ML20125A653
| ML20125A653 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 02/04/1985 |
| From: | Shiffer J PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20125A621 | List: |
| References | |
| PROC-850204-01, NUDOCS 8506110145 | |
| Download: ML20125A653 (56) | |
Text
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. ",' PGandE Lettsr No.: DCL-85-051 y
N V CURRENT EMERGENCY PLAN IMPLEMENTING PROCEDURES
~
, TABLE OF CONTENTS Volume 3A l
3RE . EV OP-0 Reactor Trip Or Safety Injection 0 i 0P-0.1 Reactor Trip Response * - 1 OP-0.2 Natural Circulation Cooldown 0 OP-1 Loss of Reactor or Secondary Coolant 0 ,x OP-1.1 SI Termination 0
;_ OP-1.2 Post LOCA Cooldown and.Depressurization 0 OP-1.3 Transfer to Cold Leg Recirculation 0
, OP-1.4 Transfer to Hot Leg Recirculatio,n 0
;' OP-2 Faulted Steam Generator Isolation 0 OP-2.1 Alternate Auxiliary Feedwater Supplies O' OP-3 Steam Generator Tube Rupture 0 0P-3.1 SGTR With Loss of Reactor Coolant 0 0P-4 Loss of All AC Power 0 0P-4.1 Loss of All AC Power Recovery Without SI Required 0 OP-4.2 Loss of All AC Recovery With SI Required 0 OP-4.3 Restore Vital Bus .
0 0P-5 Anticipated Transient Without Scram (ATWS) 0 OP-6 Response to Voids In Reactor Yessel 0
",' , OP-7 Response to Inadequate Core Cooling 0 OP-8 Response to Loss of Secondary Heat Sink . O
- w. R-1 Personnel Injury (Radiologically Related) 14
,' and/or Overexposure R-P. Release of Airborne Radioactive Materials 5 R-3 Release of Radioactive Liquids 4 R-4 High Radiation (In Plant) 3 '
R-5 Radioactive Liquid spill 3 R-6 Radiological Fire 8
, R-7 Offsite Transportation Accidents 5 M-1 Emp1gyee Injury of Illness (Nonradiological) 12 l M-2 Nonemployee Injury or Illness (Third Party) 10 l M-3 Chlorine Release 5 M-4 Earthquake 7
, M-5 Tsunami Warning 5 j. J' . B506110145 850204 PDR nDOCK 05000275 F PDR 02/04/85 ' t
TITLE REV M-6 Nonradiological Fire 10 M-7 011 Spill Isolation and Clean Up Procedure - 6 M-8 Containment Emergency Personnel Hatch 0 !
. M-9 Hazardous Waste Management contingency Plan 1 ;
.M-10 Fire Protection of Safe Shutdown Equipment 2 i G-1 Accident Classification and Emergency Plan Activation 5 G-2 Establishment of the On-Site Emergency Organization 6 G-2 51 Emergency Organization Call List Fom 69-10297 1 G-3 Notification of Off-Site organizations 5 G-4 Personnel Accountability and Assembly 5 G-5 Evacuation of Nonessential Site Personnel 2
- . e G
e e O e 02/04/85 l l l l
NUMBER EP OP-0.1 GF4E Pacific Gas and Electric Company REVISION 1
, DEPARTMENT OF NUCLEAR PLANT OPERATIONS !!
( OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 13 EMERGENCY PROCEDURE g TITLE: REACTOR TRIP RESPONSE APPROVED. Y A H' T
', . ' PU6T' AANAGER,.) DATE ggm SCOPE ,- This procedure provides the necessary instructions to stabilize and control the plant following'a reactor trip without a safety injection.
This procedure and changes thereto requires PSRC review. SYMPTOM OR ENTRY CONI)ITIONS .
- ~~
This procedure is entered from EP OP-0, REACTOR TRIP OR SAFETY INJECTION, Step 4, when SI is neither actuated nor required. k .
'\
( 1 l l DC0259 IVI
R EP OP-0.1 - 1 AND 2 ON D4ASLO CANYON POWER PUWT UNIT NO(S) DATE 12/7/84 PAGE 2 0F 13 , y Tirts: ' REACTOR TRIP RESPONSE .f' I
- RESPONSE NOT STAINED ACTION /Detutu RESPONSE LAUll(A: o 17 M actuation occurs during this procedure, go to EP OP-0, REACTOR TRIP OR SAFETY INJECTION.
o If subcooling monitor becomes inoperable, detennine
~ ' 'subcooling by using WR RCS pressure and core exit TCs(RefertoAPPENDIXC).
~
g: Monitor the SPDS display.
~
E temperature is greater
- - -- 1.; CHECK RCS Average Tem >erature than 547'F and increasing
- STABLE AT OR TRENDI E TO 547'F THEN dump steam to condenser OR dump sEeam using SG 10%
steam dumps. j IF temperature is less than i 547'F and decreasing, THEN verify ALL steam dumps closed.
- IF cooldown continues, TREN check for excessive feedwater by reducing flow.
Feedwater flow can be reduced below 460 if level is GREATER THAN 4% in at leastone(1)SG IF cooldown continues. TREN simultaneously close MSIVs - AND check bypass valves closed. I DC0259 2VI e
-- - ----,,e ---~-e ,, -g-, , -
1 EP OP-0.1 DWEO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 h
, DATE 12/7/84
- PAGE 3 0F 13
- f. - Tm.E: REACTOR TRIP RESPC'SE ACTION / EXPECTED ESPONSE ESPONSE NOT (ETAIED
; 2. CHECK FW Status:
- a. Check RCS average temperature a. WHEN less than 554*F,
. LESS THAN 554*F THEN do Steps 2b and 2c.
Continue with Step 3 a
- b. Verify MFW regulator valves b. Manually close SG MN FDER closed on monitor light box C, CONT valves:
SG 1evel portion: FCV 510 - CLOSED
.~- 1) Red activated light - ON FCV 520 - CLOSED FCV 530 - CLOSED
- 2) White status lights - 0FF FCV 540 - CLOSED
- c. Total AFW flow c. Start available AFW Pump and l - GREATER THAN 460 GPM align LCVs to control level.
- OR -
Controlled with SG NR level at ~ IF AFW NOT available. 33% THEN reset Feedwater i . Isolation and go to EP OP-8, LOSS OF SECONDARY HEAT SINK.
- 3. VERIFY All Control Rods Fully -
IF two or more control rods Inserted. NOT fully inserted, THEN emergency borate 100 ppm for each rod not fully inserted. e -e e e DC0259 3VI
) ~ ~ 1 AND 2' ON OiAsLO CANYON POWER PLANT UNIT NO(S) DATE 12/7/84 PAGE 4 0F 13 -
- . 1 Tms: REACTOR TRIP RESPONSE M
RE5PON$E NOT (BTAlED
/ ACTION /EXPtuw RE$PON5E
- 4. _ CHECK PZR Level Controls:
1
- a. _Ij_ level less than 17%,
- a. Level - GREATER THAN 17%
. THEN perfonn the following: . o Ensure letdown isolation o Ensure heaters off o Control charging to restore PZR level to
, greater than 175. 4 Verify charging and letdown b. To re-establish letdown: b.
- IN SERVICE 1) Ensure charging in service
- 2) Ensure Itdn orifice stop viv 8149A, 8 and C closed 3)OpenLCV-459andLCV-460.
! 4) Check open 8152. Letdown ISO VLV 0.C.
l 5) Manually open Letdown l Press Cont. PCV-135 to
+ 50%.
~ 6)Openone(1)75gpm orifice stop valve, 8149
- B or C.
l 7)AdjustPCV-135for350 [ psig and then place in AUTO.
- c. Adjust charging flow to
- c. Level - TRENDING TO 22% ' maintain level S.22%.
- )
DC0259 4VI
" *l D$b CANYON POWER b UNIT NCMS) 1 AND 2 ON DATE 12/7/84 5 0F 13 PAGE l,.
(. T m.E: ' REACTOR TRIP RESPONSE ACTIm/DGETE IESPmSE lE$PmsE f0T @TAffe CHECK PZR Pressure Control: 5.
$ ".a Pressure - GREATER THAN 1850 PSIG a. J,F,F less than 1850 psig, THEN manually actuate SI and go to EP OP-0. REACTOR TRIP OR SAFETY
. INJECTION. Step 5.
i' b. Pressure - STABLE AT OR TRENDING b. - IF less than 2235 psig and _ TO 2235 PSIG . . decreasing. THEN perform the following: o Ensure PZR PORVs closed. IF PORY can NOT be closed. THEN manually close its ( block valve. o Ensure PZR spray valves closed. IF sprayvalve(s)can NOT be closed. THENstopRCP(s) l supplying failed
- valve (s).
. 1
- RCP 1-1 fot PCV 455A
- RCP 1-2 for PCV 455B o Ensure PZR heaters on.
E greater than 2235 psig and increasing, THEN perfom the following:
# - -- o Ensure PZR heaters off.
o Control pressure using nomal spray, ( auxiliary spray or PORV. DC0259 SVI ' e
NUMBER EP OP-0.1 . . 1 AND 2 ' " REVISION 1 DWN.O CANYON POWER PUWT UNIT NO(S) DATE 12/7/84 PAGE 6 0F 13 . j ,' Tmm ' REACTOR TRIP RESPONSE > . itaGGE NOT GTAINED . ACTION /ENtutu E$PON5E
- 6. CHECK ALL SG NR Levels:
- a. Maintain total feed flow
- a. SG NR level - GREATER THAN 4% greater than 460 gpm until
- SG NR level as greater than I
~
4% in at le 4st one (1) SG.
- b. Control feed flow to maintain SG NR level at 33%.
?*
- c. Shutdown steam. driven AFW pump if
- - not needed.
7.* VERIFY Main Generator Trip After 30 5econd Delay:
- a. PK 14-1 Unit Trip - ON
- b. Open Generator PCBs.
- b. Generator Vol'tage - S 0 volts. l i
f
't I
l DC0259 6VI
- eWg 6g .p e %"- .&3%d *
$ 499 m ,m
~
CMYON POWER PUWT UMT NO(S) 1 AND 2 EP OP-0.1 g DATE 12/7/84
. PAGE 7 0F 13
(. Tm.g REACTOR TRIP RESPONSE ACTION /EXPECTEDPE8PON$E RE$PON$E NOT WTAIPED .
.- g: If the plant was backfeeding from the 500 KV system at the time of the reactor trip (i.e., prior to rolling off the turbine), an automatic transfer to startup power will not normally occur unless the 500 KV system becomes unavailable.
l 8. VERIFY All AC Busses ~ IF offsite power NOT . ( * - ENERGILED BY Off5ITE POWER - available. t THEN verify diesel generators have assumed the following loads: l - ASW pumps 1-1 and 1-2 AFW pumps 1-2 and 1-3 Charg. pumps 1-1 and 1-2 l CCW pumps 1-1,1-281-3 CFCUs 1-1,1-2,1-3,1-4& '
. 1-5 Attempt to restore'offsite power and, if possible, energize additional equipment from the vital busses (i.e., PZR heaters,
. TSC).
TSC OPEN 52-22J-40 OPEN 52-2F-47 OPEN 52-1F-67 SWITCH EPTSN TO VITAL POWER SWTICH EPTSC TO U-1 (52-1F-67) CLOSE 52-1F-67 e o e m 4 ( . DC0259 7VI l_ .
NUMBER EP OP-0.1 1 AND 2 REVISION 1 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 12/7/84 PAGE 8 0F 13 ,
)
TmE: . REACTOR TRIP RESPONSE RESPONSE NOT @ TAINED ACTION /EXitutu RESPONSE LAUllVN: On natural circulation, loop Tavg and associated interlocks will be inaccurate. Use WR temperature for control of plant. j((Q[: Running RCP No. 2 (preferred) or RCP No.1 should be given priority for purpose of nonnal PZR spray. Start an RCP per OP A-6:I, RCP
; 9. VERIFY RCP Status - Place in Service
- AT LEAST ONE RUNNING ,
RCP can NOT be started,
- ~-
IJ[ THEN operate steam dump to ensure: 1)RCSsubcoolingGREATER THAN 20*F I 2') SG pressures STABLE OR DECREASING
- 3) RCS hot leg temperatures STABLE OR DECREASING.
- 4) Core exit TCs STABLE OR DECREASING 5)RCScoldleg temperatures AT SATURATION TEMPERATURE FOR SG PRESSURE.
- 10. CHECK Main Turbine Status During Coastdown:
- a. Verify turbine drain valves . ..
- OPEN. .
- b. Implement Part B of OP C-3:III, ,
Main Turbine Shutdown. DC0259 8VI
~ ~
NUMBER EP OP-0.1 DMLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 1
' DATE 12/7/84
;
- PAGE 9 0F 13 l
. (.- Tms. REACTOR TRIP RESPONSE ACTIW/DGECTED IEsPWSE REsPW$E E STAlle ~
- 11. ALIGN MSRs:
'.aPress reset on MSR control panel.
- b. Refer to OP C-5, MSRs for desired
. alignment instructions.
- 12. CHECK If SR Detectors Should Be -
Energized:
- a. Check IR flux - LESS THAN 10-10 a. Continue with Step 13.
AMPS ~
' WHEN flux is le'ss than 10-10
" - ' amps.
THEN complete Steps 12b.c d. and e. ( b. Verify both SR detectors
. ENERGIZED
- b. Manually reset and energize both SR detectors
- c. Select highest SR and IR detector on NR-45.
I d. Unblock high flux at S/D alarm l when level is below setpoint and t stable.
- e. If desired, place SR audio
- countrate circuit in operation.
,13. SHUTDOWN MFW Pumps If Not Needed For Feedwater Control:
, s. Implement OP C-8:III, SHUTDOWN l AND CLEARING OF A MAIN FEEDWATER . PUMP. .. l
- b. Open MFW turbine drain valves. -
l [ DC0259 9VI
D4ASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 [fh0H DATE 12/7/84
- PAGE 10 0F 13
)
Tnts: REACTOR TRIP RESPONSE RESPONSE NOT 0BTAINED ACTION /Detuw RESPONSE
- 14. CHECK If Condenser Steam Dump IF
~~'
the condenser is NOT , Should Be In Pressure Control Mode: available. THEN use SG 10% steam dumps to
- a. Check MSIVs - NOT ISOLATED maintain T-no load.
i b. Check C-9 status light - ON
- c. Check Tave at T-no load IF demand on HC-507, remain
, d. Check HC-507 set at 8.38 turns .
~-
in Tave at T-no load, and
- e. Check for 0% demand on HC-507 recheck Tave at T-no load.
- f. Transfer to PRESSURE MODE
~
- 15. SHUTDOWN Unnecessary Plant .
Equipment As Desired:
- a. Stop No. 2 Heater Drip Pump per OP C-78:II No. 2 HEATER DRIP PUMP SHUTDOWN AND CLEARING
- b. Shutdown all but one Condensate and Booster Pump sets. ,
- c. Reset 4KV bus auto transfer relay, if necessary.
- d. Stop all but one (1) ASW pumps.
- e. Restore CFCU operation to pre-reactor trip status.
- 16. ALIGN Auxiliary Steam As Desired:
- a. IMPLEMENT OP K-5. PACKAGE BOILER AND AUXILIARY STEAM SYSTEM
- 17. NOTIFY Rad / Chem Department Of Reactor Trip.
O e g
. DC0259 10VI I
- NUMBER EP OP-0.1 oveLO CANYON POWER PLANT UNIT NCMS) 1 AND 2 REVISION 1 DATE 12/7/84 PAGE 11 0F 13 I. Tms: REACTOR TRIP RESPONSE ACTION /EXPECTEDRE$PONsE RE$PONIENOT@TAINED 18., MAINTAIN Stable Plant Conditions:
) o PZR pressure - AT 2235 PSIG o PZR level - AT 22% o SG NR level - AT 33% o RCS average temperature
- AT 547'F
- 19. COMPLETE Required Reports And -
_ _ . Notifications:
- a. AP-10051. REACTOR TRIP REPORT
- b. Refer to Appendix Z of this procedure.
4 ( c. STP M-55. Recording of Cyclic Fatique Transients.
- 20. GO To Applicable Plant Procedure:
- a. EP OP-0.2, NATURAL CIRCULATION C00LDOWN
- OR -
l b. OP L-2. HOT STANDBY TO MINIMUM
. LOAD
- OR -
- c. OP L-5. PLANT C00LDOWN FROM MINIMult LOAD TO COLD SHUTDOWN
- END -
g l' .. .. e C. . DC0259 11VI l L
l NUMBER EP OP'-0.1 1 AND 2 REVISION 1 own.O CANYON POWER PL. ANT UNIT NO(S) DATE 12/7/84 ' PAGE 12 0F 13
- . y
. mm: REACTOR TRIP RESPONSE
~
, APPENDIX C 1
~
li 2600 - .
, 2400 - -
,' UM ' _
s _ 1800 a - . C
~
1600 g SATURATION -liEE I CURVE -
. SATURATION N ==
U 1400 - - CORRECTED FOR E __. INSTRLMENT ERROR w -_ , f E 1200 _ . t . __- ~ E =-:: ...
~
z 2000 -- . - ;; 1 m = . M =_ _-. = _ _ 1 8% ?'_~
=
=_ . --
600.~~. : :
= : :
. 400 __ :
l
)
E __ ~' 200 _ _ _- t= - 400 500 600 700 200 300
)
CORE EXIT T/C TDFERATURE ('F) DC0259 12V
Duet.O CANYON POWER N. ANT UNIT NO(S) 1 AND 2 h0N DATE 12/7/84 PAGE 13 0F 13 Tms: ' REACTOR TRIP RESPONSE i APPENDIX Z t :
.' EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 3. 1. When the emergency procedure has been activated and upon
'. direction from the Shift Foreman proceed as follows:
l
- a. Notify the Plant Superintendent, Operations Manager, and
': Plant Manager of their designated alternates.
- b. Within four hours notify the NRC Operations Center using the red phone in the Control Room. Gather sufficient information from all sources prior to calling so that the phone call is~ meaningful. ' Complete the "NRC Event .
l
- _ _. Notification Form" contained in Administrative Procedure C-11. Supplement 2. " Supplement 2 to Non-Routine Notification and Reporting to the NRC and Other Governmental Agencies." Notify the NRC that your call is a four hour l? report pursuant to 10CFR Part 50.72, (Ismiediate Notification
,. Requirements).
- c. Review the circumstances causing the reactor trip against
' the criteria for reports to the NRC contained in
". Administrative Procedure C-11. Supplement 2. If circumstances warrant, designate the event in accordance <
with the e,riteria contained in Procedure C-11, Supplement 2. ! l I d. When the cause of the reactor trip has been determined, this ,
- and the subsequent plant conditions should also be reviewed !
against the classification criteria in Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation."
- 2. If plant conditions indicate the required conditions for reactor trip have occurred or the required coincidence of bistables have tripped, or trip is manually activated, and nuclear -
instrumentation indicates the reactor is not subcritical (e.g., non-negative startup rate) designated this event an Alert. Notify plant staff and response organizations required for this classification by implementing Procedures EP G-2 " Establishment of the On-Site Organization" and EP G-3 " Notification of Off-Site Organizations" in accordance with EP G-1 "' Accident Classification and Emergency Plan Activation.'"' ' 4 DC0259 13VI
69-9018 3/84 (200) Page 1 of 1 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 TITLE: NEW/ REVISED / RESCINDED OFFICIAL PROCEDURE INSTRUCTION 5HEET - TD: For Plant Manual Copy, No: Date: l- fl-f 6 Responsible Person gy , NEW PROCEDURE Proc No. Rev No. Vol No. .Section Proc No. Rev No. Vol No. Section q,,
. 1. Remove the history sheet (for departmental use as determined by each dept head).
- 2. Insert the attached new procedure into the designated volume.
- 3. Enter the procedure title and revision on the Table of Contents.
- 4. Sign and return this instruction sheet as soon as you have completed above. -
~
REVISED PROCEDURE Proc No. Rev No. Vol No. Section P me No. Rev No. Vol No. Section g7 rn-l J Z,. 34 M. - % sAlIAf.ldt 'ftUi C&ach erwAf $4M. IndLtk ~Of \ 7 ne p-I. 1+ issa hv \
) .hs(Desf e v . ~
l L -. _ 5 .
- 1. Remove the history sheet (for departmental use as detemined by each dept head).
. 2. Insert the attached revised procedure into the designatet volume. ,
- 3. Remove and return the out-ef-date procedure and ary on-t's-spot procedure changes associated with the procedure. ~
- 4. Update the revision entry on the Table of Contents. ~
- 5. Sign and return this instruction sheet as soon as you have completed above. -
~
RESCINDED PROCEDURE -
~
~
Proc No. Rev No. Vol No. Section Proc No. Rev No. Voi Mo. Section ! 1. Remove and return the cancelled procedure and any on-the-spot procedure changes associated with the procedure.
- 2. Line out the procedure entry on the Table of Contents.
- 3. Sign and return this instruction sheet once you completed the above.
l ' l REMARKS: INSTRUCTIONS COMPLIED WITH: Date: ) Responsible Person - RETURN SIGNED INSTRUCTION SHEET TO: DE*ARTMENT OF NUCLEAR PLANf OPERATIONS . DIABLO CANYON POWER PLANT - ATTENTION: M 03&.- V (Document Control Clerk)
WuM N3 3A 31IEVDtSE SIDE FOR INETitJCT1086 [0m REspoustett 301 $, REspouststE sex y n,gpta RE5 m sttLE PERSON tox N0 [gg, no RE5PouststE PERSON sex N0 #0 PERSON NO #0 PERSON no n 41 estNorse N/A 81 IUteyworth F4 121 f[,'b E8 BCThornberry A3 1 N/A 42 Gerutich N/A 82 MN, N/A 122 1 2 BGiffin E3 83 P01sen E11 123 JD5hiffer II/A 43 TJNortin 3 84 124 DCremins L11 - 4 lutC M9 44 Shift Sec Suorv K9 $$1e Shen 85 M40'Nere S4 125 DNelone A15 Library N/A 45 ACMoss li/A 5 M5 06 126 Clear Coord U2 D15 44 VRFoster 5 87 DMelone A14 127 Oper Ready lha 08 47 medallace N7 7 SFM DB 98 SS JNubble K11 128 Shift Mene9er DB 8 Control b DB 48 WEvidelin 49 Welannin9e C4 39 E5ecierelli N/A 9 Ann 81d9 Cat Br1 DS
- 90 120reke K11 50 Seedy Op Rm DB 10 Steulator Trne G4 11 IIst Shutdown Pn1 DS El Cold Shute. Pn1 08 91 @ $ "l **'"# N/A Cand Pol Sys DB 52 SvJohnson 15 32 Clearance Coord DB 12-93 1E Tmg 813
- -13 53 Press Celth Shot A14 A14 N3 54 P250 Caep Ibn le 94 NRe9011 14 JIGisclon '
1/ 95 DNorton A14 15 R55gder 58 55 MbFec/ 11 3 alhFerguson 36 56 Otsrpigt le 95 JH111 If N/A 17 57 $#I'"I N/A 97 leWnde 58 PPKristensen 111 98 11 Counting Room til ( WECrockett DO 99
~~
19 14C Foremen A14 59 100 LFisher K12 A14 40 JA5eaton 83 20 Electronics Lab 101 IE.iew D11 41 05R4 N10 21 Calib Shop A14 102 DGreen E6 62 Jvloots 33 22 103 RLFisher 010 A)4 63 istFitjiaota N/A 23 OWGiffin A14 64 IEUones 114 104 (Djst g i 24 Stet Temer ' C10 106 EOF N/A
- 65 letRyan 25 26 leechanical Fem C11 66 Tsc# f M, II/A 106 EOF II/A 1 1
107 tencLene 19 67 T5C R/A 27 Electrical Fru C9 Intenrohen A14 28 Cold elech Shop C11 48 D,",f'*8(,,, h*p/ 108 29 last slech Shot C11 69 },7,,, 7 'l 109 l3i Cambustion Enge B12 110 SUPierce D12 30 RETedere ES 70 111 San Sesser . P!ff! N12 31 Avile Guard K9 71 35 32 Cent Alere 5tn G 72 112 NFane II/A 113 URit 2 $$BCh/EleC C11 M tee Alare Etn t9 73 Finalinski N/A 114 LFidemmek M4 14 Guality Centrol L11 74 EOF N/A ill tatanton W7 Mll 76 EOF l f 15 GA QA Lttrary EfA 116 Sede Ms A14 M TG0euriste MIA 75 EOF AccessContCoord E13 A14 77 LEtunsford E10 117 B190ecten 17 ce -d J12 78 Phr 38 113 r_m A14 M teaterinit Fac 114 W/A 119 C. Swer N/A 19 tifidridae 19 79 T5C Vol 1 & 4 C11 es 1sn 1r,nuvete N/A
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Page 1 of 2 (- 7/84 RW9 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT'N05. 1 AND 2 1 , Safety. Health and Clakms Personnel to be 3 Contacted for Reporting of Injuries at Diablo Canyon i
. . 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 ocqur while on the job, report should be made as follows: During Working Hours: T. 8. Honey PGandE local ' - ~ ~ (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: Report to one of the persons on the following list, trying each in order until one is contacted: p
- 1. T. 8 Honey -
Pinole l
- 2. A. Thomas San Francisco
. 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. Glimme Danville
- 10. J. C. Vocke Lafayette
- 11. W. A. Hutchison San Carlos
- 12. C. C. Cooper Oakland
- 13. R. J. Zappelli Oakland
- 14. R. W. Hall Richmond
- 15. I. M. Crawford Hercules
- 16. R. G. Schumaker El Granada
- 17. D. E. Harelson Orinda '
t 18. P. C. Boettcher Moraga ! Ig. H. W. Reynolds Sunnyvale -
- 20. B. P. Sadler Belmont .
- 21. R. M. Petersen Walnut Creek g l
IThis listing extracted from Safety. Health, and Claims memo regarding Personnel to te Contacted'for Reporting of Accidents, dated 5/84. { . \- . : DC0084 17XI
. Safety. Health and Claims Personnel to be ,
)
Contacted for Reporting of Injuries at Diablo Canyon l i Page 2 of 2 - Non-Employee injuries / C. O. Schreil, San Luis Obispo, ' , If he cannot be reached, contact one of the following in order of
- - preference: , ,
During working hours:
's -
1- 1. John C. Echols
- 2. Doug G. Keeler
- 3. ScottP. Robinson (collectiononly)
, 3 After working hours on Monday through 8:00 a.m. un Friday, except holidays:
- 1. John C. Echols .
Pleasant Hill F
- 2. Doug G. Keeler Concord
- 3. John C. Vocke Layfayette
- 4. Donald A. Rushton San Mateo
- 5. William H. Singaman - Novato
- 6. E. Anthony Giudici San Carlos
- 7. J. Alec McCorquodale Lafayette
- 8. Stanley W.-Johnson Fairfield
- g. Scott P. Robinson San Jose
' (collectiononly) ~
- 10. . Bruce P. Sadler Belmont After 5:00 p.m. on Fridays to 8:00 a.m. on Mondays and holidays:
Contact the Investigator del.egated 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." 6 e
'l e
e
, 3 1 -
l DC0084 18XI l l
l I69901'8- '3/84 (200) Page 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIA8LO CANYON POWER PLANT UNIT NOS.1 AND 2 l TITLE: NEW/ REVISED / RESCINDED OFFICIAL PROCEDURE INSTRUCTION $HEET
)
TO: For Plant Manual Copy No: Date: 1-10 f5 l Responsible Person ,g NEW PROCEDURE Proc No'. Rev No. Vol No. Section Proc No. Rev No. Vol No. Section
,. 1. Remove the history sheet (for departmental use as determined by each dept head).
- 2. Insert the attached new procedure into the designated volume. -
- 3. Enter the procedure title and revision on the Table of' Contents.
- 4. Sign and return this instruction sheet as soon as you have completed above.
REVISED PROCEDURE , Proc No. Rev No. Vol No. Section Proc No. P.ev Mn. Vol No. Section l 69 in-s . K M 6 , i MC N orm d>>> a k duA 6
$ Reok:J e*4v Ao -14eiru. S 4 m. AccrAo 4
)
! 4 daul hsi Mchg2)(g3j3 . I .t L
% _- = _ - _ =W .
i 1. Remove the history' sheet (for departmental use as determined by each dept head).
- 2. Insert the attached revised procedure into the designatet volume.
- 3. Remove and return the out-ef-date procedure and avty on-t'.-spot procedure changes associated with the procedure.
i
- 4. Update the revision entry on the Table of Contents. .
i 5. Sign and return this instruction sheet as soon as you have completed above. - 1 RESCINDED PROCEDURE Proc No. Rev No. Vol No. -Section Proc No. Rev No. Voi No. Section l 1. Remove and return the cancelled procedure and avty on-the-spot procedure changes '
- associated with the procedure.
! 2. Line out the procedure entry on the. Table of Contents.
- 3. Sign and return this instruction sheet once you completed the above.
REMARKS: i INSTRUCTIONS COMPLIED WITH: Date: Responsible Person - RETURN SIGNED INSTRUCTION SHEET TO: DE*ARTMENT OF NUCLEAR PLANT OPERATIONS . DIABLO CANYON POWER PLANT i ATTENTION: d @ en U h - ffk.ul V (Document Control Clerk) U 4
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~~
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.40
l l
. NUMBER EP G-3 3D@:rWE Pacific Gas and Electric Company REVISION 5
!' DEPARTMENT OF NUCLEAR PLANT OPERATIONS OAII 12/19/04 CHAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE I , 1 0F 5 EMERGENCY PROCEDURE TITLE NOTIFICATION OF 0FFSITE ORGANIZATIONS i . IMPORTANT
,,,novgo. T. 6 YMr i ido-% TO PLANT MANAGEll# DATE SAFETY
, SCOPE ,
This procedure describes the steps to be taken to provide both the initial and follow-up notifications to Federal. State. Local, and Company off-site emergency organizations following the initiation of one of the four classes of Emergency Action Levels as described in EP G-1 " Accident Classification and Emergency Plan Activation." Notification of off-site organizations which would respond on-site to ( specific emergency situations. (security threat, personal injury or
- fire) are discussed in the individual procedures dealing with those
! specific types of emergencies. If required, requests for this assistance receive priority over notification calls. This procedure and changes thereto requires PSRC review.
GENERAL i
- 1. Notification of San Luis Obispo County should be made within 15 l minutes for the Unusual Event classification and sooner (consistent with the need for other emergency actions) for other classes. This time 15 measured from the time at which the Shift
. Foreman recognizes that events have occurred which make declaration of an emergency appropriate.
- 2. Offsite emergency organizations which require prompt notification in an emergency situation are listed on Fom 69-10298 " Required Offsite Organization Call List. The atencies are listed in the order in which the notifications shoult be perforined. The initial contact with an off-site _ agency should provide as much infomation concerning the state of the emergency as is available at the time the notification is made. Forn 69-10581 " Initial' Emergency Notification Form" is provided as a guide to be used in -
, . providing the initial notification of an emergency. All j available information on Fn m 69-10581 should be provTied.the __ organizations._ ,,, , _ , DC0042 1XVIII i
P G-3 DeAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON
' DATE 12/19/84 3 l
PAGE 2 0F 5 l
. NOTIFICA. TION OF 0FFSITE ORGANIZATIONS l Trris: e
~
It is important that the initial notification of off-site support l organizations be made promptly and with as much pertinent
. information as is available. It should not be delayed if all the
~
information contained on Form 69-10581 is not innediately available. Complete the required initial notifications even if the information provided is changed during the notification process. Provide the updated information as soon as initial notification is complete.
- Figure 1 " San Luis Obispo County Protective Action Zones and Sectors from Plant" and Table 1 "PGandE Recommended Initial General Public Protective Action Criteria" are provided to assist in determining appropriate protective actions to recommend for the general'public. Refer to EP R-2 " Release of Airborne Radioactive Materials" for additional protective action exposure criteria.
~
- 3. Follow-up status reports from the Control Room should also use Form 69-10581. Reports from the TSC should include the information that is appropriate on Form 69-10262 " Radiological Emergency Status Form. Forn 69-10295 " Plant Status Emergency Form" and Forn 69-10296 Onsite/Offsite Radiological Field Monitoring and PIC Emergency Status Form," where such information j
is requested and not available to the organization by electronic i data transmission.
~
- 4. All notifications and contacts with off-site emergency organizations made throughout the course of the emergency should be recorded on Form 69-10298 " Required Offsite Organization Call List" or use Form 69-9221 " Emergency Notification Record" or similar log.
! 5. Primary position holders of certain emergency response positions are provided with VHF radio-equipped company vehicles. Because these persons are essentially on-call at all times, use of these
, vehicles is warranted in off hours to ensure rapid connunication and response. These personnel are identified in Attachment 3 and l
in the call list for on-site personnel in 6-2. l
- 6. Per Adm.inistrative Procedure AP C-1152. " Supplement 2 to !
' Mon-Rout'ine Notification and Reporting to the NRC and Other l Governmental Agencies", use of any emergency procedure which ' results in declaration of any emergency classification requirts
~
l r an "Innediate Notification" and must be reported to NRC l headquarters within one hour.
. 1 1
DC0042 2XVIII : l l .. - . . _ . , . . _ _
onnes.O CANYON POWER PLANT UNIT NO(S) 1 AND 2 hh0N DATE 12/19/84 md. NOTIFICATION OF 0FFSITE ORGANIZATIONS
- 1'
, The Shift Foreman will follow Administrative Procedure AP C-1152 and its "Significant Event Notification Form" for Unusual Events.
. The Site Emergency Coordinator will assure that the mquired
; reporting is accomplished for Alert or higher conditions.
INITIATING CONDITIONS , Notification of off-site emergency organizations shall be initiated by the Shift Foreman when he declares an Unusual Event, Alert, Site Area Emergency, or General Emergency in accordance with EP G-1, " Accident l Classification and Emergency Plan Activation." IMEDIATE ACTIONS _
~ ~
- 1. Upon declaration of an Unusual Event, the Shift Foreman, or his designated representative, shall man a telephone in the Control Room and proceed to contact off-site organizations.
j 2. Upon declaration of an Alert Site Area Emergency, or General
- Emergency, the Shift Foreman acting as the interim Site Emergency Coordinator shall appoint an interim Emergency Liaison
( Coordinator to perform the initial contact of off-site organizations initially from the Control Room and then from the Technical Support Center (TSC).
- . 3. The San Luis Obispo County Emergency Plan provides that the Sheriff will make notifications to the United States Coast Guard (USCG). If the situation at the plant requires immediate protective actions on the part of the general public, and the County Emergency Organization has not had time to be activated, the plant should notify the USCG to place them on standby.
i In the event a Site Area Emergency (with recommendation for evacuation) or General Emergency is declared, and the recommendation for protective action is made within 30 minutes ,of the initial notification of the emergency condition,
. the ..
Shift Foreman or the Interim Emergency Liaison Coordinator will call the 24-hour USCG (Marine Safety Office) phone 415/437-3073
~
l and alert them to PGandE's reconmendations for protection actions. The USCG should also be informed that San Luis Obispo
--( - Cannty has Men informed of the recommendations and will be calling with a request for assistance with the offshore areas in .
the vicinity of the plant. . DC0042 3XVIII
NUMBER EP G-3 - 4 1 AND 2 REVISION 5 Dum.O CANv0N POWER PUWT UNIT NO(S) l DATE 12/19/84 , pAGE 4 0F 5 7ms: NOTIFICATION OF 0FFSITE ORGANIZATIONS SUBSEQUENT ACTIONS, 4 .
- 1. A verbal summary of actions taken to close out an Unusual Event shall be provided each organization notified by the Site Emergency Coordinator or his designated representative.
- 2. Ismediate notification of an increase in emergency classification l ,
or increase in the potential for a release shall be made to San I Luis Obispo County. Status updates shculd be provided
-approximately every 30 minutes to each organiution, for an Alert I> or higher classification, until the EOF arJ TSC are manned. j
- 3. When personnel are available the TSC will be activated for an Alert or higher classification according to EP EF-1. " Activation of the Technical Support Center." iThe Emergency Liaison Coordinator shall man his post:in the TSC Operations Center and ;
i assume responsibility for contact with off-site emergency i organizations from the person in the Control Room. i
- 4. Status updates to San Luis Obispo County will be provided by the procedure EF-3 E0F once .itof
" Activation is the manned-in accordance Emergency Operations withFacility.Emergencg Updates to tCalifornia OES-and NRC will continue from the TSC until these organizations establish their own communication channels and no ,
- longer need status reports. l g: Cnanges in emergency classification or information on the estimated potential for time of or-extent of a release will be immediately provided to offsite organizations when authorized.
- 5. Status reports to other organizations on Form 69-10298 are only required as determined necessary by the Site Emergency .
Coordinator for the organization to provide their support function. RECORDKEEPING All records generated by the utilization of this procedure for an exercise or emergency shall be forwarded the'next working day to the Assistant plant Manager / Support Siervices for , review and retention.
- 1) Records generated from exercises will be categorized as non.
permanent and retained for a minimum of five years. .
)
DC0042 4XVIII l
i . r osaaLO CANv0N POWER PLANT UNnr NO(S) 1 AND 2 Sf0N5
. DATE 12/I9/84 Tms: NOTIFICATION OF 0FFSITE ORGANIZATIONS
- 2) Records generated from actual emergency events will be categorized as lifetime and placed into lifetime storage in
'
- accordance with procedure " Requirements for Retention and Extended Storage of Operation Phase Activity Records.(AP E-151)."
ATTACHMENTS
- 1. Table 1 - Initial General Public. Protective Action Criteria.
la. Figure 1." San Luis Obispo County Protective Action Zones and Sectors from Plant"
- 2. Form 69-10298 " Emergency Offsite Organization Call List"
- 3. Mobile Phone and Pager Instructions
- 4. Fonn 69-10581 " Initial Emergency Notification Fonn"
- 5. Fo m 69-9221 " Emergency Notification Record"
( 6. Form 69-10262 " Radiological Release Status"
- 7. Form 69-10295 " Plant Status Emergency Fonn"
- 8. Form 69-10296 "Onsite/Offsite Radiological Field Monitoring and PIC Emergency Status Form" i.. SUPPORTING PROCEDURES
- 1. EP G-1, " Accident Classification and Emergency Plant Activation"
~
- 2. EP EF-1, "Activatir.n of the Technical Support Center"
- 3. EP EF-3, " Activation of the Emergency Operations Facility".
l
- 4. EP R-2, " Release of Airborne Radioactive Materials"
- 5. AP C-1152, " Supplement 2 to Non-Routine Notification and Reporting to the NRC and Other Governmental Agencies" O
e DC0042 5XVIII $
- , , - - -, , y ,
PGandE Letter No.: DCL-85-051 CURRENT
- EMERGENCY PLAN IMPLEMENTING PROCEDURES ,
.' TABLE OF CONTENTS
. Volume 38 TITLE REY OR-1 Offsite Support 8 Assistance -
3
. OR-2 Release of Infonnation to the Public - 2 EF-1 Activation and Operation of the Technical Support Center 5 "~
EF-2 Activation of .the Operational Support Center 4 EF-3 Activation and Operation of the Emergency Operations Facility 5 EF-4 Activation of the Mobile Environmental Monitoring Laboratory 6 l._ EF-5 Emergency Equipment, Instruments a Supplies 4 EF-6 Operating Procedures For EARS 9845C Controlling Stations 3 EF-651 Transfer of EARAUT Control 1 EF-7 Activation of. the Nuclear Data Communications Systems 1 EF-8 EARS operating Procedures for TSC-CC HP-1000 Station 0 RB-1 Personnel Dosimetry 1 RB-2 Emergency Exposure Guides 1 RS-3 Stable Iodine Thyroid Blocking 0 RS-4 Access to A Establishment of Controlled Areas - Under Emergency Conditions 1 i R8-5 Personnel Decontamination 2 RB-6 Area a Equipment Decontamination 2 R8-7 Emergency On-Site Radiological Environmental Monitoring 3 RB-8 Emergency Off-Site Radiological Environmental Monitoring 4 RS-9 Calculation of Release Rate & Integrated Release 3 RB-10 Protective Action Guidelines 1 R8-11 Emergency Off-Site Dose Calculations 4 RB-12 Mid and High Range Plant Vent Radiation Monitors 1 R8-13 Improved In-Plant Air Sampling for Radiciodines 1
, RB-14 Core Damage Assessment Procedure 1 i R8-15 Sentry Post Accident Sampling System (SPASS)
I Initial Sampling Exercise After An Accident 0 i RB-15A SPASS Initial Actions During An Emergency 1 ! RB-158 SPASS Reactor Coolant Sampling (Stripped-Gas and Diluted RCS) 1 l ., l p 02/04/85 l_ _
2 R8-15C SPASS Containment Air Sampling 1
. R8-150 SPASS Gas Chromatographic Hydrogen Analysis ~ 1 RB-15E SPASS RCS Liquid and Gas Sample Handling . 1
, RB-15F SPASS Data Analysis 0 R8-15G SPASS Sample Storage and Disposal 1 R8-16 SPASS Subsequent Sampling 0 RB-16A SPASS Initial Actions During An Emergency (Not Intended to Meet The 3-Hour Time Limit) 1
. R8-1681 SMS Diluted Liquid Sampling From Reactor Coolant 3
(Not Intended to Meet The 3-Hour Time Limit) 1 R8-1682 SMS Undiluted Liquid Sampling From Reactor Coolant (Not Intended to Meet The 3-Hour Time Limit) 1 RS-1683 SMS Reactor Coolant Stripped Gas Sampling
'(Not Intended to Meet The 3-Hour Time Limit) 1 R8-1684 SMS Diluted Liquid Sampling From Radweste (Not Intended to Meet The 3-Hour Time Limit) 1 RB-1685 STATS Undiluted Liquid Sampling From Radwaste !
(Not Intended to Meet The 3-Hour Time Limit) 1
. RS-16C SMS Containment Air Sampling (Not Intended to Meet the 3-Hour Time Limit) 1 RB-160 SMS Gas Chromatographic Hydrogen Analysis (Not Intended to Meet the 3-Hour Time Limit) 1 . R8-16E SMS Liquid and Gas Sample Handling (Not Intended to Meet The 3-Hour Time Limit) 1 R8-16F SMS Data Analysis (Not Intended to Meet The 3-Hour Time Limit) 0 RS-16G SMS Ion Chromatographic Chloride Analysis (Not Intended to Meet The 3-Hour Time Limit) 1 R8-16H S M S Ph/ Conductivity Dissolved Oxygen (Not Intended to Meet The 3-Huur Time Limit) 1
!- R8-16I SMS Undiluted Containment Air Sampling - l (Not Intended to Meet The 3-Hour Time Limit) 0 RB-16J SMS Sample Storage and Disposal
~
(Not Intended to Meet The 3-Hour Time Limit) 0
$ *9 e
a 02/04/85 0502d/0005K
. l 3D(BrY4E Pacific Gas and Electric Company MUMBER EP EF-4 REVISION 6 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 12/5/84 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 8 EMERGENCY PROCEDURE
- ACTIVATION OF THE MOBILE ENVIRONMENTAL
. y MONITORING LABORATORY
- IMPORTANT 4,PRoysD.
T. 6 ruansnanyn YM I4d6vant TO yg y SCOPE This procedure delineates the requirements and actions to be taken to activate the Mobile Environmental Monitoring Lab (MEML). - This procedure and changes thereto requires PSRC review. GENERAL
~
The MEML will be used to measure radiation levels in the environment at various offsite locations for use in offsite assessment activities. The unit is equipped with an intrinsic germanium (ige) detector; a sodium iodide (Nal) detector; a multichannel analyzer; a Hewlett-Packard 9845C computer with mass storage discs; a high volume ( air sampler; one pressurized ion chamber; emergency instrumentation and equipment kits; thermoluminescent dosimeter (TLD) reader and TLD's; comunications equipment for contacting the onsite Technical Support Center (TSC) and the Emergency Operations Facility (EOF); and its own electric generators. Figure 1 shows the MEML's floor plan. The MEML garage also serves as the storage area for offsite monitoring team equipment and as a staging area for field monitoring activities. It also serves as the office, shop, and staging area for the Normal offsite radiological monitoring program. h. DC0070 IIX
NUMBER EP EF 1 AND 2 REVISION 6 DWBLO CANYON POMR Pt. ANT UNIT NCNS) DATE 12/5/84 PAGE 2 0F 8 I l ACTIVATION OF THE MOBILE ENVIRONMENTAL
" MONITORING LABORATORY Access to a PGandE telephone system can be found in the division $ office area across from the MEML garage (see Figure 2). The doors into the division lunch room are keyed to accept the corporate "3A90909" key. Telephones are located in offices across from the kitchen.
INITIATING CONDITIONS 1
- 1. Emergency Conditions
- a. The Site Emergency Coordinator declares that the plant is in an Alert. Site Emergency, or General Emergency status as defined in Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation." and initiates the emergency I organization in accordance with Emergency Procedure G-2
" Establishment Of The Onsite Emergency Organization."
SUBSEQUENT ACTIONS
~
1.- The staging point for the field monitoring teams and storage area for the radiological emergency kits is the MEML garage located in the San Luis Obispo Service Center, the personnel dispatched to the MEML garage will generally consist of Chemistry and Radiation Protection Technicians (C&RP) the MEML Operators from PGandE Department of Engineering Research, and San Luis Obispo County Environmental Health Department Personnel. - l i-e
- 9 e
e e e DC0070 2IX
o . EP EF-4 NUMBER 1 AND 2 REVISION 6 DIASLO CANYON POWER PLANT UNIT NO(S) DATE 12/5/84
. PAGE 3 0F 8
(, _ ACTIVATION OF THE MOBILE ENVIRONMENTAL m '. MONITORING LABORATORY
- 2. a. When PGandE personnel have reached the MEML garage. -
establish telephone contact with the Radiological Emergency Recovery Manager (RERM) at the Emergency Operations Facility (EOF) (see Attachment 1). If the MEML garage is locked and access cannot be obtained from the DER personnel assigned to the van, then use the telephone in the division office building (see Figure 2). M: If the RERM cannot be reached at the E0F, then contact the Emergency Radiological Advisor (ERA) at the onsite Technical Support Center (see Attachment 1).
- b. If the RERM or the E.RA require immediate deployment of the MEML and/or the field monitoring teams, and access to the
~ '
garage is still not available, inform the RERM/ ERA that access is not available and request the Cypher Pad Coce that will open the door. Also request the ERA to dispatch an individual from the plant to reset the alarm. ( . E: When the alarm is actuated a loud electronic warbler will sound locally.
~
- 3. Activation of the MEML:
M: In the event that the MEML is unavailable MEML personnel will perform the tasks shown on Attachment
. 4 and report to the Cal Poly Environmental Laboratory.
- a. Switch the radiological monitoring equipmant over from house power to the Onan electric ;,ower source by disconnecting the 1 umbilical cord for the. house power. For delineation of steps required for this operation, refer to the MEML Equipment Operations Manual. Disconnect all other shore leads (as per placard on steering wheel).
- b. Start the van and imediately drive van outside garage -
Close & Lock Garage Door. , E: If van is kept in garage with engine or generato'rs i running the fire alarm system will be actuated in a ( very short period of time. DC0070 3IX \- j
NUMBER EP EF-4
~
1 AND 2 REVISION 5 DIABLO CANv0N POWER PLANT UNIT NO(S) DATE 12/5/84
- PAGE 4 0F 8
)
' ACTIVATION OF THE MOBILE ENVIRONMENTAL m MONITORING LABORATORY t
- c. Check the operability of the portable high pressure ion chambers (PIC) including their response to check source and battery levels.
- d. Start the two (2) Onan electric generators. J
- e. Verify the operation and calibration of the multichannel analyzer (MCA) following the calibration procedure in the - MEML Equipment Operations Manual.
- f. Establish verbal contact with the TSC and the EOF via the van's radio and the radio telephone systems.
RADIOLOGICAL MONITORING EQUIPMENT OPERATING INSTRUCTIONS Detailed operating instructions for the radiological monitoring equipment is provided in the van as the MEML Equipment Operations Manual. COMMUNICATIONS I Radio 'comunications includes two-way voice transmission via radio to the TSC, the EOF and field monitoring teams, and radio telephone to - any location served by Pacific Telephone. The radio telephone is the preferred communication means for the van. 4 . FIGURE
- 1. Floor Plan of the Mobile Environmental Monitoring Laboratory 1.a. Left Side View of the Mobile Environmental Monitoring Laboratory 1.b. Right Side View of the Mobile Environmental Monitoring Laboratory
- 2. Garage Layout and Phone Access ATTACHMENTS
- 1. Phone Numbers
- 2. Contamination Control for ttye. Mobile Environmental Monitoring Laboratory
- 3. Mobile Environmental Monitoring Laboratory Sample Log-in Sheet Form #69-11533 5/84 (25)
Cal Poly Environmental Laboratory Activation. )
- 4. ,
SUPPORTING PROCEDURES RB-8 Emergency Offsite Radiological Environmental Monitoring Program DC0070 4IX
~
1 AND 2 DWN.O CANYON POWER PLANT UNIT NCNS) fSf0N6 DATE 12/5/84
- PAGE 5 0F 8 g g'. ACTIVATION OF THE MOBILE ENVIRONMENTAL MONITORING LABORATORY
~
FIGURE 1 FLOOR PLAN OF THE MOBILE ENVIENENTAL MONITORING LABORATORY
!I!! "
ijj! E l 5 8
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- g i
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- f. .
El DTi e DC0070 5IX
NUMBER EP EF ~ ' 1 AND 2 REVISION 6
- OiAaLO CANYON POWER PLANT UNIT NO(S) DATE 12/5/84 PAGE 6 0F 8 ,
)
ACTIVATION OF THE MOBILE. ENVIRONMENTAL
" MONITORING LABORATORY
~
FIGURE 1.a. LEFT SIDE VIEW OF THE MOBILE ENVIRONMENTAL MONITORING LABORATO N N
-{ y
_a~ t _. s 1 _
's
- om g is I~'m l
j e I E
- I k
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sg si :!== !I- ! ) , 3 I DC0070 6IX l l l
~ '
1 AND 2 NUMBER EP EF-4 M CANYON POWER PLANT UNIT %$) REVISION 6 DATE 12/5/84. PAGE 7 0F 8
- ) (.
mm. ' ACTIVATION OF THE MOBILE ENVIR0tMENTAL MONITORING LABORATORY i 2 o 1
~
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DC0070 7IX "7---- N
- y u.c - - - ____.- _ - - - - - --_
NUMBER EP EF-4 - 1 AND 2 REVISION 6 Dust.O CANYON POWER PLANT UNIT NO(S) DATE 12/5/84 PAGE 8 0F 8 . )
~
' ACTIVATION OF THE MOBILE ENVIRONMENTAL i !
m MONITORING LABORATORY E N e 1 4 A i
; I
- i
< . 1 0
)
4
~
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\
10/83 . Page 1 of 1 l 4 PACIFIC GAS AND ELECTRIC COMPANY J: . DEPARTMENT OF NUCLEAR PLANT OPERATIONS
.- (-
. DIA8LO CANYON POWER PLANT UNIT N05. 1 AND 2
- , TITLE
- EMERGENCY FACILITY PHONE NUMBER (ATTACIMENT #1)
- 1. EMERGENCY OPERATIONS FACILITY:
Call Operator Radiological Emergency Recovery Manager ask for or PT&T Radiological Monitoring Director or PT&T UDAC or PT&T 1 l- 2. TECHNICAL SUPPORT CENTER Call Operator Emergency Radiological Advisor ask for (, or PT&T
- 3. DCPP SECURITY Security Shift Supervisor
- or PT&T.
. Central Alam System Secondary Alam System
} l l 9 e O l , (~ ~ . 1 DC0070 9X
~
1/84- Page 1 of 2 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS
. DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 C -
TITLE: CONTAMINATION CONTROL FOR THE MOBILE ENVIRONMENTAL MONITORING LA8 ORATORY (MEML) (ATTACHMENT #2) I. Sample Handling - MEML Personnel
' ~
A. Securely affix a double layer cover on all appropriate work surfaces 1 (i.e., work surfaces used to prepare potentially contaminated samplesforanalysis).
- 8. Gloves should be worn when handling potentially contaminated samples
- ', (e.g., air sampler filter heads and vegetation and soil samples).
i.- C. Perform smear surveys on the sample bags to determine if the outsides of the sample bags are contaminated. i
- 1. If 'a sample bag is contaminated, place it in another non-contaminated sample bag, stored in the van.
- 2. Use good contaminatfor control and ALARA techniques throughout ti the sample analysis, i D. When purging iodine cartridges, avoid contamination by venting the
( effluent directly to the outside of the lab. A purge vent is j' located over the sample handling i>ench and is so marked, i; E. Upon completion of sample analysis, store the samples in a large
, plastic bag. Label the bag.
II. Sample Delivery and Transfer - Offsite Monitoring Teams Personnel A. Field monitoring team personnel should pass samples into the van through the sample transfer door located towards the rear of the van, on the passengers' side. l:' 8. If the sample transfer door is inoperable, the samples may be passed through the backdoor. .
- 1. If possible, field monitoring personnel should remain outside so as not to track contamination into the van. *
- 2. .,'be established just inside the van entrance.If field personnel mu O
e DC0070 10VIII e
-,.e ,e. -
--y- . . - - - . , - - , - - . . , , - ,, - , - n, ,-- . . , , ,,.-,.- - . . . - - - - .- - -
Page 2 of 2 1/84 TITLE: CONTAMINATION CONTROL FOR THE MOBILE ENVIRONMENTAL M -
" LABORATORY (MEML) (ATTACHMENT #2)
- 3. Field monitoring personnel should frisk their hands, feet,and any other potentially contaminated area, before entering the clean step-off area.
- 4. Shoe covers and gloves should be available so that personnel may leave the van and enter contaminated areas, if necessary.
Contaminated personnel should not enter the MEML
- }QE: under any circumstances.
III. A. When analysis is complete, land samples stored, carefully remove the l covering from the work surface (s). Rubber gloves should be worn and care should be taken to ensure the containment of any contaminants present. Dispose of the covering, gloves, etc. in a labeled plastic
~
bag. B. Upon completion of all MEML activities, perform smear surveys If on the inside of the van to ensure that no contamination exists. contamination is found to exist, decontaminate as appropriate. C. If the van was near the plume and the potential for contamination If exists, perform smear surveys on the outside of the van. contamination is found to exist, decontaminate as appropriate. , D. When van is detemined to be free of contamination, return to garage. 1 l . I i 1 . 1 DC0070 11VIII \
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11/84 Pagt 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS
. DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2
(. TITLE: CAL POLY ENVIRONMENTAL LABORATORY ACTIVATION (ATTACHMENT #4)
., 1. Initial Actions (Check) - Perform before departing for Cal Poly ' ; . [] a. Unlock the garage doors / deactivate the garage alam to allow PGandE field monitoring teams to access field monitoring equipment.
[] b. Obtain the following items (as a minimum) to be transported to the Cal Poly lab.
- 1) Current MEML software (floppy disks)
- 2) GM Survey Equipment a E-140/N or equivalent b HP-210/260 or 240 probe c Smear paper
- 3) Standard Ganna Check Source
- 4) Logs / Log Sheets
- 5) Hand Held Radio
- 6) Radioisotope Reference Material
- 7) Surgical Gloves
(, [] c. Motify the following organizations of anticipated departure time: 1 2 TSC E0F (RERM- (ERA-See Attachment See At+.achemt #1 #1) )
. 3 Cal Poly Campus Police ! 6 -
[ ] ' d. Depart for Cal Poly Environmental Laboratory
- 1. Subsequent Actions (Check) - Perform after arriving at Cal Poly.
[] a. Notify the following organizations of arrival at Cal Poly: 1)
- 2) TSC(ERA-SeeAttachment-#1))
E0F (RERM-See Attachment #1 l [] b. Power up equipment and perform a daily calibration per
,, DER procedure.
[] c. Exercise sample / personnel contamination control and ! ALARA considerations as-in the MEML (See Attachment ! #2). . L l DC0070 13VIII l
NUMBER EP RB-10
.FGstE Pacific Gas and Electric Company REVISION 1
. p DATE 10/3/84
{ , DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 15 EMERGENCY PROCEDURE TITLE. PROTECTIVE ACTION GUIDELINES W, , . IMPORTANT
,,,,OVEo W.6 TA A l- M G DATE To PLANI MANgiR SAFETY SCOPE ,
This procedure describes the mechanism for recommer. ding protective actions to the appropriate state and county authorities after the occurrence of a radiological event. Also included, are the bases for the choice of.the recommended protective actions for the plume exposure pathway and ingestion exposure pathway during emergency
, conditions. This. procedure and changes thereto require PSRC review.
l DISCUSSION In a nuclear emergency, an estimate is made of the radiation dose which affected population groups may potentially receive. The dose estimate is called the projected dose. A protective action is an ( action taken to avoid or reduce this projected dose when the benefits derived from such action are sufficient to offset any undesirable features of the protective action. The Protective Action Gu'ide (PAG) is the projected dose to individuals in the population which warrants tsking protective action. A PAG under no circumstance implies an
, scceptable dose. .
AUTHORITIES AND RESPONSIBILITIES
- 1. DCPP Site Emergency Coordinator 1
- a. The authority and responsibility for the decision to notify and to mcomunend protective actions to offsite authorities '
belongs solely to the Site Emergency Coordinator. M: The Recovery Manager assumes this responsibility upon i arrival at the EOF (EP G-2 " Establishment of the On-site Emergency Organization").
- b. TheImergencyEvaluationsandRecoveryCoordinatoris responsible for determining the projected dose which affected population groups may potentially receive and the C -
DC0286 IIII -
i . EP RS-10' OsasLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 $h0N DATE 10/3/84 2 0F 15
- PAGE I
TITuE: ' PROTECTIVE ACTION GUIDELINES
' appropriate protective actions to avoid or reduce the i
,: projected dose. The Emergency Radiological Advisor will assist the Emergency Evaluations and Recovery Coordinator i
- with this assessment. , ; c. The Emergency Evaluations and Recovery Coordinator will t provide the Site Emergency Coordinator with the assessment infonnation.
1 .
- d. The recomendations of the Site Emergency Coordinator will l i be conveyed to the appropriate local and state authorities by the Advisor to the County Emergency Organization located at the E0F/EOC.
I 1 .
- e. The responsibility for implementation of protective actions belongs to county and state authorities, as does the final decision on which. protective action to implement.
- 2. Recovery Manager
- a. After arrival at, and full manning and activation of, the )
EOF, the Recovery Manager will assume responsibility for the . coordination of all offsite emergency response activities. This shall include sole authority and responsibility for the decision to notify and reconnend protective actions to the
- . appropriate county and state authorities. ,
! b. The Radiological Emergency Recovery Manager (RERM) is ! responsible for detennining the projected dose which affected populations groups may potentially receive and the appropriate protective actions to avoid or reduce the projected dese. The Emergency Supervising Engineer (ESE) will assist the RERM with this assessment. The Unified Dose Assessment Comnittee (UDAC), comprised of PGandE, county, state, and federal personnel, will provide the central point of radiological data assessment. l l c. The RERM will provide the Recovery Manager with the assessment information. l
- d. The )ecomendations of the Recovery, Manager will be conveyed l to the appropriate local and state authorities by the ,
DC0286 2II
l NUMBER EP RS-10 Due,0 CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 1 DATE 10/3/84 4 . . PAGE 3 0F 15 ( Tm PROTECTIVE ACTION GUIDELINES
. Advisor to the County Emergency Organization located at the E0F/EOC.
t 3; ,
- e. The responsibility for implementation of protective actions belongs to county and state authorities, as does the final decision on which protective actions to implement.
- . PROTECTIVE ACTION GUIDES AND PROTECTIVE ACTIONS *
- 1. Automatically recommended protective actions based on emergency i' action levels and initial assessment are contained in procedure I j EP R-2 (see also procedure EP G-3)
- 2. PAGs for the Plume Exposure Pathway
- a. PAGs for the general population for whole body external gama radiation and for thyroid dose from inhalation of radioactive material in an airborne plume are as follows:
l
- Projected Whole Body Gama Dose 0.5 - 5 Rem
( - Projected Thyroid Dose 5 - 25 Rem PAG's for the general public are given in ranges. The lowest values should be used if there are no major local constraints in providing protection at this level. Local I
. constraints may, however, make the lower values impractical l to use, but in no case should the higher value be exceeded in determining a need for protective action.
- b. The projected doses are calculated (using EARS or procedure EP R8-11) at the following distances: site boundary (800
, meters miles ((0.5 16.1 miles));
km); 15 2 miles miles (24(3.2 km); km); 5 miles 20 miles (32.2 (8.1km); km); the 10 point of maximum exposure; and the furthest distance where exposure may occur.
- c. For purposes of recomending protective actions, the minimum area affected shall be assumed to be the plume centerline sector and a 22.5* sector en either side of the plume centerline sector, moving radially away from the release point. - --
DC0286 3II
l l
~
DuRO CANv0N POWER PUWT UNIT NO(S) 1 AND 2 ON DATE 10/3/84
- i
' PAGE 4 0F 15 l
' - I Tm2 PROTECTIVE ACTION GUIDELINES .
i
- 2. Protective Actions for the Plume Exposure Pathway
!- a. Table 1 lists the PAGs and recommended protective actions
~
for the plume exposure pathway. The protective actions are classed according to the projected radiation dose which
- l. could be received by the affected population if no ,
protective actions are implemented.
- b. Evacuation Effectiveness .
! The effectiveness of evacuation in limiting radiation dose i'
is a function of the time required to evacuate. If a radioactive plume.is present, the dose will increase with the time of exposure; if evacuation is completed before the plume arrives, then evacuation is 100 percent effective. The evacuation routes are shown in figure 3 " Evacuation Routes".
- 1) Evacuation time. T(EV) is expressed as:
T(EV)=TD+TN+Ty+TT ) where: T time delay after occurrence of the incident D = associated with notificatinn of responsible officials, interpretation of data, and the decision to evacuate as a protective action. . TN = time required by officials to notify people to evacuate. TN = 45 min.* i l
- Tg = time required for people to mobilize and gei ' under way. Ty =
- li hours.* l t
TT = travel time required to leave the affected areas. T 2 3/4 to 71 hours
- for 12-18 i milebounIa=ryincludingSanLuisObispo,
! Mnrro Bay and the Five Cities. area.
*\
e s DC0286 4II
odRNCANv0N POWER PUWT UNIT NOh 1 AND 2
- DN DATE 10/3/84 PAGE 5 0F 15 i-(, TrnE: -
PROTECTIVE ACTION GUIDELINES Plumearrivaltime,t(PA)isexpressedas: 2) l T(PA) = Tg+TT : l- where: ' l l, Tg = time projected before release begins. 1 - TT= time projected for plume travel for given i; windspeed and downwind distances from the
'. start of release.
M: Use Figure 1. " Plume Travel Time vs. Windspeed
, as a Function of Distance Downwind" to determine
} .
T* T
- 3) Compare the estimated evacuation time. T(EV). with the estimated plume arrival time. T(PA) to determine if there are constraints against evacuation. If there are 1 constraints against evacuation use Section 2.c.
Sheltering Effectiveness. (
! c. Sheltering Effectiveness l j
In cases where there is no time to evacuate prior to arrival i ' of the plume or where the projected evacuation tine and time before plume arrival are nearly equal, evaluate the i' benefits of sheltering vs. evacuating and being overtaken by the passing plume.
- l. If evacuation cannot be carried out in sufficient time to offer significant dose avoidance, recomend that officials l- warn the affected population to seek shelter, close windows, i
I
, seal cracks in doors with wet rags, and turn off ventilation systems. Recomend that access be controlled to any area ,
l where either sheltering or evacuation has been implemented. After the plume has passed, ground depnsition will be evaluated to detemine whether dose rates are sufficient to warrant subsequent evacuation. -
\
- 1) Shielding factors for external whole body gama dose are presented in Table 2. Shielding factors from.
DC0286 SII
. . , . _ _ , . . . . . , _ . . _ - . . ___.__._.._.,._...__,......._..._....__.._..._.._..~_m.,.._ . _ _ _ . . . . . _ - _ . _ - - _ . _ _____ _ _
-1 AND 2 h EP RB-10.,
OsASLO CANYON POWER PLANT UNIT NO(S) DATE 10/3/84 PAGE 6 0F 15 . ! I ! Ting: . PROTECTIVE ACTION GUIDELINES external gama rays for individuals in various types of ~ stractures vary widely. To be conservative assume a sF ' ding factor of 0.9 for residences and 1.0 (no !s it)foraclosedvehicle. Muis. ply the projected dose by the external shielding l1 factor to determine the reduction in external gama + dose from the plume. Compare the revised projected ,
- dose to the PAG for whole body gamma dose.
l,
- 2) Shielding factors for an inhalation dose are presented
!. in Figure 2. Shielding factors are for a sealed, ! r wood-frame house. Multiply the projected dose by the inhalation shielding i' ~ factor to determine the reduction in inhalation dose from the plume. Compare the projected dose to the PAG for thyroid dose. i
- 3) For final evaluation of sheltering effectiveness.
l determine whether the whole body or thyroid is the ) critical organ of concern. i The gaseous portion of a radioactive plume may consist l of noble gases and/or vapors such as radiciodines. The l noble gases will not cause as much dose from inhalation ! , as from whole body external exposure and therefore need l not be considered as a separate contributor to , inhalation exposure. ! 3. PAGs for the Ingestion Exposure Pathway
- a. PAGs for the general population for the ingestion exposure pathway are for two levels of response.
- 1) Preventive PAG - applicable to situations where protective actions causing minimal impact.on the food l supply are appropriate. A preventive PAG establishes a i level at which responsible officials should take l ,
protective action to prevent or reduce the : l ' concentration of radioactivity in food or animal feed. I
. 1 i
9 DC0286 611
.s ,
DueLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h EP RB-10
. DATE 10/3/84 PAGE 7 0F 15 TTTUE: PROTECTIVE ACTION GUIDELINES i
i 2) Emergency PAG - applicable'to situations where protective actions of great impact on the food supply
, are justified because of the projected health hazards.
An emergency PAG establishes a level at which responsible officials should isolate food containing
- radioactivity to prevent its introduction into commerce, and at which the responsible officials must 1
determine whether condemnation or another disposition . . is appropriate. .
- b. PAGs for the Ingestion Pathway are as follows
Preventive WholeBygg 0.5 rem Thyroid 1.5 rem j Emergency 5 rum WholeBygg Thyroid (a) Infant thyroid ( c. Although the basic PAG recomunendations are given in terms of projected dose equivalent, it is often more convenient to utilize specific radionuclide concentrations upon which to initiate protective actions. Table 3 shows derived response levels equivalent to the PAGs for radionuclides of interest. l CONCLUSIONS j For foregoing represents considerations and methodology to guide the Site Emergency Coordinator and Recovery Manager in detennination of l recomended protet.tive actions. The actual selection of protective actions must be considered subjectively, as many factors beyond the l scope of the procedure may exist which, in the judgment.of the Site Emergency Coordinator or Recovery Manager, override the criteria i contained herein. l l REFERENCES l l
- 1. " Manual of Protective Action Guides and Protective Actions for Nuclear Ihcidents". U.S. EPA, September 1975 (Revised June, 1980). _
e l DC0286 7II i
NUMBER EP RB-10' 1 AND 2 REVISION 1 DIASLO CANYON FOWER PLANT UNIT NO(S) DATE 10/3/84 PAGE 8 0F 15 . l
~ PROTECTIVE ACTION GUIDELINES m
- 2. " Reactor Safety Study" Appendix VI, WASH-1400, October 1975.
- 3. " State of California Nuclear Power Plant Response Plan", April 1983.
l l
- 4. " Evacuation Times Assessment for the Diablo Canyon Nuclear Power l
Plant". Alan M. Voorhees & Associates. September 1980. l
- 5. " Accidental Radioactive Contamination of Human Food and Animal l Feeds". US FDA, Federal Register, Vol 47, No. 205, October 22, '
j. 1982. l SUPPORTING PROCEDURES , 1 R-2, " Release of Airborne Radioactive Material" RB-9, Determination of Release Rates RB-11. Emergency Offsite Dose Calculations l RB-8, Emergency Offsite Radiological Environmental Monitoring , G-3, Nottffcation of Offsite Organizations TABLES
- 1. Recomended Protective Actions to Reduce Whole Body and Thyroid Dose from Exposure to a Gaseous Plume. i
- 2. Reduc. tion in External Gama Doe from Passing Cloud.
- 3. Radionuclide Response Levels Equivalent to Ingestion Pathway ;
PAGs. FIGURES
- 1. Plume Travel Time vs. Windspeed as a Function of Distance l downwind.
- 2. Inhalation Shielding Factors for a Wood House Snug Doors, Closed Windows. ' . .,
- 3. .
Evacuation Routes -
- 4. Population Within 10 Miles I . 1 DC0286 8II
i
. ..-.. .. .m.. . . - . . . - . . , - - .-.
m -
-~
n< <
. TABLE 1 ' N I j g 9 ,-
j RECOMENDED PROTECTIVE ACTIONS TO REDUCE WHOLE BODY AND THYROID DOSE O
! FR(M EXPOSURE TO A GASEOUS PLUME i Projected Dose (rem to 5 E
- the Population RecommendedActionsI") Comments y i
Whole Body - less than 0.5(b) No planned protective actionsIC) . Previously recommended N :n , j ,; Offsite ahthorities may issue an protective actions may be " { Thyrmid - less than 5 advisory to seek shelter and await reconsidered or M i further instructions. Monitor .teminated, d I environmental radiation levels. 9 E-
- n Whole Body - 0.5 to 5 Seek shelter as a minimum. Consider If constraints exist to E j evacuation /unless constraints make it prevent full-scale R e i
l Thyroid - 5 to 25 impractical. Monitor environmental evacuation,special C i radiation levels. Control access to consideration should be E " affected areas. " }' given for evacuation of E
, children and' pregnant women. "
i Whole body - 5 and above Conduct mandatory evacuation. Monitor Sheltering is an environmental radiation levels and alternativeifevacuation Thyroid - 25 and above adjust area for mandatory evacuation 'can not be promptly
, based on these levels. Control access accomplished.
1 to affected areas. i . ) l (a) These actions are recomunended for planning purposes. Protective action decisions at the time of
- the incident must take existing conditions into consideration (e.g., weather, plume arrival mo==
- time). $$,
(b) The value of 0.5 rem whole body is based upon guidance from the State of California (see . 5" reference 3). wwwm (c) At the time of the incident, officials may implement low-impact protective actions in keeping " R with the principle of maintaining radiation exposures as low as reasonably achievable (ALARA). y
- iE ,
w o
.m DC0286 911 i
EP RB.-10 ' ' OLABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 DATE 10/3/84 PAGE 10 0F 15 -
)
TITLE:
- PROTECTIVE ACTION GUIDELINES TABLE 2 ~
- REDUCTION IN EXTERNAL GAM A DOSE FROM PASSING CLOUD SHIELDINGFACTOR") I AVERAGE RANGE STRUCTURE OR LOCATION Outside 1.0 --
a.
- b. ; Vehicles 1.0 --
Woodframehouse(nobasement)(b) 0.9 c.
~
Basement of wood house
~ -
0.6 0.1 to 0.7 IC) d. Masonry house (no basement) 0.6 ~0.4 to 0.7(c) e. Basement of masonry house 0.4 0.1 to 0.5 ICI f.
- g. 'Large office or industrial building 0.2 0.1to0.3(c.d)
.I l
M: I (a) The ratio of the interior dose to the exterior dose b (b) A wood frame house with brick or stone veneer is approximately equivalent to a masonry house for shielding purposes. (c) This range is mainly due to different wall materials and different geometries. (d) The reduction factor depends on where the personnel are located within the building (e.g., the basement or an inside room).
" Reactor Safety Study", Appendix VI, WASH-1400, October 1975 4
DC0286 101I I
i...
. Diast.O CANv0N POWER PLANT UNIT NCNS) 1 AND 2
; Sf0N
- DATE 10/3/84 l 11 0F !!
4 . PAGE
- b' Tms: PROTECTIVE ACTION GUIDELINES l
i i i
., TABLE 3 a . RADIONUCLIDE RESPONSE LEVELS EQUIVALENT TO INGESTION PATHWAY PAGS 1
Response Level for Preventive PAG I-131 Cs-134 Cs-137 Sr-90 Sr-89 Initial Deposition (uCf/m2) 0.13 2 3.0 0.5 8 Forage Cone (uct/kg) 0.05 0.8 1.3 0.18 3 Peak Milk Activity 0.015 0.15 0.24 0.009 0.14 4-i( . Total Intake fuC1) fuCf/1) 0.09 4.0 7 0.2 2.6 Response Level for Emergency PAG I-131 Cs-137 Cs-134 (- Infant Adult Infant Adult Infant Adult. Initial Deposition (uc.1/m2 ) 3,3 7 3g 3gp- gg y
, Forage Conc fuC1/kg) .5 7.0 13 19 8 17 PeakMilkActivity(uC1/1) .15 2.0 2.4 4 1.5 3 Total' Intake (uti) -
0.9 10 70 80 40 70 Sr-90 Sr-89 Infant Adult Infant Adult Initial Deposition (uCf/m2 ) 5.0 T 80 M
, Forage Cone (uti/kg) 1.8 8 30 700 PeakMilkActivity(C1/1) 0.09 0.4 1.4 30 Total Intake (uct) 2 7 26 400 '
i l I
. '\
" Accidental Radioactive Contamination of. Human Food and Animal Feeds" US FDA.
Federal Register, Vol. 47, No. 205, October 22. 1982. i. DC0286 IIII 4 _ _ _ _ _ -_ _ _ _ _ _ _ . _ _ . _ _ . _ . - . . _ . . _ _ _ _ _ . . _ , . _ , ,,_,..__-,,,_..,,,,,m__.__._..,.,_,_,,,.. % .,....____yy..,.m., _ - .
pues.O CANYON POWER PLANT UNIT NCHS) 1 AND 2 ff0N DATE 10/3/84 . PAGE 12 0F 15 j TrTLE: PROTECTIVE ACTION GUIDELINES FIGURE 1 Plume Travel Time vs. Windspeed as a Function of Distance Downwind , i , I 10 - g.0 - f:: s Avila Beach = 7 miles 4.0 A \ - Sam W s W spo - 10 miles ' 5.0 \\ xx 3 A
\ .
Pisse Beach - 13 efles . Santa Margarita w 18 miles 4.0 MNN Atascasero = to siles - g A l' s N Sa m Park
- 7 miles 3.0 t ,
MDPro Say w 7 miles . ' W X x Nipose- sig siles
\
N \% A , I '.0 \ _ m - M' N 9 t i l N h.0 i b Is . n: w 0.7 s . _.. A m NN N m ( x y x 4 8,0.8 N N NN N xxx
\ \\\ N \\ \
g0.5 c.4 \ \M \\\ \
\ N\ \\\ ( \ , .
r swx O.3
- ~'
0., s -
.g n11g, N \ K 0.,
e M 5.Iwa x hnewsn3 A %Na a = ro = = i 0 DC0286 12II
o , . . . DuGLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EP RB-10 ON DATE 10/3/84 g' ' PAGE 13 0F 15 Tms: PROTECTIVE ACTION GUIDELINES
'l FIGURE 2 t
i , Inhalation Shielding Factors for a Wood House. g snue Doors. Closed Windows P-.
,i
!0 CM - 8 , 3 4 (3.(,m M s N 4
- 8J l . -
!. g *4 mph - .'
- (,t. M )
g
?
, j .6 *
=
i O ,
- l. N '
- l. $ .4 .
% w on essa. 1 mg4 .
(, M M ) i ( w ' g ,g , samst 1M a 0.m in% , E p l . 1 g e. a 4 . . . . EXPOSURETIME(HR) The above curve assumes the house remains closed up for the duration. Actually the dose inside the hocse can be further rtiduced by opening the doors and windows after the cloud has passed and purging the house with fresh air. ' 3
" Reactor Safety Study." Appendix VI, WASH-1400, October 1975
( DC0286 13II ' l t.. ,.
DiAaLO CANYON POWER PLANT UNIT NCNS) 1 AND 2 fg fRS.10'" DATE 10/3/84 PAGE 14 0F 15 - I m LE: ' PROTECTIVE ACTION GUIDELINES FIGURE 3 - l Evacuation Routes 1 .
' _ =
, c' - s.
?
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,, uu .
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'3 i r1 unjor acad=y 3lll' .
LJ Control Point *
- J -
Minor Roadmy I.. .. ! *](, . l O { i Control Point 4 Wrecker Station --- 8. as State naute j V a DC0286 1411
--erawr-, - -e , - - ---s ,w-
W PO ER PLANT UNIT NO(S) EP RB-10
'DebbLO CANYON 1 AND 2
$h0N DATE 10/3/84
, PAGE 15 0F 15 ^! T m.E: PROTECTIVE ACTION GUIDELINES FIGURE 4 I: , Population Within 10 Miles 8 -
. C _ N_
E 9#MI C @ l
. NW seas mes P
WWNW 8 T E. ENE 2 N. ( W E a m I 917 ESE -
-l .
- E SE SW i C O E s, SSE
( mles) U - - C i C3 . i . ! 9tFLEATICBI 1083LB mag. Eles Sing pegnalatlas Instal Mies Ossalattw population C . 42 7 E 43 ~ 7 S-4 s2 E M es 6 10 17.asz 3 0 1o It.ex DC0286 151I I 1
.,__._-_..____y __}}