,ne y a.-j y me .. - 2 "i l
.g +u_ h om l . ._.
# b r^ m. p ra o=j _. %
J_g( W y-Q =dE5- 4V
~ -
...[ =*o s
~~
-. u -. 5
% .+ !.?.-S!D LT1 ~ --
r
'yI,M[ )
*Ta
- q g x... ,w. L-
- ~ = -e. j;
, 21. ; m -- _Qqqu
-: ar- __ ~ -s ? ~m -
r._ ,J a .r
= - - + - _ . . .
l I UNIT 1 - CONTAINMENT, AUXILIARY & FUEL HANDLING BUILDINGS, ELEV. 91' & 100' DC0036 191I
N R EP H-4 oiABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 7/6/83 PAGE 20 op 40 TITLE. EARTHQUAKE APPENDIX 1 (Continued)
- 7. - , . , s. , - -
,g g ig . i t 1
w 1i= -.,aNTd:- - i2 f u{-___.-i
.,,,y ST r
l ,o @ . {.] p , _J..eg, . . . :.:. , 1 __g 4
- . 4 -
~N C ",%
.F7g%3 L
a' Q E J, n_gn I
~ 2 k..yp r-:::f
,,g
;T.9 j
l
.- * .=?41u':$W = M' _[n lTb Q:s*totk- N%f w i' ,. ,
l
' I
# 3 7e, " $ .~.'. 2
- __. 'g >
i, -
- r. ;
3- . l .
-:l 38 , ,ET[d) ei m em g [- F]
~~
z-al y [ 5 i
-Ji
' d L _, :
I'<((
- .- - t -- r la
;W
- M
- 1 t Q Ew.
8 e
,J e$
- i. ,
-i y '
.{ .;f A
s
- j mi i
=- ( 'c vc_
c .7 2 94-" .
" ~me % ', ~. g e , ,% *- ,
7
! P '%
ls _ 3 1M' s _.. ug'M.. a 1 . wise ' . i guery .t __ y.
/ =m M $ '" aume'- f
.f I ~ D ' 8e*2' T 7 o p-
- f,-_g..
.t. %. ..
4,:s- e 3 . .,' _
^
- 1. n ".."e . -a. lg _. _. z, _-... .___.L. ,
z. i. 4 4 UNIT 1 - CONTAINMENT, & FUEL HANDLING BUILDINGS, ELEV. 85', 91', '
& 100' I
DC0036 20!! j i 6
N R EP M-4 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 i O, PAGE 21 OF 40 TITLE. EARTHQUAKE l i l APPENDIX 1 (Continued)
. \
e T . ,. . , T . , 4 # QQ. "Q _ _ _ ~ _. V s
- -- :- - - _l .
% L~&lb %L* >
~
%, r.;- %l ' T ~ ~~~ ~ . -. --. ETR;i .% ;T ** %
i,RD,-s.5 { sEE i , wn >==m -- --
-- h $. , ,1 -
7i. ,
~
e
~
w -- v _ k . j , dfw: sW.m. y$ N M-t HTS
..~.ww.. !
.' O.'
r .- - I
,i i ,;n g wi '
.m,@ c. ,f >
I. mv / ! g H
--g,; ,, -" -
f;8; P ', s, -'// 1-- g ,= :. l r --- e Us,.d- , LE, _. . J. 4- ,
,I~} -m[h' (,.[.id M' .i j c
O s' L- - -- -
-+ l+. -
u ei ;.Q3
' ^
/
wagem m
<- x .= c- m E o5 .
-, ow. -/ i-
.r . .
A l l e o _, , ]
. . , 7=an_h l,,,,,2,, a ar .<
m =miin . . a , , hit :
. ht t a
_ _ _ . [__2 lMr _ .v;;FWT- "
- I^ --
r -vT.7T' . i
?
i l UNIT 1 - CONTAINMENT & AUXILIARY BUILDINGS, ELEV. 85' l 0C0036 21II : . I
NUMBER EP M-4 OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 p 7 DATE 7/6/83 PAGE 22 Op 40
;irm. EARTHQUAKE APPENDIX 1 (Continued)
~
- t. . . e,i .. . _ . . _ M . ni M _aut _ _ . f.
, - , = -
- 1. ,., . . - -
- .i -_
i g - __ . _ ; 1 _ _ . - I W __., _ _
. .k p m. _ ___
m s l
,, ,.__?.
t_A._. ,y _ - . - - ~ _
~
Ry,lE-$
~
= ;@.:1.L]
, l a e, - - -
\ . :
..._4 l<
( 9 t t _ _ .Pl . i s : _ I l n p , t--
'> w, i i flEr I .
i b.S, g -i
;M._ n.
4 l a, . == i
- _h ':--- EC '
.rp Q.
s n -.-
,, p g- . .
- 3-=
=
7 f hn v . ::TD31M. - _ " .
=__
9 &, _.
. _ .p, - i
. - &c s , a <m _
-M= i M! _3 1 9
~"'
] r4" a
g
- :R ,_3;==, I .
~- a _-v. .a . . _ e E _.
e- . W W t i UNIT 2 - CONTAINMENT & FUEL HANDLING BUILDINGS, ELEV. 85'
- DC0036 2211 !
\
N R M-4 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 PAGE 23 op 40 l
*- EARTHQUAKE TITm S APPENDIX 1 (Continued) e A & M M
- ~- --
p:
-gi 7 u 5L, . 5 % !
-c-
-r w ht e:w e.w&n T 83; w r y g"7-
=
i y ., }y i il i "t $. t~ b '
=
. .- i
'=; n LL I, .E - i
+2 s
G _ _ A. ct'
-e k il
=-
w \ J
-M
. . -y:p m )
c.- e
;4 a 4P W . RL -
g a 8 ce .
).
i; __P -, i !G T q,-. - - * - - -
.7:EWf*?J "MyABW2Ma- _ _
= -
Ribi__ g . ,. . I, . .z#:-=4 : 4 an e t a $=.,, _. .;_e - I UNIT 2 - CONTAINMENT & AUXILIARY BUILDINGS, ELEV. 73' DC0036 2311
' --------.__m_. _ _ __ , _ _ _ _ _
NUMBER EP M-4 DIABLO CANYON POWER PLANT UNIT NC(S) 1 AND*2 REMSON7
~
DATE 7/6/83 PAGE 24 Op 40 TITLE: EARTHQUAXE I APPENDIX 1 (Continued) V
\\
I t- ,4;( n .g _ C - l r'- M@S P. . . .. . . q gem 6 Io e l i l
- I*
i I t i
! i i
UNIT 2 - CONTAINMENT, ELEV. 61', 73' l
'g '
DC0036 2411 _ t
- k. . . . ..
NUMBER EP M-4 1 AND 2 ,3 g DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 PAGE 25 or 40 1 TITLE: EARTHQUAKE
~
APPENDIX 1 (Continued) 7 b. .k h.ji-. -- -I N ..h ME $$ W _ __ >= r - -- m t %, - g - - - n =e . , tid-
- y n y-l
@ f, - .
e} 6 ,
.F m-1 a :
[Efh J 4-l} - j k,............?kh';'
.: . 7 r -' b
'+,.
h, Ri*. Wght Y t h - 4 lJ - l -R i i fV - - s 1=
- C4 r _J *-
g 1
' . . _tZ '"
gr-G --
, i
.e-' . : j -- ) Q4jF L=J t-- e a L . J ='B :
!! -8 E Q*.59 $ J'--' h_YS U
_li i! AWr-' 19 JcM* _=t I[$@' 3
#M
.Y ib . M' M WYi 1"
?
1
. : 1 n:-- ii mi ii sg.
a lD yg = 1 L x. _ e.: : n n e.----- . rp yp .my E u , . . . ,
~
-. C"" Q.
g
~
I 1
'3-1
@'Q , .
S T ,. Q_ - _ . !!1Er~.Mi!rl... 2""""" . - 1
.d*W ~I
. g--~~ _ __ ___. _
=-T--* _ _ _ _ . . .
.I '_
-W"-
~ -- -
~ --'
t .. ..A .. I 'r 1
! UNIT 1 - CONTAINMENT & AUXILIARY BUILDINGS. ELEV. 60' & 64' DC0036 2511
l NUMBER EP M-4 OtABLO CANYON POWER PLANT UNIT NCMS) 1 AND 2 7 a DATE 7/6/83 o PAGE 26 or 40 TITLE. EARTHQUAKE
. APPENDIX 1 (Continued) 0 6)
I we 9- --- . ..
.:4 .; . ... .. .1. . . . . . .Y.'.r...,
g r... .
.g _. M. -, ,%_._- ..
Tp,.s 4 t
- ; i. ,
ou l '! , C ) ;- 9 -i j } y_;
.. . ..y ,
i
'--- turn-i-. r ; . *! e i
D . . ,- 1
...T '
I ; o - 8 9) UNIT 2 - CONTAINMENT & AUXILIARY BUILDING, ELEY. 60' & 64' i DC0036 2611
NUMSER EP M-4 ~ 1 AND 2 REVISION 7 otAsto CANYON POWER PLANT UNIT NO(S) 7/6/83 DATE 27 OF 40 PAGE
- ( '
TirLE: EARTHQtlAKE 5 APPENDIX 1 (Continued)
. ... ,_ c .a . . _ _ ,
..__..__,.......s . . a e_
,,, . .c x .. r' -.
i
.i l l [,
l , I !
. l i i
!'T l .
i I, I I . l ,f"ur. ' i t , l
, i e l y- j* l
_i* => 'as = l ikl :=%R' * @~~~D E '-n-
' 7
'f t,
j g-G " r" 3 1 - l _
?
r
" ira;- C'-2 .w 7
, 74.=~
i
-mt .
i i . . g*[_. J< I I
. . a . . ._ m
'- -,=.--
j DI i
kt _, ,M, ,_,.f..
in I I , g
- t
= ,
( M. P-I r
' f,
" ~
Q ?-*l k g;DE ' N .-# . . _ _ _ _ ;
- M -; ' @7 2 4.L m _.: =
I '
'h-- k J ::d 7 "D i
' E!t 16 .
I ! L _ :. _: 4 ._ ' __
' 1h .
- _'J.
i d_ w~"" _a mL _.2..
. t l T~: e f ' ' -~ -
l- i
= =
_;D h ar- . ___ g [_ s g _'u_ _
..m..g..
r 2 ___.. i i 1 i n . . . e. I l UNIT 1 - TURBINE BUILDING, ELEV.140' DC0036 2711 es-u
' ' ~ ~ ---e - - - - . _ _ _ _ _
NUMBER EP M-4 DiABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 7 OATE 7/6/83 PAGE 28OF 40 TITLE. EARTHQUAKE
- . APPENDIX 1 (Continued)
..,...,..._... . . . . . . . .. m.
"--^3 .I p .
I i i
) i l i ii i .
I - . . j i
- I l ;
f f{ i
- i
., { I I I
1 ll X
' l ;
l i --/ l I l 1 1
; i - g ,l w. - .
i ' Jm i i j
%. gi .. r ,:-=.L, ' mwl: ~.g,,y -
r-
;g . . . . , , __
_s . i
~~ ~5Y&&&'?-$$$CN5 N= _ _ - _ t . ._ . _ _.p _ . .. .j i__,_, ~ N.Y ~~ ' '~ ' ~".&
..__--__*_ .3 ;_ i _ 7. ! 1__. .' ! '
{ -q ~_, I
$i N . I g
%n WQFT P i
1 4 TT ' ' i l .
._4 ]9 z
- - L a y
%dd 4
!.- l3 LJ.J _4. -Q' lll p.gl . J ! l l
! =J i i I i , ,
l
~ ~
x .: . l~i . _. 5 . k_ EWj I DE1- ~ ~~l
-> <'-s i' 1 0 t I )
*-l
, '_ ., --. wlg, _Q Q"Q_i C.P-Q - _
ea t a ,. -
qpw_._y,Q.__.Q e._ m . l..
, , __ ,. -d l
; .? ; _ g A4 . , .. ;_; g.; L ;a; .. ; _ ; _ , ; __
i I i, e t
. UNIT 2 - TURBINE BUILDING, ELEV. 140' DC0036 2811 L J
NUMBER EP M 1 AND 2 OtABLO CANYON POWER PLANT UNIT tO(S) REVISIGN7 DATE 7/6/83 29 OF 40 ( 9 TITLE. EARTHQUAKE PAGE APPENDIX 1 (Continued)
...a .. . . , . . ,
, .. .. q .. a . . . . . . . ...,..a.. _ ... .
; [
a 1 i l l Tl f '} I
-v.-e. f-i l
I rc l
- t. ,
I yll - l - J' n i l m -' I t j i l ! o l l' '
.2_ L._.!a + -.-al ._i _t . -l l T
. 1l- %ss e U- M3.git< _:; WT :P .s-. , -" - -
{~_i, L4 y"~ J i .v._ s- _a s 1 JJ. ,=jj,,r= , -_- ( nuf _-.Lv. -_:..,1 _ _ _ . _ . _ _ .
- e=g
.q - . - -~ = - gpr - 7 ? .t_ ,n_- .w _ p
- u. g k u
.u /
a
+~
N[N-~- ~~ a -
. : ,,_h .,
ny b y f-- l --
.- )
6 ,;- m f ~,~" M .m. .y . _;__- .", y - - O, L I fy-
--.,g
- i.
c e
,,m _
,e ~- -
.. -. x .. .
r :- /-. ~ Y "; -. y$ 5 C
, !bbbh iT F [* -c -
I W Y~- M=ama'l 3!Ap":.hh . %.ccmy =r>y.n;.r-5 $ . " Na J_us L i i e ,c .g-4,>= ,y 5 c z 2 m c,
^^
w
~ r", ^^ W -fo% . w a r c-I i
o I e i UNIT 1 - TURBINE BUILDING, ELEV. 119' l-i DC0036 2911
.~
~
s X l___.________
y . - - - _ _ _ - _ i.~ l . NUMBER EP M-4 DIABLO CANYON POWER PLANT UNIT NO(S) i AND'2 REVISION 7 DATE 7/6/83
' PAGE 30 op 40 mLE. EARTHOUAKE-M M APPENDIX 1 (Continued) i .: 1 m
-,/..,'_'_,.,,' ,,
*^
%d sa -_.-,_#
g ,- . . .. iI . j i
- r. .
4; - l, I s___ 5js _
, ll i
.( ( I
-._i i .1 .,
ll"1$ b, i. Ie i h T ~ b. l v-mi-3 , ,n n.gaxr;m.-.o:a3; .
?
#w.[1-=d w n7 --
. . e ,1tu5n=,=sin. e=
. -~. MW=
2 _ a a i Y jvc_ rr- & uio e -- - m - e . i < t-a i =- ipe[-4 -=%_--s p _&: ;i E- $-# 1' .G
,. :l M A J t #-sHe ~-Mi-5:s eu w 1 we.49
, e yg L_- ,; g fe4r a 1 g+ rhM_ u ,
dp .-Eqj ___._.yw ew i-JE:.. n d,,l g&z[=w.p* ~ .
-l.~m._v.af, P c- m' .e .._
n:.-nw
- c. . =-- . No i -
hog . . .
<.~. . c . .
f.. - -
- ....- .=.
_q-r . . { w . I i l l UNIT 2 - TURBINE BUILDING, ELEV. 119' l t g i I DC0036 30!! t'
-s ^ ^ ~ - - ' A.____ i__
x __
I ~1l f ' l} l, NUMBER EP M-4 1 AND 2 oiAsi.o CANYON POWER PL#iT UNIT ho($) REMSION7 DATs 7/6/83
;, PAos 31 op 40 . (O / /
wtg. .EARTHOUAKE I APPENDIX 1 (Continued) I 4
~[M ,7,j { ll 'j' ] i 7. ~
i , 1K g p, Ti 11, ! ".1
" ' ;4 g ,u y
l r -e I
-ly .ar ,
,w (N - -- -a . !
8 2.' e, , S. m%d
.. =M" >
~- 4W4 - ,
- y f,
," n
-h e.R ,
T_
,l,p:--':
,$mit = cmq -
k y )<r-
< I si9'E u o-H 8 :
= . . . .
4 =;.4 , 3
> LsE,
==fr i p <
3-Gh- '.wl' i -- 'CW y 4 - ==
-M-. . g'"
(-< g 4
- rAO
- l g1 E6 11 I \
b be *ireh-- r-l r nsc: ;
;t us o m; - _
~
1 , - f n! f' hj*e [ =_._..._;s . t< i e c q
. J, 1 :r-.'
6 mY,. i me .. u.. i [ [ I - g ' a . , e .- , i' p[ l ' 67 ,
,*p. , ,. -- ]
1
=
7 , q _ . _ UNIT 1 - TURBINE BUILDING, ELEV. 104' i. 0C0036 311I
-r
NUMBER EP M-4 1 AND 2 REMISaON 7 DIA8LO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 t PAGE 32 of 40 I Tira EARTHQUAKE l
.I DS APPENDIX 1 (Continued)
- - .+ . . = .. .
_I. II l ,. l
; .i
? -
l fi .f i T l l j i i I! 3 .
',i, w;/'
i l ; ,g ', i J
; .I vWO l .
t.
- < -l w-
==t-r.._4. , . , . u- :. .
r _ ir_.w w 7
---i /C .- i e a i l f *
==; ,a , g t _ = - ~ ~ lw = -L.W#
~.- =r(-
7 7* l up %..I</.1:=a % w y== c- z; I u. l=c;- . ( ..= =,s c P-W '
;'amur ' h -M rg.-
a
. r Aa l -
, S. - l 4'y _' 3),4 i f- uf * + l;]li7 l.. E j 0 l e t-24 e
-- .; .lf.t 3 hll. .. . . li{im Igi3---
r=qo mJ .
%=4.re 9" t J.,
a-L- 6,
.z_ Q gy,-
.. ,p.
g y.. -- z._ .. y w m..1 p_ g r - .#p
,i
.,:..:- t ,' ,_ _e,. ;
t_-3 .,+d%p. ie o p -
; '" ; fr, ! .A : Ta . c .
r , y. i
- v. i. e . .. . c .
. .y,.. _ , ,. ,, .. .. . . .. .
1 4 0 l 4 I 1 . e UNIT 2 - TURBINE BUILDING, ELEY. 104' w, DC0036 3211 _I
l NUMBER EP M-4 1 AND 2 REVISION 7 DIASLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 l PAGE 33 OF 40 l l( ' TiTLs. EARTHQUAKE APPENDIX 1 (Continued) C '~ ~
' "=n6 M'WU J kE I 'r' g II 8 C, .h l
'.{
I; i
' i.. .rc i
~
r f, ! -: .'- e ED(7(-lt
~
'I d_i -_
'h .
_. lA 9 M i:lPRi3 d ~6 ,, 4 ~"y ~
~~
O pl jug.. .@ Q I n11 wQw
._R -g
"~
QI$7 Ii pl. E I - -- _ ,. IN - 4.f sf-M..M , W. p.9 -
,7
#4 -
c-O
*. , tg .
g5 ' --' ~ ' 7,,i I
#. .... hj _ . ,_ -,1 j
"- L! n_ i ;. . __ h ,
tL - h[_ [M_. ~i c :
.o AA,
.c- l
?
Wl[M $ e'b_ , ed \
,e ; ....
- N.5 - . b. j) $' $ll N h.\he \, - . -
I ["F" l e uns. .e 47 ; p. r; ,g g 5 . 7 ;; =- p; ' h' Id ,U ' l' , i N I 81 :
, hi . ,
- k _
- [ !'
k db T3 y t N)' NM[3 _ iA tim M. '
$in'DiiV8N!$#-- -
k 3 - - Ls= ? Y.
.$5 $r, - - . l--
l 1
; .4' t ! 1 y: y . _
') .; .% - . .
UNIT 1 - TURBINE BUILDING, ELEY. 85' DC0036 33II i a l l
NUMBER EP M-4 1 AND 2 DIA8LO CANYON POWER PLANT UNIT NCMS) REMSm 7 DATE 7/6/83 PAGE 34 OF 40 TITLE - EARTHQUAKE APPENDIX 1 (Continued) f a a f
..._......_.......1
# 1 i e I t
_e .m . .. .. , i i p_ i j yd-- l - - - -
; , ,_ ki , . . /./ .
g': j, i =- ! a - i 2 m _h i - , ,, e . lW. r., g- + = m.i '
' ' ' ~~~2 l['
l( : i I' ' Q/ . .,
.=
W
' 3
- i h h ,
le
~
r A I [i} =_] n F 'rC ~YJ .g r _*T y .n.. - Tg p z! -
,I i
M RT.f k~i- l[ ,:::4?h ,t*- k := - -- Jh 3}: O 9 US %; 2
'4 ~
'---!_ 7__t ie'/ [;, Hm!G 1 !f4/'76i
_ . 1 i
, stae M Ee l '- ,
f 4 s - L,._-- hN N LNh5 i$. edi[%% rt- bbN EY l 1 l
$m m$.
. a g >.rv . n u n g e.. < .
I i L . UNIT 2 - TURBINE BUILDING, ELEY. 85' e DC0036 34II O e.uu4D w.--.._ _
N R M*4 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) _ DATIE 7/6/83 O EARTHQUAKE PAGE 35 op 40 TE e APPENDIX 1 (Continued) P r m 4 l :d,_ 7' N "- 1 +s==G CO ,G Wi u il . t I l- e [_'- dQ l g O.J' lI i Hv i - - dj i Mv If 3 i _
', j . _
~i-l / i 1
i 3 "6L J , . OM i i i li CO Ji,
'jj i
! };;
' l;,
li@[I -
*r I
[ma. i i e H-
'O .
ei i i gfg. ll leo r. i ; I I, si ! II i t
- i. e' .
I@L: m..n. El
;d! .
11 ' lii , - > l IIA ! I 'l f. ll
'* C !!
l 1 miU i [Ise,.i?i% ,1 > N.m
-- l p- i a i i i'N 41! 1 _.-
l lh l!g!k i, i / i I Ir .- OJ!- 5J t 11 l G 07 i
, ;e
- 6 ! %
i Q . c 1 l UNITS 1 & 2 - LAYOUT l f , 1
^
DC0036 3511 1
N R M*4 1 AND'2 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 7/6/83 PAGE 36 op 40 TITLE. EARTHQUAKE APPENDIX 2 SEISMIC INSTRUMENTATION DESCRIPTION AND POST EARTHQUAKE CHECKLIST
- 1. GENERAL There are three types of seismic sensors: 1) Engdahl peak shock recorders, 2) Engdahl peak acceleration recorders, and 3) Kinemetrics triaxial accelerometers. The different sensors are provided at plant locations as shown on PGandE drawing 443296, 443043, and 443044.
MEAS. NO. OF DWG. RANGE INSTR. DESIG. INSTRUMENTS AND SENSOR LOCATIONS
- 1. Triaxial Response-Spectrum Recorders (Engdahl)
- a. Containment Base Slab, E1. 89, 180' 1.6-90g 1 2-25.4 Hz
- 2. Triaxial Peak Accelographs (Engdahl)
- a. Containment Base Slab, E1. 89, 180' 22g 1 3b
- b. Top Unit 1 Containment, El. 303.5, 225' 25g 1 3a
- c. Intake near ASW Pump 1-1 Bay, El. 2 :29 1 3f
- d. Turbine Building, El. 85, Machine Shop 22g 1 3e Auxiliary Building, E1. 140, Hot Shop 22g 1 3k e.
- f. Auxiliary Building, E1. 140, near 22g 1 3m Control Room Door
- 3. Triaxial Time-History Accelographs (Kinemetrics)
- a. Unit 1 Containment Base Slab, E1. 89, 180' 21g 1 lb
- b. Top Unit 1 Containment, E1. 303.5, 225' 22g 1 la
- c. Auxiliary Building, El. 64 21g i Ip 4
DC0036 3611 L . . . . - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
N M*4 otAsLO CANYON POWER PLANT UNIT NOC5) 1 AND 2 p DATE 7/6/83
, O ma EARTHQUAKE PAGE 37 or 40 e DISCUSSION
- 1. Triaxial Response - Spectrum Recorders (Engdahl)
Each of these units contains twelve spring steel reeds of different lengths and weights. A diamond tipped stylus is attached to the free end of each reed. A flat plate is mounted adjacent to each stylus such that in the event of an earthquake, the vibrating stylus inscribes a permanent record of its deflection on the plate. Since each reed has a different resonant frequency, this arrangement provides the earthquake acceleration (as measured by reed displacement) at twelve different frequencies. l There are actually three individual shock recorder units on the containment base slab with one unit oriented along the three ' perpendicular (x, y, z) axes.
- 2. Triaxial Peak Accelerographs or Peak Acceleration Recorder (Engdahl PAR's)
The a celerograph records by scribing a line on the surface of a record plate. Thr.'e record plates are included in each unit, oriented along the three perpendicular axes. The lines are inscribed by a contact diamond stylus, one for each axis. The peak acceleration is measured as the maximum deflection from the zero baseline.
- 3. Triaxial Time - History Accelerographs (Kinemetrics) f Each triaxial accelerometer unit contains three accelerometers oriented along the three perpendicular axes. Each accelerometer is a damped spring-mass device which is fed to a mechanical-electrical transducer. The signals from the accelerometers are fed to one or both of two units (see Figure 1). The first is a SMA-3 magnetic tape cassette recording system. This system has a starter unit which automatically l starts the cassettes at a preset level (0.01 g) and shuts it off when the acceleration drops below this level (the unit is then '
ready for a succeeding earthquake). The tapes can be played back on a SMP-1 playback which is rack mounted with the SMA-3 unit. This provides a strip chart record of the acceleration. 9 DC0036 371I
~
N N
'l AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) - ~
DATE 7/6/83. PAGE 38 op 40 L TITLE. EARTHQUAKE The base slab accelerometer output also goes to an earthquake
; force monitor unit (EFM-1), which simply contains three indicators (one each axis) which read out in percent of g. The indi.cator pointer is held at its maximum reading until reset, so peak acceleration can be determined, p0ST - EARTHQUAKE CHECK WTE: Spare cassettes and plates are stored in the chart room adjacent to the control room.
- 1. Replace the cassettes in the SMA-3 recording system following the retrieval instructions on page 9 of Record No. 683697-15. Insure that a post-earthquake calibration is put on tape before removal.
Play back the cassettes and record the peak acceleration. Since the SMA-31s a higher class instrument than CFM-1, base subsequent action on the peak " base-slab" acceleration recorded by the SMA-3 if this reading is greater than the EFM-1. Keep the strip charts with the other records of the quake. Send the cassettes to the Supervising Nuclear Generation Engineer (Nuclear Operations) in the G.O. Department of Nuclear Plant Operation with instructions to pass on to the Chief Civil Engineer. ( ) If the acceleration on the EFM has greater 0.5 g's, determine the actual peak acceleration from unit containment base slab as follows:
- a. Play back the tapes on the position #1 of the play back recorder.
- b. Find the highest peak (either positive or negative) for the highest acceleration,
- c. Convert to g's. The scaling on this range is 1.0 9 . (For range 2 20.5 g's; for range 4 20.25 g's; for range 10 : 0.1 g's)
- 2. If the maximum acceleration indicated by the earthquake force -
! monitor is greater than 0.1g, replace the recording plates in the Engdahl peak shock recorder and peak acceleration recorders (PAR's).
- 3. Measure to the nearest hundredth of an inch the length of the scribe marks (maximum distance of the scratched record from the zero line) on each plate from the peak shock recorder using the l I OC0036 38II
N N DiAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 7/6/83 O
.( ~
PAGE 39 OF 40 m LE: EARTHQUAKE e magnifying scale provided. Record the length of the scribe on the appropriate attached data sheet noting the recorder serial number and the reed number. Convert the scribe length in inches to the equivalent static acceleration by multiplying by the acceleration sensitivity. Record this value on the data sheet. Fomard one copy of the data sheet, as well as the plates, to the Depu cment of Nuclear Plant Operations for transmittal to the Chief Civil Engineer. Retain the original copy for the plant records.
- 4. When removing or installing PAR record plates, use the following procedure:
- a. Remove the record access plugs from the PAR housing,
- b. Remove or install the PAR record plates.
CAUTIW: It is important not to move the scribe arms of the PAR in the measurement axis direction while removing or installing PAR record plates. This will avoid false indications on the record plates.
- c. Record the serial numbers of all PAR record plates and corresponding PAR location following removal on the data sheet.
- d. Record the time and date of removal on the PAR record plates and dKta sheet.
- 5. Measure, to the nearest thousandth of an inch, the length of the scribe mark (maximum distance of the scratched record from the zero line) on each record plate from the PAR's using the magnifying scale provided. Record the length of the scribe on the appropriate attached data sheet noting the PAR number and the record plate serial numbers. Convert the scribe length, in inches, to the equivalent static acceleration by multiplying by the acceleration sensitivity of the PAR. Record this value on' the data sheet. Forward one copy of the data sheet, as well as the PAR record plates, to the Department of Nuclear Plant Operation, Supervising Nuclear Generation Engineer, for transmittal to the Chief Civil Engineer. Retain the original copy for the plant records.
D DC0036 39II l l l l .
NUMBER EP M-4 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 7 DATE 7/b/83 PAGE 40OF 40 Titte. EARTHQUAKE l
- The nominal acceleration sensitivities for Engdahl PAR's model
. number PAR 400-1 (2g) and PAR 400-2 (59) are 10 g/ inch and 25 g/ inch, respectively.*
- Based on a nominal full scale deflection of 0.200 inches, l
l i O l l O DC0036 40I1
=
1 I l lt i l t M
- f. .
b I I E I m = . b p G llE 2 g 8 < i*3 W 0! E= 5
+g p ba- 5
-b s
$"g E 8ea c=
E Ws
- W o
= w w lE 5 E -
Q W D E
~
~
5.-. 5
- 1 8 5 m -
- c. s i e 8 E Y (hl _
=
5
- w M g a t
t e. W w
i Page 1 of 1 18-924810/77(50) COAST VALLEYS DIVISION DIABLO CANYON POWER PLANT UNIT N05.1 AND 2 POST-EARTHQUAKE EVALUATION
SUMMARY
/
- 1. DATE/ TIME OF QUAKE MWE, UNIT 2 MWE
- 2. POWER LEVELS: UNIT 1
- 3. PEAK ACCELERATION (FROM EFM-1)
G; VERTICAL G NORTH-SOUTH G: EAST-WEST TIME / INITIALS 4 CHECK LISTS Seismic Instrument Procedure
/
a.
- b. Level Indicator Check List
/
Surveillance Test Check List
/
c.
- d. Electrical Power Check List
/
O e. Area Inspection Check List / REMARKS: Epicenter: Magnitude 5. Obtain day after the earthquake from U.C. Berkeley Seismographic Station - (415)642-2160. Reviewed by: l Power Production Engineer
\
Date/ Time /
j
)
Page 1 of 3 l 18-9249 10/77 (50) COAST VALLEYS DIVISION l DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 90KT.EARTHot1AKE LEVEL INDICATOR CHECK LIST UNIT DATE Check the indicators twice, at about 15 minutes to 1 hour
- . INSTRUCTIONS:
, apart.
Inform the Shift Foreman of any reading outside of its nonnal range, or which changes by more than expected in the interval. LEVEL / TIME UNIT 1 Reading 2 Reading 1 Vertical Board 1 / LI-139 CCW Surge Tank /
/
/
LI-140 CCW Surge Tank ,
/ /
LI-930 Spray Additive Tank LI-931 Spray Additive Tank / _
/
/ /
LI-940 Containment Receiver Sump LI-941 Containment Receiver Sump / _
/
Vertical Board 2_ LI-920 Refueling Water S.T. / /
/ /
LI-921 Refueling Water S.T.
/
O LI-921 Refueling Water S.T. /
/ /
LI-112 Volume Control Tank
/ /
LI-149 Primary Water Storage Tank Vertical Board 3 / LI-148 Condensate Storage Tank / __
/ /
LI-147 Transfer Tank _
/
/
LI-144 Raw Water Res. 01 A
/ /
LI-145 Raw Water Res. 01B /
' /
LI-148 Fire Water S.T. _CNWON l Aux. Bldg. Control Panel
/ / l L1-180 Monitor Tank 1-1 /
/ __
l LI-181 Monitor Tank 1-2 _
/ l
/
LI-188 RCOT 1-1 /
/ /
LI-60 Containment Sump 1-1
/
/
LI-61 Containment Sump 1-2
/ /
LI-62 Reactor Cavity Sump 1-1
/
/
LI-229 Waste Conc. Holding Tank
- 1
Paga 2 of 3 18-9249 10/77(50) COAST VAli.EYS DIVISION DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 POST-EARTHOUAKE LEVEL INDICATOR CHECX LIST LEVEL / TIME Reading 1 Reading 2 Aux. Bldg. Control Panel (Cont.)
/ /
; LI-170 Liquid Holdup Tank 1-1 _
/
/
LI-168 Liquid Holdup Tank 1-2
/
/
LI-167 Liquid Holdup Tank 0-1
/
/
LI-168 Liquid Holdup Tank 2-1 LI-170 Liquid Holdup Tank 2-2 / / LI-165 Conc. Holding Tank / /
/
/
LI-158 Equip. Drain Rec. 0-1
/ /
LI-160 Equip. Drain Rec. 0-2 _
/ /
LI-162 Floor Drain Rec 0-1
/
/
LI-164 Ficor Drain Rec 0-2 /
/
LI-180 Monitor Tank 2-1 /
/
LI-181 Monitor Tank 2-2 /
/
LI-188 RCDT 2-1
/ /
LI-60 Containment Sump 2-1
/ /
LI-61 Containment Sump 2-2
/
/
LI-62 Reactor Cavity Sump 2-1 UNIT 2 , Vertical Board 1_ / LI-139 CCW Surge Tank / _
/ /
LI-140 CCW Surge Tank
/
/
LI-930 Spray Additive Tank
/
/
LI-931 Spray Additive Tank _
/ /
LI-940 Centainment Receiver Sump l / / ! LI-941 Containment Receiver Sump
/
Vertical Board 2 / LI-920 Refueling Water Storage Tank /
/ _/
LI-921 Refueling Water Storage Tank
/ / __
LI-922 Refueling Water Storage Tank
/
/
LI-112 Volume Control Tank / LI-149 Primary Water Storage Tank / _ O.
Page 3 of 3 18-9249 10/77 (50) l COAST ALLEYS DIVISION ' DIABLO CANYON POWER PLANT UNIT NOS.1 AND 2 POST-EARTHOUAKE LEVEL INDICATOR CHECK LIST LEVEL / TIME _ Reading 1 Reading 2 Vertical Board 3_
/ /
' LI-148 Condensate Storage Tank LI-147 Transfer Tank
/ -
/
/ /
LI-144 Raw Water Res. 01 A
/ /
LI-145 Raw Water Res. 018
/ /
LI-148 Fire Water Tank Data Taken By: REMARKS: Reviewed By: Date/ Time / Shift Foreman: 1 l O i
Pag) 1 of 10 18-9250 10/77 (50) COAST VALLEYS DIVISION DIABLO CANYON POWER PLANT ( . POST-EARTH 00AKE AREA INSPECTION CHECK LIST' CONTAIMENT (OUTSIDE MISSILE SHIELD 1 CHECKED BY _ TIME /DATE
- UNIT 1 AREA - 6* (ELEV.140' & AB0VE) INCLUDING DOME
& LINEAR, SPRAY HDRS. & PIPING, ETC.
/
/ l AREA - 17 (ELEY. 117')
_/ , AREA - 30 (ELEY. 91')
\
CHECKED BY TIME /DATE , UNIT 2 l AREA - 9 (ELEV.140' & ABOVE) INCLUDING DOME /
& LINER, SPRAY HORS. & PIPING, ETC.
l
/
AREA - 25 (ELEV. 117')
]
AREA - 40 (ELEY. 91') REMARKS: l REVIEWED BY: SHIFT FOREMAN TIME /DATE / (
- Area designations refer to Attactment 1 to Emergency Procedure M-4.
Pag) 2 of 10 18-9250. 10/77 .(50) COAST VALLEYS DIVISION DIABLO CANYON POWER PLANT POST-EARTHOUAKE AREA INSPECTION CHECX LIST CONTAINMENT (INSIDE MISSILE SHIELD)_ NOTE: To be completed only if Unit is shut down. UNIT 1 CHECKED BY TIME /DATE AREA - 16* (ELEY.117') /
/
AREA - 29 (ELEV. 91') AREA - 44 (BELOW ELEV. 91') / UNIT 2 CHECKED BY TIME /DATE AREA - 24 (ELEV. 117') / AREA - 29 (ELEV. 91') / AREA - 51 (BELOW ELEY. 91' / REMARKS: REVIEWED BY: SHIFT FOREMAN TIME DATE /
- Area designations refer to Attactment 1 to Emergency Proceddre M-4.
. Page 3 of 10 18-9250 10/77 (50)
COAST VALLEYS DIVISION g DIABLO CANYON POWER PLANT POST-EARTHQUAKE AREA INSPECTION CECK LIST _ AUXILIARY BUILDING (MAIN AREAL CHECXED BY TIME /DATE
- UNITS 1 & 2
/
AREA - 10* (ELEY.140') / AREA - 10A (ROOF AREA & EQUIP. ABOVE ELEV.140') / AREA - 13 (ELEY.115' & 126') / AREA - 19 (ELEV.115') f AREA - 20 (ELEY. 127') / AREA - 21 (ELEV.115') / AREA - 22 (ELEV.115') _/ AREA - 32 IELEY. 100') / AREA - 33 (ELEY.100') / AREA - 34 (ELEY.100') / AREA - 35 (ELEV.100') / AREA - 45 (ELEV. 85') /
- AREA - 46 (ELEV. 85') /
AREA - 47 (ELEY. 85') / AREA - 48 (ELEV. 85') / ' AREA - 52 (ELEY. 73') / AREA - 53 (ELEY. 73') / AREA - 54 (ELEV. 60' & 64') _/ AREA - 55 (ELEV. 60' & 64') / AREA - 56 (ELEY. 60' & 64') _/ AREA - 57 (ELEV. 64') . REMARKS: REVIEWED BY: SHIFT FOREMAN IO TIME /DATE /
- Area designation refers to Attachment 1 of Emergency Procedure M-4.
Page 4 of 10 ', 18-9250 10/77(50) COAST VALLEYS DIVISION DIABLO CANYON POWER PLANT POST-EARTHQUAKE AREA INSPECTION CHECK LIST _ AUXILIARY BUILDING (PENETRATION AREAS) UNIT 1 ._ CHECXED 8Y TIME /DATE
/
AREA - 7 (ELEY. 140')
/
AREA - 18 (ELEY.115')
/
AREA - 28 (ELEY.100')
/
AREA - 43 (ELEY 85') UNIT 2 CHECKED BY TIME /DATE AREA - 8 (ELEY.140') / ,
/
AREA - 23 (ELEY.115') AREA - 38 (ELEY. 100') /
/
AREA - 49 (ELEY. 85') REMARKS: __ G . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . . . . . _ _ _ _ _ _ _ . _ . _ _ _ _ - . _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ _ .__________O
Page 5 of 10 18-9250 10/77 (50) - COAST VALLEYS DIVISION DIABLO CANYON POWER PLANT POST-EARTHQUAKE AREA INSPECTION CHECX LIST. FUEL HANDLING BUILDING (MAIN AREA) CHECXED BY TIME /DATE UNIT 1
/
AREA - 2 (ELEY.140' }
/
AREA - 3 (ELEY. 140') HOT SHOP AREA AREA - 12 (ELEV.115' & 126')
/ _
AREA - 27 (ELEY.100')
/
CHECKED BY TIME /DATE UNIT 2
/
AREA - 4 (ELEV. 140')
/
AREA - 14 (ELEY.115' & 126')
~
AREA - 36 (ELEY.100* )
/
REMAR d: O
Page 6 of 10 18-9250 10/77 (50) COAST VALLEYS DIVISION DIABLO CANYON POWER PLANT POST-EARTHQUAKE AREA INSPECTIOff CHECK LIST FUEL HANDLING BUILDING (VENT. EQUIPMENT AREAS)_ CHECKED BY TIME /pATE UNIT 1
/
AREA - 1 (ELEY. 140') .
/
AREA - 11 (ELEV.115')
/
AREA - 26 (ELEY. 100')
/
AREA - 42 (ELEY. 85') _ CHECKED BY TIME /DATE UNIT 2
~ AREA - 5 (ELEY.140')
/
AREA - 15 (ELEY.115')
/ g
/
AREA - 37 (ELEV.100') . AREA - 50 (ELEV. 85')
/
REMARKS: l O. l l
Pa9e 7 of 10 18-9250 10/77 (50) COAST VALLEYS DIVISION
! DIABLO CANYON POWER PLANT POST-EARTHOUAKE AREA INSPECTION CHECK LIST UNIT 1 TURBINE BUILDING _
CHECKED BY TIME /DATE _ UNIT 1 _
/
AREA - 58 (ELEY.140')
/
AREA - 60 (ELEV.107' & 119')
/
AREA - 61 (ELEY.119' & 125')
/ .,
AREA - 62 (ELEY.119' & 123')
/ _
AREA - 65 (ELEY. 107')
/
f AREA - 66 (ELEY.104' & 108')
/
AREA - 67 (MACH. SHOP OVERHEAD) _/ AREA - 31 (ELEV.109') MN. STM. LINE PLTFM.
]
AREA - 70 (ELEY. 85' & BELOW)
]
AREA - 71 (ELEV. 85')
/
AREA - 72 (ELEV. 85' & BELOW)
/ _
AREA - 73 (ELEV. 83' & BELOW)
- /
AREA - 74 (ELEV. 85') REMARKS: O r
Page 8 of 10 18-9250. 10/77 (50) COAST VALLEYS DIVISION DIABLO CANYON POWER PLANT POST-EAP.THQUAKE AREA INSPECTION CHECK LIST
- UNIT 2 TURBINE BUILDING CHECKED BY TIME /DATE UNIT 2
/ >
AREA - 59 (ELEV. 140') J' AREA - 63 (ELEV.119' & 125')
/
AREA - 64 (ELEV.107' & 119')
/
AREA - 68 (ELEY.104' & 108')
/
AREA - 41 (ELEV.109') MN. STM. LINE PLTFM.
/
AREA - 69 (ELEY.1078 )
/
AREA - 75 (ELEY. 85' & BELOW)
/
AREA - 76 (ELEY. 85' & BELOW)
]
AREA - 77 (ELEV. 85' & BELOW) f AREA - 78 (ELEY. 85') REMARKS: S.
Page 9 of 10 18-9250 10/77 (50) . . 3 C0AST VALLEYS DIVISION
, DIABLO CANYON POWER PLANT i
POST-EARTHQUAKE AREA INSPECTION CHECK LIST _ OUTSIDE AREAS CHECKED BY TIHE/DATE ,, AREA - 79 (UNIT 1 F.H. BLDG. EXTERIOR, STOR. TKS, STOR. AREAS, ETC.) 1 AREA - 80 (UNIT 2 F.H. BLDG. EXTERIOR. STOR. TKS, STOR. AREAS, ETC.) / , AREA - 81 (UNIT 1 BLDG. EXTERIORS, M. AUX,
& STUP. XFiW. BKS. & STRUCTURES, ETC.) / ,_
l
- AREA - 82 (UNIT 2 BLDG. EXTERIORS, 2, & AUX. !
XFMR. BKS. & STRUCTURES, ETC.) / AREA - 83 (UNITS 1 & 2 DISCH. STRUCTURE)
/
/
AREA - 84 (230 KV SWYD. & LINES) O - AREA - 5 ( AW WTR. 510R. ,0NOS, ,
/
AREA - 86 (500 KV SWYD. & LINES) - 1 REMARKS: l 4 e e
- i O
( Pag] 10 of 10 18-9250 10/77 (50) , COAST VILLEYS DIVISION ' DIABLO CANYON POWER PLANT POST-EARTHQUAKE AREA INSPECTION CHECK LIST _ INTAKE STRUCTURE CHECKED BY TIME /DATE AREA - 87 (ELEY.17.5') ___/ 1 AREA - 88 (ELEY. -2') AREA - 89 (AUX. SALT WATER PUMP COMPARTMENTS /
& VENT. SHAFTS)
/
AREA - 90 (PIPE & DISCHARGE VALVE GALLERIES) REMARKS: O 0,
Page 1 of 1 18-9251 10/77 i(50) COAST VALLEYS DIVISION (O DIABLO CANVON POWER PLANT UNIT N05.1 AND 2 POST-EARTHQUAKE SURVEILLANCE TEST CHECK LIST _ UNIT DATE INSTRUCTIONS: Check the data sheet with the time test is completed and the initials of the person performing the test. TIME / INITIALS A. Instrument Surveillance Tests /
- 1. 1-1,ChannelCheck(shiftanddaily portions only)
/
- a. Shift Data Sheet
/
- b. Daily Data Sheet
/ -
l 1-29, Emergency Signals and Consnunications 2. System Functional Test B. Reactor and Auxiliaries
/
- 1. R-1A, Exercising Full Length Control Rods
/
.2. R-10, Reactor Coolant System Leakage Evaluation .
C. Miscellaneous and Integrated Tests
/
' 1. M-16B Operation of Slave Relays K604A and K6048 (Safety Injection.
/
- 2. M-16C Operation of Slave Relay K608A (Safety Injection).
M-160 Operation of Slave Relay K6088
/
3. (Safety Injection). M-16E Operation of Slave Relay K633A
/
4. and K609A (Safety Injection and Auxiliary FW Pump Start).
/
- 5. M-16F Operation of Slave Relay K6338 and K6098 (Safety Injection and Auxiliary FW Pump Start).
M-16I Operation of Slave Relays K606A
/
6. and K6068 (Phase A Containment Isolation). REMARKS: Reviewed by: Power Production Engineer Date/ Time /
pag, i of j n, 18-9252 10/75 (50) {
- C0AST7 ALLEYS DIVISION DIABLO CANYON POWER PLANT UNIT N05.1 AND 2 2O ELECTRICAL POWER CHECK LIST DATE:
l _ INSTRUCTIONS: Insure that the lines indicated are functioning properly. ' Insure that the batteries are undamaged and that the chargers coatiflue to supply the load. Start all diesels and bring them to rated voltage.
*I
' TIME / 'IMITIALS _
A. 500 KV System Midway #2 line
/
1.
/
- 2. Midway f3 line '
i
/
- 3. Gates line
/
- 4. Tie line to Unit 1 , , _
/
- 5. Tie line to Unit 2
/
- 6. 500 KV Switchyard B. 230 KV System Morro Bay-Diablo line /
1. Morro Bay-Mesa line / 2.
/
- 3. Tie line to startup bank 1-1
/ '3 4. Tie line to startup bank 2-1 230 KV Switchyard /
5. C. Station Batteries & Chargers
/
- 1. Battery 1-1
/
- 2. Battery 1-2
/
- 3. Battery 1-3
/
- 4. Battery 2-1
/
- 5. Battery 2-2
/
- 6. Battery 2-3 D. Diesel Generators
/
- 1. Generator 1-1
/
- 2. Generator 1-2
/
- 3. Generator 1-3
/ _
- 4. Generator 2-1
/
- 5. Generator 2-2 REMARKS:
O Reviewed By:
/
Date/ Time Shift Foreman
18-10291 5/81 (10) . Page 1 of 3 _ PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS
^ DIABLO CANYON POWER PLANT UNIT NOS.1 AND 2 I
- CALIBRATION AND TEST DATA SHEET
~
- PEAK SHOCK RECORDER PSR1200 H j
701 March 23,1981 INITIALS CALIBRATION DATE RECORDER S/N __
"' SURFACE -
RECORD PLATES S/N - EQUIVALENT ACCELERATION DISPLACEMENT STATIC REED FREQ'JENCY SENSITIVITY (inches) ACCELERATION NUMBER (Hertz) (g/ inch) (g) I 1.94 0.353 2 2.57 0.552 3 3.12 0.853 4 3.83 . 1.20 iO* , 5 5.43 2.23 6 6.45 3.41 7 8.06 5.08 8 10.3 7.82 : 9 12.6 12.9 l 10 16.2 19.5 , 11 20.1 29.65
~
12 25.7 49.3 Damping: 2% viscous damping (Q of 25) TEST DATE TESTER PREPARED BY TEST LOCATION . DATE ( TEST NUMBER
- Values based on Kinemetrics Calibration Test Report and Certification for DCPP Seismic Instrumentation.
18-10291 5/81 (10) Page 2 of 3 PACIFICGASANdELEbTRICCOMPANY ' DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS.1 AND 2' CALIBRATION AND TEST DATA SHEET D PEAK SHOCK RECORDER PSR1200 - H 710 CALIBRATION DATE March 23,1981 INITIALS _ RECORDER S/N i RECORD PLATES S/N SURFACE QUI M ENT ACCELERATION DISRACEMENT STATIC SENSITIVITY ACC LERATION REED FREQUENCY (g/ inch) (inches) NUMBER (Hertz) 1 1.90 0.339 2 2.48 0.54 5 1 3 3.21 0.822 4 3.80 1.20 h 5 5.37 2.22 6 6.52 3.20 i 7 7.97 5.03 8 10.0 7.36 9 12.8 12.1 f l 10 16.1 20.3 Il 20.2 30.6
~
I 12 25.6 45.8 l l Damping: 2". viscous damping (Q of 25) l TEST DATE TESTER PREPARED BY O TEST LOCATION DATE TEST NUMBER . l \
~
" Page 3 of~3 18-10291 5/81 (10)
PACIFICGASdNDE'LECTRICCOMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 CALIBRATION AND TEST DATA SHEET E ' PEAK SHOCK RECORDER PSR1200 - V 728 CALIBRATION DATE March 23, 1981 INITIALS RECORDER S/N SURFACE RECORD PLATES S/N EQUIVALENT ACCELERATION DISPLACEMENT STATIC P.EED FREQUENCY SENSITIVITY (inches) ACCELERATION NUMBER (Hertz) (g/ inch) (g) I 1.89 .299 2 2.45 .485 3 3.20 .823 4 3.87 1.11, 5 5.21 2.08 6 6.38 3.05 7 8.20 5.00 t 8 10.2 7.64 l 12.1 I 9 12.6 10 15.9 18.1 l 11 20.2 29.1 12 25.3 44.1 Damping: 2% viscous damping (Q of 25) TEST DATE TESTER PREPARED BY TEST LOCATION DATE _ TEST NUMBER
# Page 1 of 2 69-9283 (10) 10/81 PACIFIC GAS AND. ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERAT10NS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 .
E: CALIBRATION AND TEST DATA SHEET -PEAK ACCELERATION RECORDER _ - EP M-4 669 DATE TIME PAR 400- 1 RECORDER S/N RECORD PLATE S/N 517 CAL. DATE 9/29/81 LOCATION; CONTAINMENT SASE SLAB UNIT 1.EL. 89',180* DISPLACEMENT ACCELERATION PERFORNED BY SENSOR ACCELERATION SENSITIVITY g/in l g/ml Inches l m (g) L 16.3 0.640 T I 16.1 0.635 I V 15.4 0;606 i l i PAR 400 2 RECORDER S/N 654 DATE , TIME RECORD PLATE S/N 51 6 CAL. DATE 1 0/2/81 i LOCATION: TOP OF UNIT 1 CONTAINMENT, EL.303.5', 225* aENSOR ACCELERATION DISPLACEMENT ACCELERATION PERFORMED BY l SENSITIVITY i m (g) l f I g/in g/m Inchesi L 32.5 .1.28 T l l 30.1 1.18 V 32.3 1;27 TIME PAR 400- 1 RECORDER S/N 673 DATE RECORD PLATE S/N S21 CAL. DATE 10/1/81 LOCATION: INTAKE NEAR ASW PUMP 1-2 BAY. EL. 2' SENSOR ACCELERATION DISPLACEMENT ACCELERATION PERFORMED BY l SENSITIVITT l g/in g/m Inchesl m1 (g)
- 13.1_ 0.51 5 T 15.4 0.606 ,
( m V 13.8 0.543
Page 2 of 2 69-9283 (10) 10/81 , TITLE: CALIBRATION AND TEST DATA SHEET - PEAK ACCELERATION RECORDER -EP M-4 PAR 400- 1 RECORDER S/N 672 DATE TIME RECORD PLATE S/N 520 CAL DATE 9/29/81 LOCATION: TURBINE BUILDING, MACHINE SHOP EL.85' ACCELERATION PERFORMED BY SENSOR ACCELERATION DISPLACEMENT SENSITIVITY g/in g/m Inches m (9) l 16.2 0.635 T 15.6 0.61 5 V 14.2 0.558 TIME PAR 400- 1 RECORDER S/N 682 DATE RECORD PLATE S/N 526 CAL DATE 9/29/81 LOCATION: AUXILIARY BUILDING, HOT SHOP EL.140' DISPLACEMENT ACCELERATION PERFORMED BY l SENSOR ACCELERATION SENSITIVITY g/in_ 9/m Inches m (g) L 15.3: 0.601 T 15.4, 0.608 V 12.7 0.500 PAR 400- 1 RECORDER S/N 683 DATE TIME RECORD PLATE S/N 527 CAL DATE 9/29/81 LOCATION: AUXILIARY BUILDING NEAR CONTROL ROOM 000R EL. 140' DISPLACEMENT ACCELERATION PERFORMED BY SENSOR ACCELERATION SENSITIVITY g/in 9/m Inches m (g) L 16.2 0.635
.T 16.0 0.630 V 14.3 0.562 h
. i NWBER EP M-6 p@q$
Pacific Gas and Electric C0mpany REylSION 8 DEPARTMENT OF NUCLEAR PLANT OPERAT!ONS DATE 7/5/83 1 AND 2 PAGE 10F 10
) DIABLO CANYON POWER PLANT UNIT NO(S) l f EMERGENCY PROCEDURE L 737ts; NONRADIOLOGICAL FIRE b})
APFAOVED: _ hlhh PLANTMAyER DATE SCOPE l This procedure discusses the actions which are taken in the event of a fire which does not involve radioactive materials This procedure and changes thereto requires PSRC review. , GENERAL Fires at Diablo Canyon can be classified as either radiological or nonradiological . Nonradiological fires do not involve either radiation or radioactive material. Examples of such fires are fires in the turbine building or outside grass fires. Radiological fires are handled in accordance with Emergency Procedure R-6, " Radiological Fires". SYMPTOMS
- 1. A fire is discovered outside the plant or inside the plant in an area where no radioactivc materials are located.
- 2. The fire detection system may indicate the presence of a fire within the plant.
AUTOMATIC ACTIONS The Sprinkler, Deluge, Halon, Cardox, or Intake'C02 fire systems may activate IMEDIATE ACTION l ' 1
- 1. Activate the fire signal by dialin s a code which gives the location of the fire (see able 1 . fire signal is a 30
! second blast on the fire sirens. The signal will be followed by the
, location code of the fire on the code call system repeated 8 times.
The first five persons to dial 76 will be connected into a conference call. The priority of the conference call is:
- a. Shift Foreman (Interim Site Emergency Coordinator).
- b. Senior Control Operator (Fire Brigade Leader). l
. J (O
O DC0004 IIII
P . 1 AND 2 NUMBER EP M-6 DIABt.O CANYON POWER PLANT UNIT NO(S) REVISION 8 DATE 7/5/83 PAGE 2 Op 10 TITLE. HONRADIOLOGICAL FIRE
. c. Assistant Fire Brigade Leaders (Two).
? d. Plant Superintendent / Manager.
- e. Fire Marshal .
- 2. The Shift Foreman and Senior Control Operator will dial 76 and be given the details regarding the fire, including the exact location and potential damage to the plant.
I 3. Members of the on-shift fire brigade should report to the control room l to pick up their equipment and receive instructions from the Shift Foreman. The Shift Foreman is responsible for establishing an appropriate on-shift emergency organization and assuring that Technical Specifications for control room staffing are not violated.
- 4. If the fire occurs during normal working hours, members of the Maintenance Fire Brigade should go to the cold machine shop. The Assistant Fire Brigade leaders should enter the conference call to receive their instructions.
- 5. If appropriate, isolate (Mode 3) the control room ventilation system to prevent the entry of smoke. If the fire is within the control i
room, change the ventilation system to Mode 2 for 100% outside air makeup.
- 6. If the fire is in an area protected by either the cardox, halon or deluge systems, manually initiate these systems from the panel in the control room or locally.
- 7. Clear the area affected by the fire. This may be done by sounding the site emergency signal, or other appropri, ate means.
SUBSEQUENT ACTIONS The Shift Foreman, acting as Interim Site Emergency Coordinator, shall direct all subsequent actions from the control room until relieved by the long tenn Site Emergency Coordinator if the emergency warrants it. Such actions should include the following:
, 1. If the fire is a grass fire, notify the California Department of Forestry and give details regarding the fire.
I
- 2. If the fire cannot be physically contained and controlled promptly !
with available resources, or if the Fire Brigade Leader reconinends, assistance from the California Department of Forestry should also be requested. Refer to Appendix 1 for telephone numbers. O. DC0004 2111
0 , NU8dDER EP M-6 1 AND 2 DIABLO CANYON POWER PLNiT UNIT NO(S) . REVISION 8 DATE 7/5/83 TITLE. NONRADIOLOGICAL FIRE f(JTE: 1) If outside assistance.has been re ested, have notify themthe notify the Security Departrent - f. Avila Gate. One or a re pian ating personnel shall be dispatched to the Security Butiding to escort CDF crews to the scene of the fire. Security Officers may be requested to escort off-site fire fighters to the appropriate plant access door.
- 2) Maintain a record of notification r:ade to offsite personnel.
Form 69-9221 " Emergency Notification Record" may be used to provide this record.
- 3. If CDF is called to respond, insure that the person calling CDF gives a name and number to call back the plant. Provide CDF with details concerning location and type of fire. Also give CDF an update of fire conditions even before they arrive as they may decide to send more support.
- 4. If CDF responds, their first responding chief officer will identify himself. He may initially decide to go to the scene of the fire. He will eventually desire to contact the PGandE Site Emergency Coordinator. Therefore escort and access should be provided to him to l
reach either the Control Room or TSC depending on where the Site Emergency Coordinator is located.
- 5. If the fire is a grass fire that is near the plant, a person such as the Assistar.t Fire Brigade leader from the Maintenance Brigade should be dispatched to the scene. This person can then interface with QF and assist in providing equipment and manpower. l l
l
- 6. During the course of' the fire, the Control Operator and those at the /
scene should pay particular attentiran for signs that the operability of the various engineered safeguards equipment is being affected. If the operability of any safeguards equipment is reduced below minimum Technical Specifications limits, or if such damage is iminent, shut down the Unit irrmediately. NOTE: Operating Procedure K-2C provides the operator with listing of safeguards equipment which may be affected by fires in various
~
locations. This procedure should be consulted to assist in determining the operating strategy during the fire. A
- DC0004 3111
NUMBER EP N-6 DIA LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 - REVIS:ON 8 DATE 7/5/83 PAGE 4 OF 10 TITLE. HONRADIOLOGICAL FIRE
- 7. Establish an initial emergency classification based 0:e the criteria in
~
- Appendix Z and perfom the actions required by the classification.
- 8. If the control room must be evacuated, follow the instructions given in Emerger.cy Procedure OP-8.
- 9. If the deluge or cardox system has been activated, the system must be reset after the fire is extinguished. The reset buttons for the cardox system are located in the teminal boxes on the south side of the cardox assembly on the 104 foot elevation of the turbine building.
The reset buttons for the deluge system are located locally. If the tystem was activated by a thermal element, the themal element must be replaced before the system can be reset.
- 10. Supplied air breathing apparatus should be worn if smoke inhalation is a hazard. If self-contained breathing apparatus (SCBA) is being used, a crew should be dispatched to an air bottle refilling station and prepare to refill the backpack bottles as required. The stations are located at the northwest end of the Unit No. 2 component cooling water heat exchangers on the +85 foot elevation and on the +140 foot elevation behind the control room.
- 11. Close out with verbal sumary to offsite organizations and complete the following written reports:
- a. Plant Problem Report (see Nuclear Plant Administrative Procedure C-12).
- b. Written summary to NRC within 24 hours for an Unusual Event or 8 hours for a higher classification.
- 12. If the fire is put out before CDF arrives,*they may still request to send one engine company to the site for their close out.
i DC0004 4III i
l i NUMBER EP M-6 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISON 8 DATE 7/5/83 O TITLE: NONRADIOLOGICAL FIRE PAGE 5 Op 10 SPECIAL CONSIDERATIONS REGARDING BRUSH FIRES Because of the danger of rapid spreading, the Department of Forestry l i' 1. shculd always be called in case of a brush fire. l
- 2. A fire trailer containing 300 gallons of water is located south of the Administration Building near the circulating water discharge gate structure for fighting grass fires. Portable fire fighting packs are located on the trailer.
- 3. When fighting a brush fire there are several basic precautions which should be taken by plant personnel engaged in fire fighting:
- a. Always remain upwind on the fire.
- b. Remain downhill of the fire, if possible.
- c. Watch for fires circling behind the fire fighters.
> ( 1 DC0004 SIII
OiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 y, [ Dt,TE 7/5/83 PAGE 6 Op 10 TITLE. NONRAD:0 LOGICAL FIRE REFERENCES
. 1. Diablo Canyon Power Plant.- Fire Protection Plan
- 2. Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation."
- 3. Emergency Procedure G-2 " Establishment of the Onsite Emergency Organization."
- 4. Emergency Procedure G-3 " Notification of Offsite Emergency Organizations."
- 5. General Operating Orders - 1.300 and 1.301
- 6. PGandE Fire Prevention Manual
- 7. Accident Prevention Rule No. 23
- 8. Emergency Procedure R-6, " Radiological Fire."
ATTACHMENTS
- 1. Fonn 69-9221, " Emergency Notification Record."
l l l 0C0004 6111 i
DrAeto CANYON POWER PLANT UNIT NO(S) . . 1 APID 2 g DATE 7/5/83 PAGE 7 OF 10 TITLE. NONRADIOLOGICAL FIRE TABLE 1
; FIRE CODE CALL LOCATIONS CODE LOCATIONS Control Building No. 1 Containment No. 1 Turbine Building No. 1 Auxiliary Bldg.
No.1 Fuel Handling Building Package Boiler Area Hot machine shop area No. 2 Containment No. 2 Turbine Building No. 2 Auxiliary Bldg. No. 2 Fuel Handling Building Security Diesel Area Grass fire Outside Transformer Fire O-: Intake structure 500 kV switchyard 230 kV switchyard Radwaste Storage All clear Fire Orill Test fire code Administration Building Security Building Training Building Assembly Building Technical Support Center . (0 DC0004 7111 s
N M8 ciaBLo CANYON POWER PLANT UNIT NO(S) 1 AND 2 , g , cATE 7/5/83 , PAGE 8 OF 10 ()l TITLE- NONRADIOLOGICAL FIRE I l l APPENDIX 1
FIRE ASSISTANCE COM.MUNICATION 543 4242 (Emergency Only)
- 1. California Department of Forestry 543-4244 (business)
OR San Luis Obispo County Sheriff 1. Automatic Tie Line (Request they dispatch the (Control Room & TSC) California Dept. of Forestry) or
- 2. Radio (Control Room, TSC or Security) 1 or 2
- 3. 543-7911 (Emergency Only) 543-2850 (business)
~'
Fire Marshal Plar.t Extension s
- 2. Hone Phone ;.
Randy Kohout or - HP Freq Pager Call (Group Call h e l l 1 9 OC0004 8III .
l l oiAsLO CANYON POWER PLANT UNIT NO(S) ,1 AND 2 RE
. DATE 7/5/83 PAGE 9 OF 10 TITLE: NONRADIOLOGICAL FIRE l l
APPENDIX Z j
.f EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been implemented, and upon direction from the Shift Foreman, proceed as follows:
- a. Designate this event a Notification of Unusual Event for fires within the site boundary if a verified fire is not under control within 10 minutes of initiating fire fighting efforts or if the California Department of Forestry Assistance is requested.
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-1 " Accident Classification and Emergency Plan Activation."
- b. Designate this event an ALERT if a verified fire is not under control within 10 minutes of initiating fire fighting efforts and the fire is located in one of the following areas containing safety systems:
- 1) Containment
- 2) Control Room
- 3) Cable Spreading Room
- 4) Diesel Generator Room
- 5) Auxiliary Building
- 6) Intake Structure Pump Room Notify Plant Staff and response organizations required by EP G-2 and EP G-3 in accordance with EP G-1.
- c. Designate this event a Site Area Emergency if a verified fire is not under control within 10 minutes of initiating fire fighting efforts in an area containing safety systems, and causes a confimed loss of a safety system function that causes entry into a technical specification action statement. Notify plant staff and response organizations required by EP G-2 and EP G-3 in
- accordance with EP G-1.
- d. Designate this event a General Emergency if the fire causes massive damage to plant systems which, in the opinion of the Site Emergency Coordinator, is likely to lead to a core melt situation. Notify plant staff and response organizations required by EP G-2 and EP G-3 and implement the instructions in EP G-1 regarding on and offsite protective actions.
O DC0004 9III
hUMBER EP M-6 , CtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ! REVISION 8 DATE 7/5/83 PAGE 100F 10 TITLE. NONRADIOLOGICAL FIRE APPENDIX Z (continued) 4 2. In addition to personnel required to be notified by EP G-2 also notify the following:
- a. Fire Marshal (See Appendix 1)
- b. System Dispatcher (if load may be affected).
NOTE: In off-normal working hours, consideration should also be given to calling in additional nembers of the Plant Fire Brigade. This should not take precedence over calling CDF. O P I DC0004 10III
-&-a i % I W
W w w M Z E M g M w E E. I 1 w C D E Z w
~ ~
W e
< C w
2 2 wW C C AZ U 4 O eC w W w M M WL hM ww -
- a. W Eev E 6 > >-
OO V CI3 e 3
>.- cs2 w Z et C
= cg wZ. =C W C
>-- E CI: w w 4 3 A U W 4 C w K
.=
WW 5_ W 4= 5 :! m W W l a 4 4 8 E
- m w
N W X w CX2 W -J
% C 4 m 4 y% W
>=
a
) Y
- a. s= .
w
@ W O-
@ K W
2 _ - - - --- , . ,_
. . . - - _ _ . __ u--------
? ) HDGWE Pacific Gas and Electric Company REvtSION 5 DATE 7/5/83 DEPARTMENT OF NUCLEAR PLANT OPERATIONS 1 AND 2 PAGE lOF 5 DIABLO CANYON POWER PLANT UNIT NO(S) EMERGENCY PROCEDURE TITLE. OIL SPILL ISOLATION AND CLEANUP 4* APPROVED: Y DATE PLANTMAg6ER SCOPE This procedure. outlines the steps required to isolate and clean up small oil spills that could occur during tank truck loading and unloading or during other plant operations. It is absolutely necessary that no oil reaches Diablo Creek or the ocean from spills that might occur. This precedure and changes thereto requires PSRC review. Dt4EDIATE OPERATOR ACTION
- 1. Perform any operation which can be done rapidly to stop the spill.
.; 2. Notify the Shif t Foreman.
SUBSEQUENT ACTION
- 1. Notify the following Company personnel.
- a. For all occurrences:
- 1) Plant Manager. .
Plant Superintendent. l
- 2) l
- 3) Supervisor of Operations. l
- 4) Supervisor of Chemistry and Radiation Protection, f^
- b. If any oil reaches the creek or the ocea*n:
- 1) Manager of Nuc, lear Plant Operations or his alternate.
- 2) Supervising Nuclear Generation Engineer (Personnel and Environmental Safety) or his alternate.
l
- 3) District Manager, Los Padres Distr'ict.
- 4) Onsite DER Marine Biologist.
<C DC0100 III l
NUMBER O 1 AND 2 ' REVISION 5 D iABLO CANYON POWCR PLAP T UN;T NO(S) /5/ DATE 5 PAGE 2 OF T TLE. OIL SPILL ISOLATION AND CLEANUP PROCEDURE .
- 5) PGandE Law Department.
Mr. David J. Williamson
- e. Company Phone: '
Home Phone: _J u PGandE Public Information Office, San Luis Obispo 6) j Ms. Suzanne G. Brown t Company Phone:' Home Phone: '
- 2. Notify the folloYing non-Company agencies if any oil reaches the Creek or ocean,
- a. Federal National Response Center.
U.S. Coast Guard l Washington, D.C. l Tel. (800) 424-8802 (toll free) l or Coast Guard San Francisco (Captain of the Port) Tel. (415) 556-3740 or Coast Guard Monterey (Captain of the Port)
- Tel. (408) 375-2278
\
' b. California State Office of Emergency Services Sacramento (ring down line) or
, Tel. (800) 852-7550 (toll free) 3 or l Tel. (916) 427-4341
.i e
- c. Environmental Protection Agency Tel. (415) 974-8131
^
G OC0100 21 6 i- ,
- N oiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2
, , p
. DATE 7/5/83 j PAGE 3 op 5 TITLE. OIL SPILL ISOLATION AND CLEANUP PROCEDURE
- d. California State Land Comission Tel. (213) 590-5201
- e. State - Executive Officer California Regional Water Quality Control Board Central Coast Region 1122 Laurel Lane San Luis Obispo, CA 94301 Tel. (805) 549-3147 (Request California Office of Emergency Services to notify in off-hours)
POTE: A record of all such notifications should be kept on Fonn E!Pi221. " Emergency Notification Record" or similar log.
- 3. Emergency Actions for Spills During Loading and Unloading of Tank Trucks.
t0TE: Operating Procedure K-8 requires that operating personnel be present during loading and unloading of tank trucks. This individual will be responsible for taking necessary action should an oil spill occur during these operations,
- a. Types of spills that could be expected:
- 1) Transfer hose connection at truck or tank breaks loose and oil spills onto pavement.
- 2) Transfer hose from tank truck breaks or cracks and oil spills onto pavement.
- 3) Overfilling of the diesal fuel oil tanks or the auxiliary boiler fuel oil tank.
- 4) Oil drain from the transfer hose after being disconnected.
- 5) A leak at the lube oil receiving connection occurs.
- b. Methods for oil spill containment and cleanup: l
- 1) Sand bags and aosorbents are stored near the diesel fuel oil storage tanks and the auxiliary boiler fuel oil storage tank for the purpose of diking and absorbing spilled oil.
( DC0100 31
N R N DIABLO CANYON POWER PLANT UNIT NCKS) 1 AND 2
--DATE 7/5/83 PAGE 4 Op 5 TiTLc. OIL SPILL ISOLATION AND Cl.EANUP PROCEDURE
- 2) Sand bags should be used to dike any significant oil
- spill which could flow to Diablo Creek or the ocean.
Once the flow of oil has been stopped, absorbents should be used to clean up the oil.
- 3) The absorbent should be used by itself only if the leak is of a small nature and a shallow film has been formed on the pavement. The absorbent can contain small spills by absorption.
- c. Action to be taken if truck is loading oil:
- 1) Shut off any transfer pump involved.
- 2) Isolate all connections to the transfer hose.
- d. Action to be taken if truck is unloading oil:
- 1) Close truck tanker drain valve.
- 2) If a leak occurs at the lube oil receiving connection, the transfer pumps must also be shut down and the connection isolated.from the lube oil storage tank.
- 4. Emergency Actions for Spill at Circulating Water Pump from Bearing Oil Pot
- a. Turn off sump pump at intake structure sump.
- b. Before turning on sump pumps mentioned in "a" above, clean oil from sump area.
- 5. Emergency Actions for Major Oil Spill in an Area Which Leads to the Turbine Building Sump
- a. Periodically check the sump to verify that it is not overflowing to the discharge side.
- b. Take samples periodically from the effluent of the oil water separator. If significant quantities of oil seem to be coming from the oil water separator, then redirect flow to the oil water separator holding tank.
- 6. Followup Reports
- a. Prepare a Nuclear Plant Problem Report (see Nuclear Plant Administrative Procedure C-12).
DC0100 41
~
R P M-7 oiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 7/5/83 - PAGE 5 on 5 TITLE. OIL SPILL ISOLATION AND CLEANUP PROCEDURE
- b. Written notification to the Executive Officer of the RWQCB is required within 5 days of awareness of the
" non-compliance.
The written report will include the information required by the RWQCB Water Discharge Requirements. A copy of the report should be provided to the NRC, Region V to meet NRC reporting requirements.
- c. Any letters or reports issued outside the company should be reviewed by Mr. David Williamson of the PG&E Law Department. .
REFERENCES
- 1. California Regional Water Quality Control Board - Centra: Coast Region, Order No. 82-24, NPDES No. CA0003751, Waste Discharge Requirements for PGandE Diablo Canyon Nuclear Power Plant Units 1 and 2, San Luis Obispo County.
- 2. Diablo Canyon EPA 011 Spill Prevention Control and Countermeasure Plan, Rev. 2,3/25/80.
ATTACHMENT
- 1. Form 69-9221, " Emergency Notification Record" DC0100 51
4 'e
, e a
1
$=*
W W W m W f* E W
>=
4 C 1 M E D
< C wp
==
b v b< C4 W W d = M W4 iE = E_
.m L >
4 U [3:
- C.j=< C E
v 4 > > CC U m a M wm l
=5 m We
.- E e z w w 4 Z 4 W w 4 W
M E_ W C E d ' 1
- m
>= 6
* .4 4 8 E 5 e N E w m
U 4 W s >
< s s= -
w
\ @ b
- m l
1 .
PGwE . DtABLO CANYON POWER PLANT gjg PROCEDURE.ON-THE-SPOT CHANGE eroe.ow,. No. @ Q-7 m.v.' 3 Una No.10 :O ia 2% r v emo o-ur as m-<.cr swor.suca m Auranwu _ Tp. of Ch.ng, h PERMANENT (gr n) OTEuaoa^av(W); c .ir. tion o.t. n.ou ., o.o.,,n -rwmutrat AsmAuer ong,n.or h R thaw er., e ch.ac. (oo eu. nor tre an.,u of ongn.l proc.du ? h h No)
. (Does'st constitut. n unr.v1 e4 s.fety/ enviro, ment.1 uestion? O,rts a no)
. i OP TATE. OF EMEREgy CALL our t.asT l
per ATrV-ED foo# 69-102S7 da.ted 74-63 ge5CI A)b CT5c DATED l-II '6 D I . I ( n ni.,cr ne. Mey pc.rsonnd Ao o,re. qdited b k Add'ed 6 4he. eveAt of an, wegucy ha.ve chaA3ul pa.hs eVor phs nuh. The vpW M ed List, M-lo297 khr.cl 7-6-63, re.4 fe64kca. Aanoramon.: .
~-
__< = = A .,n a y n d[
<r = u.n.#,n.n,se -isao -
7/ f o..r N t 4.t. istr4.ution to t,. controi .ne .u.cs a .r s uir.at a rEs yio initi.i o4str4 ution sy: Distri.uted To: O control Room C Otmers 5 .y oocu nt controi 1hsIL3 - 5 o.t. w .sv esac n. - .noe m u.n w . .n ~7/4/U ~ - == w 14 a.v. R Ir **"" *"' p ---O-O- . _ _ . , _ . o m.
& u =ae===<O O-D O C
% = %.e o.s cwO a=== -0
-5 Amen T.wm., nema.
(a . oismaurm O ."o.f BE L ; O o=== - .a=== .n.=. 0
EMERGENCY OR ZATION CALL LIST I 3 of 28 69-1029 7/06/83 (100) I Call Out Instructions: l i . ,. i 1. Contact one person for each position.
- 2. Contact first listed available person (preferred position holder); if unavailable, contact the next available person l
i 3. Persons with a
- are designated for on-call rotation. Describe event if requested.
1 4. Describe emergency classification and position person is called for. NOTE: Personnel to report to assigned location for Alert Classification or higher; optional for unusual event. 4 H/P FREQ. EMERG. NOT ON-CALL Wit.L BE IN HOME Pil0NE/ PAGER CALL # CONTACTED ORGANil. AVAIL 7 P05 2 PLANT PHONE GROUP CALL # YES NO TIME YES NO POSITION ABLE liOLDER NAME/NON-EMERGENCY TITLE.
~
Emergency 1. J. M. Giscion { Power Plant Engineer i Evaluation ' A & Recovery
$ Coordinator *2. L. F. Womack Sr. Power Production Eng l (Assigned
! to TSC)
*3. Y. R. Foster i
Sr. Power Production Eng. i
*4. E. G. Davis Sr. Power Production Eng.
l *S. R. M. Luckett - i Regulatory Compliance Ent . 1
~
1 I l . Insert date person is not available. NOT FOR PUBLIC DISCLOSURE DC0075 3 1. l 2. Insert date person assumes "on-call" responsibility. j (Person on call will possess the pager 'or this posit on) i
69-10297 07/06/83 (100) EMERGENCY ORGANIZATION CALL LIST Page 2 of 28 Call Out instructions:
- 1. Contact ene persen for each position. . i.
- 2. Contact first listed available person (preferred position holder); if unavailable, contact the next available person
- 3. Persons with a
- are designated for on-call rotation.
- 4. Describe einergency classification and position person is called for. Describe event if requested.
NOTE: Personnel to report to assigned location for Alert Classification or higher; optional for unusual event. EMERG. NOT ON-CALL H/P FREQ. ORGANIZ. AVAIL HOME PHONE / PAGER CALL # CONTACTED WILL BE IN 7 P05 2 POSITION ABLE HOLDER NAtiE/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL i YES NO TIME YES NO Emergency 1. P.. Patterson -- Opera tions Plant Superintendent Coordinator (Assigned to *2. J. A. Sexton Control Room) Supervisor of Operations
*3. 5. R. Fridley General Operating Forema
*4. W. G. Crockett Sr. Power Prod. Eng. -
(0pera t jons)
*5. R. L. Fisher '
Sr. Power Prod. Eng. DC00h 2 1. Insert date person is not available. NOT FOR PUBLIC DISCLOSURE
- 2. Insert date person assumes "on-call" responsibility.
(Person on all will possess the pager for thi- ition)
,lil(
l ,' l 1 lj
;i v
N I O 8 N 2 E B f o n L5 LE o I Y s r W e p a P e E l b . M a t I l n T i e a v
- v e f' a l
t a D x . u EO e d s TN n e u C t n A E e s u TS R h e NE U t u r OY S _ q o C O t e f y L c r C a l ## c S t f a n I n i n . LL e D o o QLL g r c t i EAA C n t p RCC : e I e F m L e v o RP E B l e PEU U b ; /GO l P a e r l AR a T l b e l PG r e R i i h O S a r g n F I v c i e L a s h G T n e O L u D r /E ] N L A f o EN N0 [ C i . n Oi l
)
r o HP n N ; o i P y o O ) f t T c i I r a EN . n t T e d c MA e .i d e i OL g ys l l f HP M r t o o l i e ip h a s t m l
. c s n E is G n a a bi R o s l E l a ih O i i C L t P e st t T n r n Y i .n t I e e A or C sno r T d h po N oos e n t e sf E pi r l Y y e t e G t e A C r t r o i rr R dap N rr n ne t S e E et r E ee ni oe r . g M
E ron rro f o G R bg na or se i n ci e . ft
] e "l l l p a
e i E rn rp sg es [ ba fl t n M oa eu i na as ace el i o E hM tS GE
- KA l - h ras pco i - T t t i nt t N t at . t . . r ao
( p a O .n Mn e v
. nod n c o
N
/ C. a l
P n
.l a .l a
Bh
.ce l A
a"sess no n l E RP RP JP WT t es osra i ro d M A . . . . .
] oms nuo t ef n e N l 2 3 4 5 [ sp i p o n * * *
- ss s di g ial oeet i t l pl t a s 2 n nni h ani bac s a
l l .E R e v oow ss cl gf A5D E rrl
'aiii o C0L eel eass t - PO l ppa ves N H a c rad a t r
O u ee ) o l s tt n 0 fd ec o u aao 0 er p .' n dd 1 : nt ay e LE U n ( i os c r TI L tt o n si* n OAB ] rrs o rl e o NVA eer 3 i e ag t A [ sse 8 t pt r . n nnP / c she l o I I( 6 u ert m e : i 0 r niie n y n t t of w n c o p . . h 1 9 I t s n u ttsb ccni aaor t t sc nnrs e P o s r e ZO
.N n
ert go rtd eae mnn o i t i f a c i D r c s e 12 1 2 O ooee GNT
. I I Ei g i 5 0 CCPD : di) s t /
1 l E RAI EGS ersC s n U
- l T t osS a e U 9 a . . . . O MRO i OAT l v C o C 1234 N EOP SC(( C E D Ill lll lllll!l l :
I 69-10297 07/06/83 (100) EMERGENCY ORGANIZATION CALL LIST Page 4 of 28 Call Out Instructions:
- 1. . Contact one person for each position. . i.
2.
- 3. Contact first Persons with listed a
- areavailable person designated (preferred for on-call position holder); if unavailable contact the next available person rotation. ,
4 Describe emergency classification and position person is called for. Describe event if requested. NOTE: Personnel to report to assigned location for Alert Classification or higher; optional for unusual event. l l EMERG. NOT ON-CALL H/P FREQ. ORGANIZ. AVAll y ABLE P05 2 HCME PHONE / PAGER CALL # CONTACTED WILL BE IN l POSITION 110LDER N.AME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL f YES NO TIME YES N0 i , Energency *l. J. V. Boots l Radiological Sup. of Chem & Rad Prot. l Advisor I (Assigned *2. W. A. O'Hara to TSC) Sr. Chem & Rad Prot. Eng ,
*3. H. W. C. Fong i.
Chem & Rad Prot. Eng.
- 4. ,
e l S. , fl
\!
n 6 DC0075 4 1. Insert date person is not available. NOT FOR PUBLIC DISCLOSURE
- 2. Insert date person assumes "on-call" responsibility. '
(Person on call will possess the pager for thic sition,'
-- al
- y. . ,a ._ _n _ - - . ~ . . - - . - - _ _ - . - - - - - - - - - - -
3 *
- 2" e-* O '
Z CD IJI . N CD
% JO
- C C J LAJ O ->=
W M b 3 GJ LaJ
- "E".
.O +J
*=*
so C H i a== GJ m >
> GJ E9 -
C l
+J #U wO I
- x
- m HZ E
LA.J ' GJ D m O l ' CC C CJ 3
*J C < :D W
O Att 3 H@ Z LJ s' C
.C CJ Q >= J
*J U L ,
U O U '
*J O'
GJ % m U L aem ame C m -
+J % m U C e C Cr J J -
O O LaJ J J f.J +J e= CE < <C CC J C +J La U t J C. ~3
- QJ
> 0 CL CC C. a QJ
- O %WO CC
.O == =cC O l
e CJ L <c W f
.O Q1 C. C ;
M ,- e .C H A m L w m O
- > U ;;". j J 'o m .C C QJ
*N Ld 3 O L m J O La.J ::"
-.J ZO C"
% O
< ---
- C O= v U L O Z Q. +J
** O e C. *e Z e % +J >.-
O m Lad Z hv
-= L I uC eJ C
- 4) V U -a H
V QJ -== 0J at: % i C. e--
*m O - - '
80 m .O - 4 m e .C U m *J C m LaJI L C O m -
.J O OL
=r- r= U b aO O d t==
- O
*J m%
+> so
>= **= *C >= m C cJ mCO L - L L U as w
Z O O so - >- > D O w av b U L L ** C5 C *J c) att Z W GJ CO O- A CE V *U a W C c. C * .x L.; D
'e= O - - CL I
L LaJ GJ +J L OC O C =r= 3 GB D V L -L -U .c m L % Cf +J M c- O CJ O C *o U GJ LaJ L LO LaJ L MO ~~ Cn - er O' e E e Cn OO HC t e C
% *J C La.: IC -- EU mU - ro O CJ - - O s *C 6 >s m e * * *
- L so e Z *C La Cn Cf -*= ats m CL U O +J LAJ CM w e a m O "'3 - -
#O C C e L6 Q1 U Z
- 6
- L *b +a Oe C N *b 7H OGe
- COT C LAJ H>- 7t- 3 t-- C3 c C O C - m C.
Om6m E Lt) me D N M C w kO Z - * +J 43 % C QJ e f 4 -
-*- a O C CC#
m Cp V- OO3 O O QJ +J - sn N , emL-a- *J *C m J CE' . L
.O mU- J
- LAJ O GJ -
4 m 6:: su C. CL m U- Cnww aC m o U oo w e O UOJ
+J e n. O GJ 03
@ m m in 2' i ,
*J *J C
> 01 sn se O so e O L m 'n m vV
^ O - L C O % 'O 4J U O w *J *J C a) L CL L L e
} O qJ J Le2
- ** CM eo % L >===J QJ QJ L w m Om U O <C tc e sn CJ C in - e C Z><, t t
C C C. O L- CJ O et *-*====
=r= eo tn +J M GJ L
CD +J CL +J U to E Q e- * *
- N U
@ "3 SJ L +J E. -N k C ** ~r= GJ C O C
% +J O% % O 6 m GJ m LC)
C +J +J nn .D k O
*== t2 U C w= h +J %
00 no O L CJ
- 2"' U oo G Lt1
( sa 3 sJ ed mU C C L m G. NO C C Cr*C^ CJ O CD U r=. C N O OO GJ CJ ** CZH Ch m 't - m C U y D. O Cr aC - L- L to >== v O LJ La.8 C M CJ 80 O m O e *-= t-= O x Cr O E - O at O eo e * *
- LaJ O h. LaJ J 4 J - * +J cn -N Me Z U
i go
--- ~ _-_____
. - . - ..~. - . . ~ . , . _ - - - - . - _. _ .- - ~ ~. - .. . - .
~----~. _ % _ . . _ . .
I i
<l i
1 Z
-O <
CC Z i N W g CD 5 O C JD
- _J W O
D sn * > ~ L 3 GJ GJ Q C.
*0 C. QJ
- W 4 . E eu +J -
- C >=
- GJ m >
L> G3 m M m O M = 3 WO GJ % B WZ C CJ 3
+J C - .O
- W C3
G) m 3 &D
.C CJ ZW D
+J 3 L O >= M C* Q O 4J CJ tO. J U L \ U
'O - == W M % -
to C -e - C .JJ C C O C7 J _.J U +J v w<< U C +J C2: UU
- CJ C. La. -_J CJ > 0 C2: A CD
- Q Q. W D D 4 .= NOO Q.
<c CJ L = *:C E
- C CJ Q. O C:
& *
- 2 O W m L Cn t.a.
*-a > U e J m m .C C CJ O J '3 O L %W Z J O LJ Z
< % ZO O= ^
y e . C L Q = CL C Z .* O e Q. O m % +J & r= O.
.- L sg 1.LJ Z W CJ D U T<
- C D G) e C h N - - % I Q..J +J L
- C - ~ '~ ~ - C' Z r #c m C % -
< U m 80 C ^
W
^
W
-t i O C sg E +J .O **-
, c: O m - W m % % -r O w e Q J +J %.* *C to m +J
+J & C e +J +J C
>= e .C +J = eg 01 LA M OL U mC O L H - C w w a C-Z M CJ Q. W mW w O .O 6 C. - >- . . c)
O +J CJ < U O .C
+J V
- C4 C
Cl C 6 L CJ C: V e C. Z +J w QJ +J L W L L O La.J L&J th .= Qi E L O C O O CJ e OL GJ h s GJ - oo w L L Q % C3: W +J 3 Q. .nc * - * - - C. CJ - w CJ M > mD - D .O 90
%- +J C E #O m CJ
- L Q CJ O so U c)
CJ - O w M< M 3 CD L M L - e 4 L va m .- e O Q. C. e C +J C. U C 43 Z * *
- Q. *
- cO w a CL ve O CD 4 *"'3 LaJ
- 7 * >= en C U Z J
- 3 3 #O in
*C OV O N e q) *L *O
- O in CD i C C C - t.LJ 3H 3m H CL 3 Q. +J q) in OM L e E O E in w L O y < e o e w
- e C3 O
+2 GJ % C c) Z - N t*) Ln sn CL
- C. O C * *
- in en m T- C) =s=. #O -
O CJ CJ +J e - Cl- +J m in N C C-omU vs J Cx: O O y 2mCw r0 .J ew en sn U- CM W e:C M O L L-90*= e
- O QOJ GJ GJ -
QJ dO en m +J s C. O Q. Q. #c
> CJ m Z Z U L e t 80 +J Q QJ 43
^ O - L +J +J C O %V cs u O #c so o O CJ L C1 W tV
=== .* C +J so X c; .J L&J C w sn C sn U L W m== J +J +J L L *n O
C in - e C O aC CD i O L- c) Z>< al c) L. ; rn - a) on Cn .OJ < sn M al C C C. 1 CO +J G.ee L
-*-w i
N U en r c) - i D 3 GJ L +J G CJ l O L c v .~ GJ C CJ
= =
% +J 0% 3 C 4
- N en cJ Q *J Os C -' N O C +J +J sn L= O U U sn C.
,o. O 'y -
6 en re O L c) *J E . +J V @ N - .3 a g ., o Z w m QJ Ch 3 -C-C L en NO L O h* N C^ 8 (V Q O O CJ CJ O "Z" H" s C C' '
- O' N'O O v v c. O ..
- - us Cx; a:: - -*^ 'C *o to w O s p sa 4 3 m > 3 m en C
____m _ _ . . ___.._--m ___ T c L gr" n n.A
EMERGENCY OR ZATION CALL LIST 7 of 28 69-102sh7/06/83 (100) Call Out Instructions: i 4
- 1. Contact one person for each position. I
! 2. Contact first listed available person (preferred position holder); if unavailable, contact the next available person i 3. Persons with a
- are designated for on-call rotation, i
, 4. Describe emergency classification and position person is called for. Describe event if requested. i
! NOTE: Personnel to report to assigned location for Alert Classification or higher; optional for unusual event. i i i i l EMERG. NOT ON-CALL ll/P FREQ. ! l ORGANIZ. AVAIL P05 2 HOME Pil0NE/ PAGER CALL # CONTACTED WILL BE IN i 7 l POSITION ABLE HOLDER NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # YES NO TIME YES NO l l - l
- Emergency (No On- 1. J. A. Sexton {
Operations Call Sup. of Operations j j Advisor Person i (Assigned - for 2. 5. R. Fridley to TSC) this General Operating Forem posi t!cr.)
- 3. T. J. Martin Training Supervisor
- 4. W. G.'0rockett j Sr. Power Prod. Eng. _ j j (Operations)
~
l 5. 1 - 3 i i i I i li DC0075 7 1. Insert date person is not available. NOT FOR PUBLIC DISCLOSURE - f'
- }}