ML20092L801
| ML20092L801 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/01/1984 |
| From: | PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20092L793 | List: |
| References | |
| 05020-0005K, 5020-5K, PROC-840601-01, NUDOCS 8407020019 | |
| Download: ML20092L801 (118) | |
Text
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PGandE Letter Ns.: DCL-84-199 ATTACHMENT 1 Updates Included In This Submittal DIABLO CANYON EMERGENCY PLAN IMPLEMENTING PROCEDURES Volume 3A Updated Table of Contents EP OP-20, Revision 3 EP R-1, Revision 12 Volume 38 Updated Table of Contents EP RB-8, Revision 4 EP EF-1, Revision 3 EP EF-3, Revision 4 8407020019 840601 PDR ADOCK 0$000275 F
PDR 0502d/0005K L
.s s
^
PGandE Letter No.: DCL-84-199 ATTACHMENT 2 Location of Proprietary / Privacy Information Procedure:
R-1 -- Pages 2,11 and 16 of 16; Attachment - Safety, Health and Claims Personnel to be Contacted for Reporting of Injuries at Diablo Canyon, pages 1 and 2 of 2.
RB-8 -- Page 3 of 49 EF-1 -- Attachment-TSC Activation and Operation Checklist for the Site Emergency Coordinator, page 1 of 2; Attachment - TSC Activation and Operation Checklist for the Emergency Liaison Coordinator, page 1 of 1; Attachment - TSC Activation Checklist for the Emergency Radiological Advisor, page 1 of 2.
EF-3 -- Attachment -- EOF Activation Checklist for the Advisor to the County Emergency Organization, page 1 of 2; Attachment
- E0F Activation Checklist for the Interim Radiological Recovery Manager, page 1 of 2; Attachment - EOF Activation Checklist for the Interim EARS Operator - page 1 of 1; Attachment - EOF Activation Checklist for the Interim Operations and Analytical Recovery Manager, page 1 of 1; Attachment - EOF Activation Checklist for Interim Public Information Recovery Manager, page 1 of 1; Attachment -
E0F Activation Checklist for the Technical Advisor to the PRIM, page 1 of 1; Attachment - Auxiliary Trafier Call Out List, page 1 of 1.
i 0502d/0005K
PGandE Letter No.: DCL-84-199 CURRENT EMERGENCf PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS Volume 3A TITLE REV
' 0P -O' Reactor Trip With Safety Injection 6
OP-1 Loss of Coolant Accident 7
OP-2 Loss of Secondary Coolant 2
OP-3A Steam Gen Tube Failure 5
OP-3B' Minor Steam Gen Tube Failure 1
OP 4A Loss of Electrical Power 1
OP-5 Reactor Trip Without. Safety Injection 5
OP Emergency Boration 6
OP-7 Loss of Condenser Vacuum 2
OP-8 Contrcl Rocm Inaccessibility S
OP-9 Loss of Reactor Coolant Pump 4
OP-10 Loss of Auxiliary Salt Water 2
OP '1 Loss of Component Cooling Water 3
OP-)."
Maifunction of Auto Reactor Control System 1
OP-12A Failure of a Control Bk to Move in Auto 2
OP-128 Cont Withdrawl of a Control Rod Bank 3
OP-12C Cont Insertion of a Control Rod Bank 2
OP-12D Control Rod Pos Indication Sys Malfunc 3
OP-12E Control Rod Misalignment 2
OP-12F Dropped Control Rod 2
OP-13 Malfunction of Reac*or Press Control System 3
OP-14 High Activity in Reactor Coolant 2
OP-16 Nuclear Instrumentation Malfunctions 3
OP-17 Malfunctior; of RHA System 2
0P-18A Loss of Chargina 1
OP-188 Loss of Nomal f.etdown 1
OP-19 Malfunction of Reactor Makeup Control 2
OP-20 Excessive Reactor Coolant System Leakage 3
(
{,
06/01/84 ca-0502d/0005K L
' TITLE REV OP-21 Loss of A Coolant Loop RTD 2
OP-22 Emergency Shutdown 1
OP-23 Natural Circulation of Reactor Coulant 3
OP-24 Loss of Containment Integrity 1
OP-25 Tank Ruptures 2
OP-26 Excessive Feedwater Flow 1
OP-27 Irradiated Fuel Damage 1
OP-28 Startup of an Inactive Reactive Coolant Loop 1
0P-29 Excessive Load Increase 1
OP-30 Inadvertent Load Fuel Assly Improper Pos 1
OP-31 System Under Frequency 1
OP-32 Rod Ejection 1
OP-33 Losc of Instrument Air 1
OP-34 Generater Trip - Full Load Rejection 1
OP-35 Loss of Vital or Non-Vital Instr AC Sys 1
OP-37 Loss of Protection Systen Channel 1
OP-30 Anticipated Transient Without Trip -( ATWT) 5 OP-30 RCP Locked Rotor Accident 1
OP-40 Accidental Depressurization of MS System 1
OP-41 Hydrogen " Explosion" Inside Containment 1
OP-44 Gaseous Voids in the RCS 2
R-1 Per Injury (Rad Related) And/0r Overexp 12 R-2 Rel of Airborne Radioactive Materials 4
R-3 Re1 of Padioactive Liquids 3
R-4 High Radiation (In Plant) 3 R-5 Radioactive Liquid Spill 3
R-6 Radiological Fire 6
R-7 Offsite Transportation Accidents 4
M-1 Employee Injury of Illness (Nonradiological) 11 H-2 Nonemployee Injury or Illness (Third Party) 10 M-3 Chlorine Release 5
M-4 Earthquake 7
M-5 Tsunami Warning 5
M-6 Nonradiological Fire 8
M-7 011 Spill ISO and Clean Up Procedure 6
M-8 Containment Emergency Personnel Hatch 0
M-9 Hazardous Waste Management Contingency Plan 1
G-1 Emergency Classification and Emergency Plan Activation 3
G-2 Establishment of the On-Site Emergency Organization 4
G-2 51 Emergency Organization Call List Fonn 60-10297 0
G-3 Notification of Off-Site Organizations 2
G-4 Personnel Accountability and Assembly 3
G-5 Evacuation of Nonessential Site Personnel 1
06/01 /04 4
0502d/0005K
NtNBER EP OP-20 FGW4E Pacific Bas and Electric Company agyision 3 DATE 5/02/84
(
DEPARTMENT OF NUCLEAR PLANT OPERATicWS l
PAGE 1 0F 6 l
DIABLO CANYON POMR PLANT UNIT NCNS) 1 AND 2 EMERGENCY OPERATING PROCEDURE t
inu EXCESSIVE REACTOR COOLANT SYSTEM LEAKAGE WPORTANT TO t
APPROVED PLANT MA g DATE V
l l
I SCOPE This procedure outlines the steps to be taken in the event of reactor l
coolant system leakage in excess of the Technical Specifications l
limits, yet within the capacity of the charging system.
If leakage is detected, the primary goal should be to identify and isolate or reduce the magnitude of the leak.
l t
l SYMPTOMS Any one or more of the following symptoms may indicate excessive reactor coolant leakage:
i 1.
Unexpected auto mke-up to Volume Control Tank (VCT).
2.
Unexpected charging pump speed or f'ow increase during l
steady-state operation.
3.
Increased level, temperature and/or pressure in the Pressurizer l
Relief Tank (PRT).
i
(
l 4.
Possible annunciators:
l a.
HIGit RADIATION (PK11-21) 1)
Containment Area Rad Monitor alarm.
l 2)
Ir, core seal table Area Rad Monitor alarm.
3)
Sampling room Area Rad Monitor alam.
4)
Charging ptmp room Area Rad Monitor alarm.
5)
Auxiliary bui.lding control board Area Rad Monitor alars.
6)
Process monitor Hi-Rad alarm.
e i
DC0135 III i
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DMLO CANYON POWER PLANT UNIT WS)
'1 ANO 2 S ON DATE 5/02/84 PAGE 2 0F 6 EXCESSIVE REACTOR COOLANT SYSTEM LEAKAGE TITLE.
b.
CONTAI MENT ENVIRONMENT (PK01-16)
PRESSURIZER SAFETY OR RELIEF LINE TEMPERATURE (PK05-23).
c.
d.
PRESSURIZER RELIEF / SAFETY VALVES OPEN (PK05-20) e.
BUILOING SUMPS (PK15-01) 1)
Containment sump high level alarm.
2)
Reactor cavity sump high level alarm, f.
PRESSURIZER LEVEL HI/LO (PK05-21)
PRESSURIZER LEVEL HI/LO CONTROL (PK05-22) g.
h.
REACTOR FLANGE LEAKOFF TEMP HI (PK11-02 j
1.
RCS VALVE STEM LEAKAGE (PK05-8)
AUTOMATIC ACTIONS 1.
Possible charging pump flow increase.
2.
Possible process monitor isolation actions:
Component cooling water surge tank vent valve closure.
a.
b.
Steam generator blowdown and sample line isolation.
c.
Containment ventilation isolation.
3.
Possible PRT vent header isolation at 10 PSIG in PRT.
4.
Possible pressurizer letdown isolation.
OBJECTIVE 1.
Identify the source and rate of leakage.
2.
Isolate the leak, if poss'ible.
3.
Take actions as necessary to comply with Technical Specifications requirements.
DC0135 211
Sf0N DeAaLO CANYON POWER M. ANT UNIT E i, 1 AND 2 DATE 5/02/84 EXCESSIVE REACTOR COOLANT SYSTEM LEAKAGE IlmEDIATE OPERATOR ACTIONS COP 91ENTS 1.
Monitor pressurizer level and start another charging pump as necessary.
i 2.
If pressurizer level continues to drop, isolate letdown.
t 1
3.
If pressurizer level cannot be maintained, manually initiate SI and go to
~
EP OP-0, Reactor Trip with i
Safety Injection.
SUBSEQUENT OPERATOR ACTION 1.
Monitor the VCT level and take manual control as necessary to maintain VCT level.
If charging pump suction is swapped to the i
RWST, comence a rapid load j
reduction and proceed to shut down the reactor.
I l
l l
2.
Attempt to determine the 2.
Refer to STP R-10.
magnitude of the leak while continuing with this procedure.
l 3.
If S/G tube leakage is indicated, go to EP OP-3B, Minor S/G Tube Leak.
4.
Check for indication of 4.
Refer to Technical leakage from PZR Safety Specifications 3.4.4 if valves and PORV's by block valve is closed.
observing discharge temperatures and sonic flow detector.
If leakage is indicated from PORY close the associated block valve.
c DC0135 3II s
b a-
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DMO CANYON POWER PLANT UNIT NCMS) 1 AND 2 S ON DATE 5/02/84 PAGE 4 0F 6 EXCESSIVE REACTOR COOLANT SYSTEM LEAKAGE
,g 5.
If the leak appears to be inside containment:
a.
Check the containment a.
Monitoring system is temperature and located in Mech. Panel dewpoint monitoring 199 next to the HSD system and attempt to Panel. Refer to P&ID determine the location drawing No. 102023 of the leak, sheet 8 for detector location table and b.
Consider making
- map, containment entry for inspection.
6.
Check other possible sources of leakage.
a.
Primary sampling system.
b.
Component cooling water b.
If leakage is surge tank.
indicated in CCW system, go to EP OP-11.
c.
If reactor vessel flange leakage is indicated:
- 1) Close 8032 on VB2.
- 2) Close 8069B, then open 8069A.
3.
Open 8032 and check for indications of leakage past the outer 0-ring.
4.
If leakage occurs past the outer 0-ring, proceed with reactor shutdown.
i DC0135 4II c
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Sf0N OueLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 5/02/84 i
PAGE 5 0F 6 EXCESSIVE REACTOR COOLANT SYSTEM LEAKAGE TITLE I
i d.
Check unusual inflow to liquid radwaste system.
l e.
Check for possible e.
Refer to 09 A-48:IV, discharge into the PRT Table 1 & 2 for list i
from relief valves or of valves that i
valve stem leakoff.
discharge into the PRT.
i
- 7. If leakage is indicated in 7.
If leakage is due to a th? auxiliary building, letdown or charging conduct a radiation survey failure, refer to to assist in locating the EP OP-18.
leak.
- 8. If leak is located, attempt l
to isolate it.
l
- 9. When the leak rate is 9.
Technical Specifications detemined and classified, 3.4.6.2.
take actions as required by the Plant Technical Specification.
- 10. Continue to monitor leakrate as necessary.
DC0135 SII l
i otAaLO CANYON POWER PLANT UNIT NO(Q l AND 2 RE ON DATE 5/02/84 PAGE 6 0F 6 EXCESSIVE REACTOR COOLANT SYSTEM LEAKAGE TITLE.
APPENDIX Z i
EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS l
r i
1.
When this emergency procedure has been activated and upon i
direction from the Shift Foreman, proceed as follows i
I a.
If the leakage rate appears to be less than 50 gpm (pressurizer level can be maintained with one centrifugal charging pump with normal letdown flow) then:
j l
l 1)
Evaluate the leakage rate and identify the type of l
leakage within four hours.
j 2)
If within the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the leakage is determined to be within the LCO of Tech. Spec. 3.4.6.2, there is NO l
emergency and no reporting is required.
3)
If the leakage rate exceeded the LCO and the leakage rate was returned to within limits within the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or if the leakage rate cannot be brought within limits within the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or if there is PRESSURE BOUNDARY j
leakage, declare a NOTIFICATION OF UNUSUAL EVENT and continue to comply with the action statement. Notify l
l plant staff and response organizations required for l
this classification by implementing Procedures G-2 l.
" Establishment of the On-Site Emergency Organization" and G-3 " Notification of Off-Site Organizations" in i
accordance with Emergency Procedure G-1 " Accident I
Classification and Emergency Plant Activation".
b.
If the RCS leak rate is calculated to be >50 gpm or one l
centrifugal charging pump is unable to maintain pressurizer level with normal letdown flow, designate this event an i
Alert. Notify plant staff and response organizations l
required by EP G-2 and EP G-3 in accordance with EP G-1.
I l
l DC0135 6II
otASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h
ON
~
12 DATE 3/29/84 PAGE 2 0F 16 PERSONNEL INJURY OR ILLNESS (RADIOLOGICALLY I' M RELATED) AND/OR OVEREXPOSURE I
b.
Notify the centrol room (Shift Foreman) as soon as practical, anc provide a phone number for the patients location.
NOTE:
T shift be notif'ed h dialirg Ext.
ialing" fctig tes the t re a errr. anc rredical emergency coce cei..
Tre callcr cust remain on the phcr.c t., er.at,it tre Sn1 # 1 Foreran to dial inte a conference call.
2.
5r 't Fs ec.ari,:rterim Si*e Ererge"., Cccedicat r,
r a.
Eve hate plar stat s that r ay ha,e ;, rec.:ec tne pe-s:r-C
- r;ury, iiir.ess ana.c c.e e pcsure.
S- -c tne st.e energe :3 signai to cle?r tne a'f t.:teo a<en, if the situa*.';a warrirts it.
b.
Discatch acdit ce 1 first alc ce sJ,ne.el uch as tne pra;e:.
i construction EMI
'the scene cete ir,ary or t' ires
- quired, c.
E iaticn Protection personre' d.
Cal' an ambulance if the injury warraitt:
't.
Refer to Appendix 1 "Peasures to be taken if Fecical. Care Is Requirec for instructions.
SCESEQUENT ACTIONS The Shift Fereman shall airect all subs =.
actions urtil relievea by the long-terr.t Site Emergency Coordinator if the situatien s.arrants it.
1.
Actions Comon to All Occurrences Transport the patient to.the first aid rcom, proviced that a.
this can be done without aggravating tnE injury.
b.
Take actions as specified in the followirg sections as apprcpriate for the,particular occurrence.
Section 2:
Mircr injur, when conteririation is present.
i l
A
.. _ ) Y
NUMBER EP R-1
,d w.A, Pacific Gas and Electric Company REVISION 12
[T.TLE DATE 3/29/84 OEPARTMENT OF NUCLEAA PLANT OPERATIONS PAGE 1 0F 16 j
DIABLO CANYON POWEA PLANT UNIT Nots, 1 AND 2 EMERGEf;CY PROCEDURE i
PERSONNEL INJURY OR ILLNESS (RADIOLOG:CALLY i
RELATEC) Ahbf0R OVEREXPOSURE i
AppAOVEC _ _. - Y.
_ __5-3 44 PLAriTPA!.gP DATE SCOPE l
This proceAra describei the act c's v+icn are.c be tak e. ir
.r e event of:
Persu r.cl in;ury or Gines, 0 ce or ser'c s, ane<e t r. c. : - -
is rac:clegically ccrtami etec.
2.
C.,.eceipcssre Nr suspectec cve erec..re, #rcr. er external 3.
Overexposure (cr suspectec vverexpos re) fro:t ari :rternal sc sce.
4 A certinatien cf the aceva.
Injuries or illnesses v.bich do nct tr.volve radice:tive ccr.taminaticr.
- r overexposure are har.dleo in acccrdance with Er
- ergency Procedures N-1 or M-2.
This procecure and changes tnereto rcquires PSRC review.
D:5CUSSION Any radiologically related injury or illness or pctential rac1ation l
uverexposure is a serious matter recuiring pron.pt a tention tc the care of the patient anc prompt appropriate correctise tction to preclude re-occurrence.
In addition, followup irsestigation to Quantify the extent of exposure to radiatier. requires care in the gathering and retention of samples, raciation reac:r.gs and other evidence which may contribute to the understanaing tf the incides t er.c assist both ir. care of the injured and in preventing re-occur erce.
'MMEDIATE ACTIONS 1.
The employee (s) who are at the scene sliall:
a.
Pender all r.ecessary first aid.
l g
- 5
,4 1h f
i 1
i
$0N osaaLO CANYON POWER PLANT UNIT %S) 1 AND 2 DATE 3/29/84 PAGE 3 0F 16 y,7 m PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/OR OVEREXPOSURE Section 3: Serious injury when ccntamination is present.
Section 4: Overexposure from external source Section 5: Overexposure from internal source.
Perfom the notifications required by Appendix Z " Emergency
[
c.
Procedure hotification Instructions."
i NOTE:.Fom 69-9221 " Emergency Notification Record" is provided to record notif1 cations not documented elsewhere, d.
Collect personnel dosimetry assigned to the incividual and
[
have it evaluated.
l e.
Begin gathering infomation to assist the long-term Site Emergency Raciological Advisor in his evaluation. Guicance on things which should be investigated is given in Appencix 2 " Factors to Consider in Making a Preliminary Evaluation."
f.
Close out the event with the following writte, reports:
1)
Report to NRC (required within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for an Unusual Event, or within 30 days for a report under 10CFR20.403).
2)
Fom 62-4587 " Report of Industrial Injury to Employee."
3)
Fom 62-4586 " Employers' Report of Occupational Injury or 111 ness."
4)
Nuclear Plant Problem Report.
(See huclear Plant Administrative Procedure C-12.)
g: 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.
i-DC0084 1XII
9 NUMBER EP R-1 DIA84.0 CANYON POWER Pt. ANT UNIT NOIS) 1 AND 2 REVISION 12 i
DATE 3/29/84 PAGE 4 0F 16 7rg PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY j
RELATED) AND/OR OVEREXPOSURE 2.
Minor Injury or Illness When Contamination is Present The following steps apply to injuries where prompt medical attention is not required (i.e., first aid at the plant is adequate).
a.
Make the following surveys and record the results on the
" Skin and Clothing Decontamination" Form (Fortr 69-9392).
1)
The wound prior to decontamination.
2)
The object causing the injury (if possible) and any clothing penetrating or toucning the injury. These r
items shoulc be retainec, if possible, until the long-terrn Site Emergency Rac1clogical Advisor has completed his evaluation so that detailed radionuclide analysis can be performed, if required.
3)
The wound during each decontamination and after final decontamination.
NOTE: These personnel surveys are in addition to other radiological surveys (e.g., work area, equipment) l which may be required by radiation protection j
management.
b.
Decontaminate the wound using the standard procedures l
discussed in Radiation Control Procecure G-4.
In cases of severe contaminstion, where there is a realistic possibility l
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.
g: Refer to Emergency Procedure RB-5 " Personnel i
Decontamination" in the event nortnal decontamination facilities are overloaded or unavailable.
c.
Complete any additional first aid measures.
n DC0084 ax!!
i l
otAaLO CANYON POWER PLANT UNIT NO(S) 1 AND. 2 ON 2
DATE 3/29/84 PAGE 5 0F 16 PERSONNEL INJURY OR ILLNESS (RAD 10 LOGICALLY f
W RELATED) AND/OR OVEREXPOSURE i
r d.
Complete accident report Form 62-4587, " Report of Industrial Injury to Employee" and forward to plant clerk for processing.
NOTE: This documentation requirement assumes no medical attention-(beyond first aid) is required and that ne lost time occurs.
If lost time beyond the day of injury is likely, or if medical treatment (includin; doctor referral) is required, complete Forn 62-4586
" Employers' Report of Occupational Injury cf Illness" and forward to plant clerk.
3.
Serious Injury or Illness When Contamination is Present The following steps apply to injuries or illnesses where pror;t medical attention is required (i.e., the patient must be taker. 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 Artulance 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
" Skin and Clothing Decontamination" Form (Fom 69-9392.)
1)
Survey any wounds and/or the victim's skin (if l
possible).
2)
Survey the object causing the injury (if possible) and any clothing penetrating or touching the injury. These items should be retained, if possible, until the long-term Site Emergency radiological Advisor has completad his evaluation so that detailed radionuclide analyses can be performed, if required.
C l
DC0084 5X11
i NUMBER EP R-1 DiAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 12 DATE 3/29/84 PAGE 6 0F 16 7,7 2 PERSONNEL INJURY OR ILLNESS (RAD!0 LOGICALLY RELATED) AND/0R OVEREXPOSURE 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 $1te Emergency Radiological Advisor.
MTE: Refer to Emergency Procedure RB-S " Personnel Decontamination" in the event normal decontamination facilities are overloaded or unavailable.
c.
Have the hospital kit and a handheld 'adio available for r
transport to.the hospital with the monitor accompanying tre patient, or the team dispatched to the hospital.
l 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 l
limit contained in Radiation Control Standard ho. 1, and where the individual does not require prompt medical attention for any other reason. Fersonnel suspected of overexposure shall not re-enter radiation controlled areas unless authorized by the Site Emergency Coordinator.
l a.
Provide any first aid or medical attention which the patient may required.
t-b.
Notify San Luis Anbulance anc. French Hospital and transpcrt I
the patient to French Hospital in accordance with Appendix 1 l-for observation or treatment in any of the following circumstances: 1)
The patient is known or suspected to have received at least any of the following:
I j
a) 25 rem to the whole body, active blood fonning l
organs, lens of eyes, gonads, head or trunk.
l l
l I
l l
DC0084 6XII l
L
e
-4
' S.
0iAsLO CANYCW POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP R-1 REVISION 12 DATE 3/29/84 PAGE 7 0F 16 7,77 PERSONNEL INJURY OR ILLNESS (RAD 10 LOGICALLY RELATED) AND/OR OVEREXPOSURE b) 150 rem to the skin.
-c) 375 rem to the extremities.
2)
The patient shows signs of radiation sickness, such as nausea, vomiting, extreme sweating, weakness, diarrhea, extreme anxiety, incoherence, sensitivity of the nerves (tingling or itching sensation).
3)
The patient 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 wamth and itching.
Redness, blistering and other effects may not appear for several days.
c.
If the patient requires transportation to the hospital, during the interval until the ambulance arrives keep the patient comfortable. Survey the individual and perform any decontamination which circumstances require and/or pemit.
f Do not aggravate any injury or unduly alarm the patient in performing these operations. Record survey results on the
" Skin and Clothing Decontamination" Fom (Fom 69-9392) l 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 l
particularly important if internal deposition of radioactive materials is suspected.
e.
Collect the patient's personnel dosimetry and any materials which may)have been activated (if a neutron exposure is suspected such as belt buckles,' watches, jewelry, prior to l
sending him to the hospital or releasing him. This will be processed for evaluation.
f.
Subsequent actions will be based upon the results of the evaluation of the external exposure.
L s
I e
---+-m.--. ---..,.-
$ ON l
DAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 l2 DATE 3/29/84 l
PAGE 8 0F 16 ratg PERSONNEL INJURY OR ILLNESS (RADIOLOGICALLY RELATED) AND/OR OVEREXPOSURE 5.
Overexposure From Internal Sources The following steps apply to cases where the patient has (or is suspected to have) ingested a significant quantity of radioactive material.
If the ingestion was by breathing, this procedure applies any time that the concentration to which the persor. has been exposed is greater than or equal to (MPC) x PF, where (MPC) refers to the norwal (40 hr.) maximum permissible concentration, l
l and PF refers to the protecticn factor the patient obtained when l
a quantitatively fit tested to the respirator that was worn for tne job.
t l
a.
Take any medical action which may be required as a result of injury or external dose received (Steps 3 and 4 above,. Tne l
treatment of these effects should take precedence over the evaluation of internal exposure.
l b.
Remove anc retain for subsequent radiological analysis the l
patient's clothing and respirator.
I c.
Survey the patient thoroughly and record the results on the -
l
" Skin and Clothing Decontamination" Form (Form 69-9392).
i d.
Decontaminate individual to as low as practical without l
causing further injury.
If practical, save samples of the decontamination solutions, swabs, and other materials which l
may be of use in subsequent radiological evaluations.
e.
Count the patient on the whole body counter. The results of i
this analysis will, in large measure, oetermine the necessity for further medical attention or surveillance.
i f.
Collect and save any urine, feces, or vomit which is passed f rom the patient. The long-term Site Emergency Radiological i
Advisor may request that special urine samples be collected l
for bioassay.
I g.
Subsequent actions will be based upon the results of the evaluation of the internal exposure.
l l
h.
If the patient is sent to the hospital, make arrangements to have all urine, feces or vomit samples retained for radiological analysis.
i
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i j
DC0084 8XII j
t 0AaLo CANYON POWER PLANT UNIT %S) 1 AND 2 h0N 12 DATE 3/29/84 PAGE 9 0F 16 I' M PERSONNEL INJURY OR ILLNESS (RAD 10 LOGICALLY RELATED) AND/OR OVEREXPOSURE REFERENCES 1.
Radiation Control Standard No.1, " Personnel Exposure."
2.
Radiation Control Standard No. 2. " Internal Expcsure Controls."
j 3.
Radiation Control Standard No. 5. " Medical."
4 Raciation Control Standard No. 8, " Reporting Requirements."
5.
Radiation Contrcl Procedure No. G-3, " Personnel Interr.a1 Expost.re i
Control."
6.
Raciatier Control Proceoure hc. G-4, " Personnel Contacinatior Centrci."
7.
Radiation Control Procecure No. G-7, " Radiation Surveys."
8.
Emergency Procedure G-1, " Accident Classification and Emergency Plan Activation."
9.
Emer*gency 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."
i
- 13. Emergency Procedure OR-1, "Offsite Support anc Assistance" l
APPEhCICES 1.
Appendix 1. Measures To Be Taken If Medical Care Is Required.
2.
Appendix 2. Factors To Consider In Making A Preliminary Investigation.
3.
Appendix 2. Emergency Procedure hotification Instructions.
1-i C
I DC0084 9XII
i NUMBER EP R-1 OsaaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 12 DATE 3/29/84 PAGE 10 0F 16 r,7 g PERSONNEL INJURY OR ILLNESS (RAD 10 LOGICALLY RELATED) AND/0R OVEREXPOSURE ATTACHMENTS 1.
Form 69-9221. " Emergency Notification Record."
2.
Form 69-9316, " Radiation Dose Rate Survey Record."
3.
Form 69-9392, " Skin and Clothing Decortamination."
4.
Form 62-4587, "Repcrt of Incustrial Injury to Employee."
l S.
Fere 62-45Ef, " Employers' Repcet of Occupational Ir. jury or lilness."
6.
Fo rm 62-6015, " Medical Referral.
t
[
7.
Light Duty Program Letter.
i 8.
Safety. Health and Claims Personnel to Be Contacted for Reporting of Injuries at Diablo Canyon (3/83).
I n
DCD084 10XII L
I
[ ON DMO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 12 DATE 3/29/84 PAGE 12 0F 16 mg PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/OR OVEREXPOSURE APPENDIX 1 (Cont'd)
MEASURES TO BE TAKEN IF MEDICAL CARE 15 REOUIRED b.
Company affiliation.
l l
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 know.;.
r f.
Extent of in3ry, illnes s or symptoms.
9 Meolcal histcry (if knowr).
n.
Raciological conditicns.
Recced this inforv.ation on Fom 69-9221, " Emergency Nctificatico Recorc", or other suitable log.
4.
Prior to arrival of the ambulance, the patient should be decontaminated to the extent practical without aggravation of i nj u ry.
5.
If the patient cannot be completely decontaminated prior to arrival of the ambulance, wrap him in a blanket prior to placing him in the ambulance in order to minimize the spread of contamination. Alternatively, he may be placed in the plant's Nuclear Accicent 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 handhela radio with him.
g: Two hospital kits and radios are stored in Access Control.
Additional equipment and radios are also available at the PG&E San Luis Obispo Service Center.
7.
Two additional individuals qualified in radiation monitoring should be dispatched to French Hospital to assist hospital personnel.
OTE: Refer to EP OR-1 "Offsite Support and Assistance" for air ambulance and medivac support.
I DC0084 12XII
1 l
otAsto CANYON POWER PLANT UNIT NOISI 1 AND 2 h0N 12 DATE 3/29/84 i
PAGE 11 0F 16 i
7,7 g PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/OR OVEREXPOSUPE l
l APPENDIX 1 MEASURES TO BE TAKEN IF MEDICAL CARE IS REQUIRED The following are the procedural steps to be taken in the event a contaminated patient must be transpcrted to the hospital for mecical treatment:
1.
CallSanLuisAmbulance[ Phon Emergency ho, f
anc provice the follow 1ng informattor:
{
a.
Name of caller.
i f
t b.
Cory.ary a f filiatien.
i c.
Pnene number of caller. (Where he can be reached.)
Name of injureo or ill person.
d.
e.
Where the patient is located.
f.
Where the patient is to be transported (French Hospital).
g.
Nature of injury or illness.
I h.
Patient is contaminated.
1.
Any other medical information which might be pertinent to I
transporting the patient.
Record this information on Form 69-9221. " Emergency Notification j
Record," or other suitable log.
l 2.
Contact the Security Shift Superviso nd' ave him call l
the security force at the Port San Luis entrance rfd alert them that the ambulance is entering.
It is a o a visable j
4 to have an escort accompany the adulance from the Security Building to the first aid room to minimize the delay in reaching l
the destination.
i 3.
The victiri shall a
te e, French Hospital. Call ahead to the hospital and provide the following l
information:
i a.
Name of caller.
t k
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osaaLo CANYCW MM PLANT UNIT NCNS) 1 AND 2 V
ON 12 DATE 3/29/84 PAGE 13 0F 16 yir a PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/OR OVEREXPOSURE APPENDIX 2 FACTORS TO C0hSIDER IN MAKING A PRELIMINARY INVESTIGATION l'
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). Al so,- two other factors are important in conducting an investigation of this type, namely:
a) information which is gathered shoulc be written cowr 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, collectior.
time, sample identification, and other pertinent. data.
1.
Factors Common to All Accidents a.
Date, time of occurrence.
b.
Basic reconstruction cf events.
Probable source (s) of radioactivity involved.
c.
d.
Names and addresses of all witnesses.
2.
Considerations in Evaluating External Exposure a.
Exactly where was the patient located at the time of exposure?
b.
How was patient physically oriented with respect to source (will help to evaluate nonuniform exposure)?
c.
On what part(s) of body were dosimeters being worn?
d.
Were self-reading dosimeter readings recorded and all nonself-reading types collected?
e.
Are there any " natural" dosimeters available? (Belt buckles, wrist watches, gold tooth fillings, and other such items are useful in determining neutron dose.)
f.
Exactly what was the time interval over which exposure occurred?
e
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i DiAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EP R-1
)
DATE 3/29/84 l
PAGE 14 0F 16 i
ri7 g PERSONNEL INJURY OR ILLNESS (RAD 10 LOGICALLY RELATED) AND/0R OVEREXPOSURE F
g.
Are there any applicabie dose rate measurements, and if so,
~
exactly where and when were they made?
1)
Ion chamber measurements l
2)
Area monitors 3)
Other h.
What was the status of the plant at time of expcsure?
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 occurree?
c.
Can sar:ple(s) of liquids which were internally deposited be obtained?
t d.
Can samples of airborne activity which were breathed be
[
obtained before the area is purged?
(
e.
Are there any applicable monitor readings?
l I
1)
Process monitors j
2)
Continuous Air Monitors 3)
Area Monitors 4)
Other 1
i f.
Can samples of patient's clothing, decontamination j
solutions, secretions, respirator filters, be saved?
9 Can the region in the vicinity of the oc:urrence be smear-tested, or can decontamination solutions be retained?
l l
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1 otAaLO CANYON POWEER PLANT UNIT NO(S) 1 AND 2 ON 12 DATE 3/29/84 PAGE 15 0F 16 y,7 g PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED) AND/OR OVEREXPOSURE APPENDIX Z EMERGENCY PROCEDURE NOTIFICATIOh INSTRUCTIONS 1.
When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
L a.
In case of a minor injury with contamination present or an overexposure case from any source which does not meet tne criteria for an Unusual Event, notify the Plant Mar.ager, Plant Superintendent and Supervisor of Chemistry and Radiation Protection or their designated alternates.
b.
Designate this a Notification of Unusual Event in any case of an injury or overexposure requiring transportation of the patient to an offsite hospital or if extensive 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 i
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."
c.
If the case involves an overexposure from an external source which exceeds:
l Inunediate Notification
150 Rem Skin 30 Rem Skin 375 Rem Extremities 75 Rem Extremities Notify the Director, NRC Region 5 by telephone and l
telegraph, mailgram and ficsimile within the applicable time i
frame described above.
Indicate the notification is pursuant to 10 CFR20.403 (Notification of Incidents).
' Designate this a Notification of unusual Event and complete the additional notifications prescribed in section 1.b.
above.
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f0N oiAsto CANYON POWER PL. ANT UNIT NO(S) 1 AND 2 12 DATE 3/29/84 PAGE 16 0F 16 7,7 g PERSONNEL INJURY OR ILLNESS (RAD 10 LOGICALLY RELATED) AhD/OR OVEREXPOSURE 2.
In addition to notification perfomed above, also notify the following in any case where NRC notification is required.
Supervising Nuclear Generation Engineer (Personnel ard a.
Ensironmental Safety) or his alternate in the Departnent of huclear Plant Operations:
/
l_
Mr. W. H. Fujimoto PGandE:
Plant Ext.:
Home:
t.
Compensation Claims Representative in the Department of Safety, Health and Claims, per the attached list of personnel.
NOTE:
- 1) The System Dispatcher will handle the notification of General Office Personnei if they cannet be promptly reached.
- 2) Nuclear Mutual Limitec (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 g
when required. American Nuclear Insurers / Mutual Atomic Energy Liability Undeneriters ( ANI/MAELU) holds third party insurance coverage and would be similarly notified in accidents involving a third party.
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DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POER PLANT RADIATION DOSE RATE SURVEY RECORD DATE TIME SWP/RWP NO SURVEY NO.
AREA OR EQUIPMENT TYPE OF SURVEY SHEET OF ITEM BETA GAP 94A NEUTRON g-DESCRIPTION i
m rad /hddistance mR/hrldistancer. rem /hr I distance i
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l SURVEYED BY SURVEY TYPE INSTRUMENT TYPE DETECTOR SERIAL NO.
DATE CALIB. DUE BETA GA!94A NEUTRON C0fMENTS l
RECCMMENDATIONS i
i SURVEY REVIEWED DATE SUPERVISOR
. 9392 4/84(100)
PACIFIC GAS AND ELECTRIC COMPANY Page 1 of I DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 SKIN AND CLOTHING DECONTAMINATION REPORT RCP G-4 NAME EXPOSURE ID#
DATE/ TIME RWP/SWP NO.
DECONTAMINATION LOG NO.
Plant locatio' where contamination occured Cause of contarination Skin condition a#ter decontar.ination 1
Radiation Prote::icr, Te: ret:1a-Use drawings below to identify where and what leve's of contamination present. Show post decontamination l evel s.
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f.a., las r.'me in;urt as, nas c-amatically inenasac.
.T we selieve cat s=me of =is time away f =s work signt==ss-!bly 22 avcicac if =a availamility of lign: (socidiec) auty or cask-r/pa wort ners =n wicaly kaswi. %ssa pnysicians have sutac ma in same ca.res ma paren will russent more rapidly u treetzent if kast busy in a lignt-cuty casac4/.
%c;;va, lign:-cuty a.ssignmanu are almest always availa=ia far ac:icyses enleasac '=r = ors =imin ma socical res==icticas ass =lisnee by me ;nysician.
t It our =clicy 23 have an injured art:1cyee ac=mmanied by a su=arvis.-- cr l
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3/83 PACIFIC GAS AND ELECTRIC COMPANY Page 1 of 2 i
RW9 DEPARTME'4T OF NUCLEAR PLANT OPERATIONS j
DIABLO CANf0N POWER PLANT UNIT N05.1 AND 2 i
j j
Safety Health and Claims Personnel to be l
]
_ Contacted for Reoorting of Injuries at Diablo Canven1 1
}
EMPLOYEE INJURIES i
i lI In all cases of serious encloyee injuries (for example, injuries involving l
i hospitalitation, electric contact, hernia, amoutation, fractures, or
)
injuries expected to result in lost time from work beyond the day of injury}
f or deatn, which occur while on the joo, report should be made as follows:
't l
Ourine werkinc Hou-s:
T. S. Honey PGanoE loca (If Mr. Money is not available, the person answering the tele none v
tace l
the message ano notify Mr. Honey or any other parties necessary in tne i
Safety Healtn ano Claims Depart:nent).
l Any Othea Time:
Report to one of the persons on the following list, trying each in or:er
~
until one is contactac:
k ',
1.
- 7. B. Honey Pinole 2.
A. Thomas San Francisco i
3.
C. B. Powell San Francisco l
4.
P. 5. Benitez San Rafael 5.
T. G. Scott Oakland l
6.
L. Lasagna Albany 7.
C. W. Allen San Francisco 8.
B. L. Wade La rtspur i
9.
J. A. G11rene Danville 10.
J. C. Vocke Lafayette 11.
W. A. Hutchison San Carlos 12.
M. C. Dolan Oakland 13.
M. W. Johnson Walnut Creek la.
R. W. Hall Richomed 15.
I. M. Crawford Hercules 16.
R. G. Schumaxer El Granada 1
17.
R. D. Fagg San Rafael J
18.
P. C. Soettcher Mortga f
19.
H. W. Reynolds Sunnyvale 20.
B. P. Sadler.
8elmont i
L j
AThis listing extracted from Safety. Health, and Claims ammo regarding f
Personnel to be Contacted for Reporting of Accidents, dated 01/13/83.
L DC0084 16VIII
. t
~
hatety, Mealtn anc CtW1ms7er'sonnel to De
~
Contacted for Reporting of injuries at Stablo Canyon Page 2 of 2 Mon-Emoloyee Injuries e
C. O. Schreil, San Luis Obispo ffice) j j
office) home)
I If he cannot be reached, contact one of the following in order of
{
preference:
During working hours:
B -i 1.
John C. Echols 2.
Ocus G. Keolar 3.
George G. Perry (collection only) j
>3 After =ceting hou s on Monday :nrougn 8:00 a.m. en F-1 day, except he' cays:
{
i 2'
1.
John C. Echols Pieasan: Hi
{
2.
Doug G. Keeler Concere 3.
Joan C. Vocke Layfayette 4
Amos L. Bech old Cupertino L
5.
William.4 Bingaman NCvato 6.
E. An:nony Giucici San Carlos 7
J. Alex McCorcuoca'e San Ramen S.
Smca P. Sadler Beimont 9.
George G. Perry Hapard (collection only) 10.
Stanley W. Jenns:en Fairfiel d
(!
i After 5:00 p.m. on Fridays to 8:00 a.m. on Mondays and holicays:
l Contact the Investigator delegated to stay on call for all emergencies.
He
.any be reached through the System Dispatener.
If he is not availacie, the Dispatcher will follow the procedures for "After Working Hours."
l i
l
)
l l
L
)
1 1
l 1
L OC0084 17yII se
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dQs; s.
P,GandE Letter No.: DCL-84-199 CURRENT EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS Volume 3B TITLE REV OR-1 Offsite Support & Assistance.
3 OR-2 Release of Information to the Public
-2 EF-l' Activation and Operation of the _ Technical Support Center 3
~EF-2
' Activation of the Operational Support Center 2
~EF. Activation and Operation of the Emergency Operations Facility 4
EF-4 Activation of the MEML 4
EF-5 Emergency Equipment, Instruments & Supplies 4
EF-6 Operating-Procedures For EARS 9845C Controlling Stations 2
EF-651.
Transfer of EARAUT Centrol 1
.EF-7 Activation of _ the Nuclear Data Communications Systems 1
-EF EARS Operating Procedures for TSC-CC HP-1000 Station 0
RB-1 Personnel Dosimetry 0
- RB-2.
Emergency Exposure Guides 1
RB ~ Stable Iodine Thyroid Blocking 0
RB-4 Access to a Establishment of Controlled Areas Under Emergency 0
RB-5 Personnel Decontamination-0 RB-6 Area & Equipment Decontamination 1
-RB-7
_ Emergency On-Site Radiological Environmental Monitoring 3
RB-8 Emergency Off-Site Radiological Environmental Monitoring 4
RB-9 Calculation of Release Rate & Integrated Release 2
Protective ~ Action Guidelines 0
.RB ' Emergency Off-Site Dose Calculations 3
RB-12 Mid and High Range Plant Vent Radiation Monitors 1
RB-13 Improved In-Plant Air Sampling for Radiof odines 0
RB-14~
Core Damage Assessment Procedure 0
(
06/01 /84 0502d/0005K
0
'O 3D@rstE PacNic Gas and Electric Company NUMBER EP RB-8 REVISION 4 DEPARTMENT OF NUCLEAR PLANT OPERATKWS DATE 5/2/84 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 49 EMERGENCY PROCEDURE TITLE EMERGENCY OFFSITE RADIOLOGICAL i IMPORTANT ENVIRONMENTAL MONI RI TO D2
/
SAFET/
APPROVED PLANTMANKEMENT DATE SCOPE This procedure and changes thereto requires PSRC review.
i This procedure describes the emergency offsite radiological environmental monitoring program which would be undertaken in the event of an airborne release of radioactive materials from the Diablo Canyon Power Plant. The procedure provides instruction for implementation of the program. Also provided are instructions to monitoring teams for locating sample points, collecting samples, and performing field analyses of samples.
INITIATING CONDITIONS The Site Emergency Coordinator declares a Site Area or General Emergency in accordance with EP G-1, " Accident Classification and Emergency Plan Activation". Offsite environmental monitoring teams may be dispatched for an Alert classification if judged appropriate by the Site Emergency Coordinator.
j DIRECTION AND CONTROL Offsite monitoring teams and the Mobile Environmental Monitoring Laboratory (MEML) will be initially dispatched at the direction of the Emergency Evaluations and Recovery Coordinator (EERC) in the TSC or Control Room.
The offsite monitoring teams and MEML may receive operating instructions from the Emergency Radiological Advisor (ERA) which may be through a liaison assistant. The ERA will keep the EERC informed of the offsite monitoring team activities.
After the EOF has been fully manned and activated, the Radiological Emergency Recovery Manager (RERM) or interim RERM, will assume control l
l of and responsibility for offsite radiological assessment and monitoring activities. On-site and near-site monitoring activities usually continue to be coordinated from the TSC.
The Radiological Monitoring Director (or monitoring team liaison coordinator) vill be l
responsible for connunication with the monitoring teams, the MEML, and provide them with operating instructions. The RERM will be kepf informed of the offsite monitoring teams activities, and coordinate 9
PGandE efforts with the Unified Dose Assessment Center (UDAC) staff.
l DC0182 IVI
.,..,-m.
,__f_
~.
o osaat.O CANYON POWER P:. ANT UNIT NCNS) 1 AND 2 P RB-8 DATE 5/2/84 PAGE 2 0F 49 EMERGENCY OFFSITE RADIOLOGICAL ym ENVIRONMENTAL MONITORING
~
Transfer of control and responsibility for offsite radiological assessment activities will usually be initiated by the EOF staff. The decision to transfer control and respor sibility shall be approved by t
the Site Crnergency Coordinator and the person in charge at the E0F.
TMs shall be done by direct comunication and entered on the radiological status board.
The ERA, at the TSC, will then inform each offsite environmental l
monitoring team and the MEML, by radio, that corrnunications and data will be transmitted to and from the E0F to the Radiological Monitoring Director.
COMMUNIC ATIOi,5 1.
The primary conrnunication links between the TSC, EOF, MEML, and i
field monitoring teams will be by radio comunications on the Health Physics frequency. The field monitoring teams will use hand-held radios. The location and numbers of available radios are listed below:
Location Radio Type Number OSC (Security Building)
H 3
PGandE Service Center (MEML Garage)
H 4
EOF H
2 l
P 1
MEML P
1 l
DER Vehicle P
1 H= Hand-held.
P= Permanent.
g: Field teams should obtain hand-held radios from the OSC or i
MEML. Other locations should be used as a back-up only.
[
l l
a.
For ease of comunication with the radios, the field
(
monitoring teams will be given call names using the International (ICA0) Phonetic Alphabet:
A - Alpha E - Echo I - India l
B - Bravo F - Foxtrot J - Juliett l
C - Charlie G - Golf K - Kilo l
O - Delta H - Hotel L - Lima i
l DC0182 2VI i
3 q
o omm.O CANYON POWER PLANT UMT $$)
1 AND 2 NUMBER EP RS-8 REVISION 4 DATE 5/2/84 PAGE 3 0F 49 EMERGENCY OFFSITE RADIOLOGICAL nu ENVIRONMENTAL MONITORING
\\
b.
Radio Technique
~
OTE: The "T" switert is set o "F" set or j
repeater $ or local.
t I
1)
Hold the radio upright, directly in front of the moath
^
with antenna oriented 90* from direction of receiving station (e.g., EOF).
This normally means the antenna l
is also upright.
h 2)
Before transmitting, make certain that someone eise is not already transmitting on tne frequency.
3)
Af ter pushing transmit butter., wait twc seccnds to allow automatic radic encoding to occur.
4)
Begin all comunications using the following example:
" EOF, this is Alpha team. Jo you read me?"
5)
Close all comunications using the following example:
"This is Alpha team. Over".
2.
Comunications back-up would be by telephone:
$.C,i [y EOF:
! J. ; W '4".g pg;. - e(
,b_
g TSC or Control Room:
G.t ~ ' <
- d. V :' f, 9 '? h l.$ h 4 UDAC:
?
n.W.:
,,.L. e+4 3.
Each monitoring team leader and the MEML shall contact the TSC or EOF under the following conditions:
Prior to beginning the monitoring program, in order to a.
obtain initial instructions.
b.
Upon completion of monitoring at each location.
OR c.
At least once per hour.
MONITORING TEAMS
- I 1.
Cogosition
~
Equipment for a minimum of four teams plus the MEML is a.
DC0182 3v!
o i
1 AND 2 NUMBER EP RB-8 otAsLO CANYON POWER PLANT UNIT %S)
REVISION 4 DATE 5/2/84 PAGE 4 0F 49 EMERGENCY OFFSITE RADIOLOGICAL 7,7 g ENVIRONMENTAL MONITORING available for offsite environmental monitoring. One team is normally designated for on-and near-site monitoring (per Emergency Procedure RB-7 " Emergency On-site Radiological Environment Monitoring).
i b.
Each team will have two menters. One team member will be designatec the team leader.
c.
Teams will be comprised of 1 (one) PGandE C&RP Techniciar. as the team leaaer and 1 (one) additional PGandE Technician and/or 1 (one) SLO County (SLOCO) Environmental Sanitartar..
2.
Day Shift (Week Days) a.
PGandE personnel will be dispatched from DCPP.
b.
One team will be supplied with a hand-held radio and an emergency kit from the site, and initiate monitoring. The other teams will obtain equipment at the MEML Garage.
c.
Mobilization and dispatch on the day shift will take approximately 20 minutes.
3.
Back Shifts (Weekends) a.
Teams notified on a call-out basis will be directed to assemble at the Operational Support Center (Security Building) or the San Luis Obispo Service Center MEML Garage.
l Teams including a SLOCO Environmental Technician will assemble at the MEML Garage.
b.
Mobilization and dispatch on a backshift will take approximately one hour.
4.
The Emergency Liaison Coordinator will transmit the assembl, location to the SLOCO Emergency Organization.
GENERAL INSTRUCTIONS 1.
Locations to Monitor j
a.
Affected Sectors The 360' of the compass have been divided into sixteef 22.5*
l sectors which are identified by the cogass point of their centerline:
1.e., N. NNE. NE ENE E, etc.
In this i
DC0182 4VI
e DWKO CANYON POWER PUWT UNIT NO(S) 1 AND 2 NUMBER EP RB-8 REVISION 4 DATE 5/2/84 PAGE 5 0F 49 i
7,y g EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING procedure, all directions are referenced to true north, so N means true north.
If the wind direction has been reasonably steady, the monitoring program should emphasize the sector immediately downwind plus one adjacent 22.5" sector on either side of the downwind sector.
If the wind direction is changing considerably, the sectors monitored will have to be appropriately increased.
r b.
Jistance Downwind The EERC will use the EARS system or manual overlays as described in EP R8-11 to determine distance affected downwind. Generally, it is best to send at least one tearn as far downwind as appropriate, and then have them work their way back in toward the plant.
c.
Identification of Emergency Monitoring Locations 1)
Monitoring locations used in this procedure are identified in Figure 1. "Onsite Assembly and Monitoring l
Locations" and Figure 2. " Emergency Offsite Monitoring Locations". Table 1. " Description of Emergency Onsite L
Monitoring Locatio'ns", and Table 2. " Description of Emergency Offsite Monitoring Locations" are included for reference.
2)
Coordinate System Each monitoring location is identified by three coordinates: a compass point, a distance in kilometers,andaletterdesignation,(i.e.,NNE,8 i
A).
l The compass point refers to the sector in which the sample was taken.
To help locate the distance from the plant at which the sagle was taken, concentric circles have been drawn on the map at the following distances from the plant: 0.8 km (800 m), 2 km, 4 km, 6 km,10 km,15 km, 20 km, 30 l
l km, etc. This defines segments of a circle which are 22.5" in arc, and either 0.8,1.2, 2 or 5 km deep, l
depending upon the particular location of the tegnent.
The km designation in the identification refers sa the distance of the farthest segment boundary, not the l
l actual downwind distance.
t I
I l
DC0182 5VI i
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..r-'
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-.. * ~..
...: 3 4.'. m....
/,.
-L M.'
..,. :.... / t
.v m
e osasLO CANYON POWER PLANT UNIT %S) 1 AND 2 EP RB-8 DATE 5/2/84 PAGE 6 0F 49 EMERGENCY OFFSITE RADIOLOGICAL 7,7 g ENVIRONMENTAL MONITORING In cases where samples are taken at locations other than those previously labeled, some other identification means must be used. Thus, the following might be typical sample location designations:
(ESE 15, Avila Pcst Office',
(ENE, 20, Corner of Marsh a' u Broad Streets, SLO)
(NNW, 8, Campground at mouth of Islay Creek) 2.
Radiological Precautions N)TE:
In NON-evacuated areas NO PROTECTIVE CLOTHING OR RESPIRATORS shall be worn, a.
Protective clothing should be worn if loose surface contamination levels above unconditional release are expected. The amount of and the need for protective clothing nmst be balanced against other controls (such as leavingthearea). Here are some criteria to be used in determining when and how much protective clothing is worn.
1)
If contamination surveys (smears, direct readings probe held out car window facing down indicate >1000 dpm
/100cm2but<10,000dpm/100cm],theminimum protective clothing is hand and feet protection.
2)
If surveys indicate activity >10,000 dpm/100 cm2, then a minimum of a full set of protective clothing is worn, b.
Respirators should be worn if loose surface contamination levels of >100,000 dpm/200 cm2 is found or an air particulate sample indicated an concentration of 5 x 10 8 vCf/ml. The following rules of thumb can be used to determine the nun 6er of counts per minute (as a function of sample volume) that would give the above concentration.
1)
Using an HP-210 or HP-260 probe, the ratio of cpm to sample volume to give 5 x 10~8 SC1/ml = 500 cpm /ft3 2)
Using an HP-240 probe (window oEen), the ratio of cpm to sample volume to give 5 x 10 a uti/sl = 50 cpm /ft3 For example, if a sample volume of 10 ft3 were taken la 5000 cpm reading above background using an HP-210 probe.wo&id be equivalent to 5 x 10 a vC1/ml.
DC0182 6VI l
1 AND 2 EP RB-8 osasLO CANYON POWER PLANT UNIT NO(S)
DATE 5/2/84 PAGE 7 0F 49 EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING FOT
~E: The presence of radon products can cause erroneous readings. Be sure to count the filter with and without a sheet of paper between it and the probe.
If tha count rate decreases by 50% with the paper, then the rules of thumb needs to be adjusted a corresponding amount.
Team me nbers shall survey themselves, their equipment af ter c.
use and the exterior package of their samples if loose i
surface contamination is found during their surveys.
Contamination control points may be required.
If possitle, unconditional release of all items should be made.
Othenvise, control them as radioactive materiels.
d.
Environmental Sampling Stations l
1)
There are a number of environmental monitoring anc l
sampling stations which are part of the continuing program conducted by the Department of Engineering L
Research. For reference, these stations are showr, in Figure 3. " Location of Departments of Engineering l
Research Environmental Monitoring and Sampling Stations".
l 70TE 1: Field monitoring teams will not collect data from DER monitors unless expressly directed by the Radiolo at the EOF)gical Monitoring Director (located POTE 2: The TLD's are located in a grey plastic container. Opening the container requires an l
1/8-inch Allen wrench which is in the emergency kits.
2)
The Nuclear Regulatory Comission also has posted TLD's in the area..Information may be obtained from the NRC Representative onsite. See Table 4. " Environmental Radiation Monitoring Network Stations - Nuclear Regulatory Comission". for locations of the TLD's.
e.
Dairies l
8ecause the milk pathway is often the limiting pathway. it may be desirable to collect milk samples. The locations of dairies in the DCPP area are described in Table 5.-
" Locations of Selected Dairies".
j i
l DC0182 7VI
1 AND 2 EP RB-8 tHasLO CANYON POWER PLANT UNIT NO(S)
DATE 5/2/84 PAGE 8 0F 49 EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING 2.
Sample Identification and Data Sheets a.
Identification and Retention of Samples Samples or filters which are collected in the field shall be placed in a sealed plastic bag, envelope, or bottle, as appropriate, and identified with a finnly attached label which states the following infonnation:
1)
Date and time of start and end of sample collection.
The time is expressed using the military (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period) standard.
2)
Sampler flow rate (air samples only).
3)
Location of sample.
4)
Name of person who collected the sample. The exterior of the bag shall be surveyed.
If contam1 nation above unconditional release limits are found, decontaminate or place it in another bag. Note contamination levels on label.
All samples and filters shall be taken to the MEML for preliminary field screening.
b.
Field Data Sheets Field data shall be recorded on the Emergency Environmental Monitoring Field Data Sheets (Form 69-9259). Each monitoring team shall maintain a notebook with the data sheets and other pertinent instructions.
The data sheet contains provisions for entering the data from all of the various field monitoring techniques. At any given moni+oring location, only a few of the possible types of measuremerits may actually be performed.
MONITORING PROGRAM An external dose rate measurement shall be taken and an air sasple shall be collected at each offsite monitoring location.
IftheTASC-4continuousenvironmentalmonitorsareinanaffecked sector, they shall be read. The TASC-4 are located at the Avile Beach Gate (ESE.10, 8) and the Los Osos fire station (N.15. C).
i DC0182 8VI
~
1 AND 2 EP RB-8 dmo CANYON POWER PLANT UNIT NCHS)
DATE 5/2/84 PAGE 9 0F 49 EMERGENCY OFFSITE RADIOLOGICAL i
ENVIR0hMENTAL MONITORING j
If the Pressurized Ion Chambers (PICS) are located in an affected sector, they shall be read.
Plc locations are described in Table 6.
Collection of any other types of samples (i.e., ground deposition measurements, vegetation, soil, water or milk samples) will be at the direction of the Emergency Evaluations and Recovery Coordinator or tne Radiological Monitoring Director.
1.
External Dose Rate and/or Count Rate Measurements i
a.
Equipment Required 1)
Any of the following instru:nents can be used fcr external dose rate measurements:
a)
Rad Owl.
b)
Victoreen Radgun, c)
HPI-1010 d)
R0-2 For measuring an external count rate, use an Eberline E-140/N survey meter equipped with either an HP-240 standard GM probe, HP-260 pancake GM probe, or an HP-210 shielded GM probe.
b.
Procedure i
1)
Dose or Count Rate Measurements a)
Make a dose rate and/or count rate measurement with the detector held about three feet off the i
l ground (i.e., approximately at waist level). Scan in a 360* direction.
If the detector is so i
equipped, take the data both window (or shield) on l
and off.
g:
When using(GM window down) and shield down the HP-210 probe, take both shield up (GMwindowup) readings. These readings may be required later to account for' sky shine. Se sure to note the correct Peading l
underthecorrectheadinfup)ntheData so Sheet-cpm (shieldoff
]orcpm (shieldon(down)].
I I
DC0182 9VI i
m.
...----,...-e.,
.-n-,
r-
ocaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EP R8-8 DATE 5/2/84 PAGE 10 0F 49 EMERGENCY OFFSITE RADICLOGICAL y,7 g ENVIRONMENTAL MONITORING b)
Identify the type of instrument (or probe) used, time survey was started, and calibration due date of the instrument on Section 1 of the Field Data Sheet.
c)
Using the highest value obtained during the scan, calculate the net dose or count rate values by subtracting the appropriate background values given in Table 7.
d)
Report both the open window (or shield) on and off values and the type of instrument used, to the Emergency Evaluations and Recovery Coordinator (EERC), or Radiological Monitoring Director (RMD).
2)
Integral Dese The Rad Owl and the HPI-1010 have the capability for dose integration if desired.
If an integrated measurement is made, the data can be entered in Section 1.c. of the Field Data Sheet.
Integral measurements with the Rad Owl should be made with the window open.
Report the integral dose and the time period over which it was collected to the EERC or RMD,'as appropriate.
2.
Collection of Air Samples a.
Equipment Required 1)
One of the following air samplers, equipped with sample head for two-inch filters:
a)
RADECO Model HD-288 (120V AC-powered).
b)
RADECO Model H-8098 (12V DC-powered, with battery).
l l
c)
RADECO Model H-809C (12V DC-powered, without battery).
I 2)
Two-inch diameter absolute particulate filter paper.
3)
Coin envelope for retention of filter.
~ [_
l l
t l
DC0182 10VI l
1 AND 2 EP RB-8 Dt,WI.O CANYON POWER PUWT UNIT NCKS)
DATE 5/2/84 PAGE 11 0F 49 EMERGENCY OFFSITE RADIOLOGICAL t
ENVIRONMENTAL MONITORING 4)
HI-Q 2-1"-diameter characoal cartridge or AgZ cartridge, l
r 5)
Plastic sandwich bag for retention of cartridge.
6)
Gummed or other label for labeling cartridge container.
7)
Wristwatch or stopwatch.
b.
Procedure i
l 1)
Assemble the filter and haloge cartridge in the sampling head as shown in Figure 5.
Draw an arrow or, the cartridge to indicate the direction of flow.
2)
Place the filter head on the sampler.
l l
3)
For an HD-288, proceed as follows:
l a)
Plug in the sampler, turn on the power, and simultaneously start a stopwatch (or reset the timer en the sampler itself, if a sampling time of several hours is contemplated).
b)
Quickly adjust the flow rate to the desired value (typically 2 cfm).
l t
4)
For an H-809C, proceed as follows:
a)
Attach the sampler to the car battery by attaching the red cable to the positive battery teminal and
~
the bla:k cable to a chassis ground.
g: Close the hood and place the air sampler on top of it to avoid engine fan turbulence, b)
Turn the vehicle engine on. Start the sampler.
Note the airflow. Do not attempt to adjust the airflow by turning the setscrew on the top of the flowmeter.
5)
For an H-8098, proceed as follows:
a)
Ifanautomobileisavailable,putthetoggke switch on the black battery pack in EXT. hnect the red cable to the positive terminal of the I
I DC0182 11VI
1 AND 2 EP RB-8 Osaat.O CANYON POWER Pt. ANT UNIT NO(S)
DATE 5/2/84 PAGE 12 0F 49 EMERGENCY OFFSITE RADIOLOGICAL i
ENVIRONMENTAL MONITORING i
battery and the black cable to a chassis ground.
E: Close the hood and place the air sampler on top of it to avoid engine fan turbulence, b)
If an automobile is not available, put the toggle i
switch on the black battery pack in INT.
ff>TE: The unit will not run using 12DV AC, so do not sample while charging.
c)
Dial in the appropriate sampling time, usin5 the appropriate combination of toggle switches.
d) ' Turn on vehicle engine. Start the sampler. Note the airflow. - Do not attempt to adjust the airflow by turning the setscrew on the top of the flowmeter.
~'
g: The maximum flow rate is si cfm when the l
unit is using its own battery.
6)
Periodically check the flow indicators to verify that the flow rate is being maintained.
If the flow rate changes significantly during sample collection, note the value at the end of the sample period and detemine the average value of the flow rate. This average value i
should be used to detemine the size of the sample collected.
7)
Allow the sampler to run until at least 10 f t3 (but 3
preferably 30-50 ft ) is collected. The greater the volume sampled, the better.
8)
Stop the vehicle engine. Stop the sampler and remove the filter head.
9)
Make the halogen and particulate measurements discussed in steps 3 and 4 below, if desired.
- 10) Label the envelope and then place the particulate i
filter in the coin envelope.
- 11) Place the iodine cartridge in a sandwich bag andtlabel i
the bag.
l d
DC0182 12VI
osaaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-8 REVISION 4 DATE 5/2/84 PAGE 13 0F 49 EMERGENCY OFFSITE RADIOLOGICAL 7q ENVIRONMENTAL MONITORING
- 12) Enter the collection data in Section 2 of the Field Data Sheet.
3.
Determination of Gross Iodine (Field Technique) a.
Equipment Required -
1)
Eberline E-140/N survey neter equipped with either an HP-240/270 standard GM probe, an HP-260 pancake GM probe, or an HP-210 shielded pan:ake GM probe. The HP-210 probe is preferred.
2)
Cylinder of dry air equipped with regulator.
3)
Plastic bag'.
4)
Forceps or tweezers b.
Procedure..
1)
Depending on the air samples used, remove the cartridge from the air sampler head (HD-28) or remove sampler head from sampler (H-809).
2)
Insert the cartridge (or sample head) into the adapter sample hvad shown on Figure 6.
3)
Open the main valve on the air cylinder and note the cylinder pressure gauge.
It should normally read about 1800 psi. Replace the cylinder if it reads <300 psi.
Close the main valve. Open the flow control ~ valve and adjust the regulator so that the delivery pressure gauge reads 5 psi. C1cse the flow control valve.
4)
Attach the air cylinder / regulator to the adapter and sample as shown in Figure 6.
Open the main valve and flow control valve to allow air to ble through the cartridge in the reverse direction. Let the purge continue until the cylinder pressure gauge drops 200 psi. The technique removes noble gases from the halogen cartridge.
5)
Record the standard background count rate for the GM probe used for counting the cartridge using Table-7 onto Section 4 of the Field Data Sheet.
t DC0182 13VI
EP RB-8 i
DansLO CANYON POWER PLANT UNIT NO(S)
DATE 5/2/84 PAGE 14 0F 49 EMERGENCY OFFSITE RADIO'.0GICAL N
ENVIRONMENTAL MONITORING 6)
Remove the cartridge and place the probe within one-half inch of the upstream side of the cartridge.
See Figure 7.
Measure and then record the count rate.
When using the HP-240/270 probe, the window must open, The detector is face down when the HP-210 or HP-260 is used.
7)
Record the count rate in Section 4 of the Field Data Sheet. Note time sample was started and calibration due date of the instrument.
l 8)
Bag and label the cartridge. Surve,. the exterior of the bag. Decontaminate or put it into another bag if contamination levels above uncondition release limits I
are found.
9)
Calculate gross iodine concentration from the following expression:
(1.59 x 10 11)
(CRnet) l 8 II*I "
(c2) (E )
(V) g where:
CR
= net cpm on cartridge net c2 = probe efficiency from Table 8 E = cartridge collection efficiency, assumed l
C to be 0.80 3
V=volumeofairbornesample(ft)
- 10) Report gross iodine concentration, probe used, and volume of sample to the Emergency Evaluations and l
Recovery Coordinator or the Radiological Monitoring
- Director, i
i 4.
Determination of Gross Particulate (Field Technique) a.
Equipment Required 1)
Eberline E-140/N survey meter equipped with either, an l
HP-240/270 standard GM probe, an HP-260 pancake mi probe, or an HP-210 shielded pancake GM probe.
i
[
i l
i DC0182 14VI l
t t
Dueto CmvoN PowEm Pwn umT ms) 1 AND 2 NUMBER EP RB-8 REVISION 4 DATE 5/2/84 PAGE 15 0F 49 EMERGENCY OFFSITE RADIOLOGICAL 7,7tg~
ENVIRONMENTAL MONITORING
~
2)
Coin envelope.
3)
Forceps or tweezers, b.
Procedure 1)
Remove the filter from the air sampler head.
2)
Record the standard background taken from Table 7 for the probe being used in the appropriate location ir.
Section 3 of the Field Data Sheet. Wher using the HP-210 or HP-260 probe, the reading is taken with the detector faced down. The window must be open wher using the HP-240/270 probe.
3)
Place the probe (window open using the HP-240/270 probe, face down using HP-210 probe) within one-half inch to the upstream side of the filter in an analagous manner to the counting of halogen cartridges shown in Figure 7.
Filters should be handled with forceps (or tweezers) and the probe should not touch the filter, in order to avoid contamination of the proce.
4)
Record the count rate in Section 3 of the Field Data Sheet. Note time sample was started and calibration due date of the instrument.
l 5)
Label the envelope and place the filter in the coin l
envelope, using the forceps (or tweezers). Place the probe within one-half inch over the envelope.
If the count rate now decreases, then radon products should be suspected. Note this on the Field Data Sheet.
6)
Determine the net count rate and calculate the gross particulate activity from the expression:
(1.59x10'11) (CR * )
uti/mi =
g,3) gg ;
(yy f
N DC0182 15VI
1 AND 2 EP RB-8 om0 CANYON POWER PLANT UNIT AS)
DATE 5/2/84 PAGE 16 0F 49 EMERGENCY OFFSITE RADIOLOGICAL 7,7 g ENVIRONMENTAL MONITORING where:
CR
= net cpm on filter 4
net c3 = probe efficiency from Table 9 Ef = cartridge collection efficiency, assumed to be 0.90 i
3 V = volume of airborne sample (ft )
i i
7)
Report the activity, type of probe used, and volume of sample, to the Emergency Evaluations and Recovery Coordinator or Radiological Monitoring Director.
5.
Soil and Vegetation Sampling a.
Equipment Required 1)
Trowel.
2)
Grass cutters or knife.
3) 18" x 24" plastic bags.
4)
Masking tape.
5)
Labels.
6)
Eberline E-140/N survey meter with HP-240/270 standard GM probe.
7)
Protective clothing as determined by surveys.
b.
Procedure 1)
Vegetation Sampling and Counting a)
Cut the vegetation from the approximately 1 m2 of ground; the aim being to collect approximately one pound. Cut the vegetation at a height of I-2 cm from base of vegetation to approximate what a grazing animal would consume. Do not contaminate the sample with dirt.
b)
Place the vegetation in the plastic bag, top end c
l first. Slowly compress the air out of the bag and DC0182 16VI
1 e
l DMLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EP RB-8 DATE 5/2/84 j
PAGE 17 0F 4g 1
EMERGENCY OFFSITE RADIOLOGICAL 7,7 g ENVIRONMENTAL MONITORING
~
seal it with tape. One pound of material will i
normally fill the bag about half full.
CAUTION: DO NOT PLAE BODY OVER BAG OPENING WrilLE COPPRESSING IT'S CONTURS.
c)
Label the bag with the following information 1)
Location of sample 2)
Date and time of sanple. The time is expressed using the military (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period) standaro.
3)
Name of person who took sample d)
Using Table /, pick the standard background for the HP-240/270 probe and record it on Section 7 of the Field Data Sheet, e)
Flatten the bag and lay the probe (window open) on the center of the bag.
f)
Fold the bag over the probe and note the reading.
Record the reading on the field data sheet along with time of survey and instrument calibration due l
data.
~
g)
The activity level in uCi/gm can be obtained from l
the following expression:
uCi/gm = 2.5 x 10~5 x CRest where:
CR
= net epm on a standard GM tube net (HP-240/270) i h)
Survey the exterior of the bag.
If contamination levels above unconditional release limits are found, decontaminate or place it into another bag.
i Notethecontaminationlevelsonthelabel.L 1)
Report the type of vegetation samples and the c
activity level to the Emergency Evaluations and i
DC0182 17VI
1 AND 2 EP RB-8 DeABLO CANYON POWER PUWT UNIT NO(S)
DATE 5/2/84 PAGE 18 0F 49 EMERGENCY OFFSITE RA010 LOGICAL ENVIRONMENTAL MONITORING Recovery Coordinator or the Radiological Monitoring Director.
2)
Soil Sampling a)
Sample the soil from about a m2 area.
Remove only the top surface (to a depth of = 1" or less) using the trowel. Stay upwind and wear appropriate protective clothing when scraping. See GENERAL INSTRUCTIONS.
b)
Place the sample in a bag, seal, and label.
c)
No field counting of soil samples is reovired.
The samples are taken for follow-up analysis only.
Scan the bag to detennine if there is a high count rate (>1,000 cpm). Survey the exterior of the bag.
If contamination is found above unconditional release limits, decontaminate or place another bag cver it. Record any high count rates on Section 10 of the Field Data Sheet.
6.
Liquid Sampling and Counting a.
Equipment Required 1)
Sample bottle (1 liter) 2)
Labels.
i 3)
Eberline E-140/N survey meter equipped with HP-240/270 standard GM probe.
4)
Sheet plastic or plastic bag.
S)
Protective clothing as determined by surveys b.
Procedure 1)
Wrap the GM probe and cord (window open) in thin plastic to protect it against liquid damage and contamination.
2)
Innerse the probe in as large a body of liquid at-is available (reservoir, cattle trough,10-gallon afik I
can, etc.) to obtain the gross open window reading.
i DC0182 18VI
___m-,.__
4 otAato CANYcW POWER PLANT UNIT NCMS) 1 AND 2 EP RB-8 i
DATE 5/2/84 i
PAGE 19 0F 49 EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING l
Enter the reading in Section 9 of the Field Data Sheet along with the time of survey and calibration due date of the instrument.
3)
Use 60 cpm as a background count rate to deterinine the net count rate.
4)
Report the type of sample, volume of sample counted, and net count rate to tne Emergency Evaluations anc Recovery Coordinator or Radiological Monitoring Director.
5)
Collect and label a 1-liter sample and retain for later analysis.
If readings >200 cpm were obtainea during probe irtrnersion, place the 1-liter sample in a plastic l
bag and then tape the opening. Survey the exterior of the bag.
If contamination levels above unconditional release limits are found, decontaminate or place
- .other bag over it.
l 6)
Survey the probe after it has been removed from it's l
plastic bag. Decontaminate if practical. Otherwise l
treat it as radioactive material.
7.
Ground Surveys a.
Equipment Required Eber11ne E-140/N survey meter equipped with either an HP-240/270 standard GM probe and HP-260 pancake GM probe, or an HP-210 shielded pancake GM probe. The HP-210 is the preferred detector because its shield reduces the influence of sky shine.
Protective clothing as required by surveys. See GENERAL INSTRUCTIONS.
b.
Procedure 1)
Hold the GM probe, window open using HP-240/270 probe (shield up when using HP-210 probe) not more than two inches above the ground, and measure the count rate.
The following precautions should be taken when miiking this measurement.
e t
DC0182 19VI
1 AND 2 EP RB-8 DiaaLo CANYON POWER M. ANT UNIT NO(S)
DATE 5/2/84 PAGE 20 0F 4g EMERGENCY OFFSITE RADIOLOGICAL ym ENVIRONMENTAL MONITORING t
l a)
Make the measurement over short grass on undisturbed land (connon grazing, permanent pasture),
b)
Make the measurement at least 20 yards from any building, road, railway, bridge, or heaps of material such as gravel, rubble, or road-cut.
These all contain varying amounts of natural uranium and thorium.
c)
Haystacks or silos should be avoided because they may contain in an concentrated form the total deposition on grass which originally covered a large area. Trees and hedges also act as collectors of fallout which is washed out to a variable extent by rain.
In an emergent /, they may trap large amounts of airborne particulate and give a falsely high reading, d)
Care must be taken to avoid any contamination of the instrument.
If necessary, wrap the instrument (including probe) in a plastic bag prior to starting survey.
2)
Identify the type of probe used ano enter the data in Section 6 of the Field Data Sheet.
Include the time the survey was started and the calibration due date of the instrument.
3)
Calculate the net count rate value by subtracting the background value given in Table 7.
NOTE 1:
It is not possible to correct the background values for sky shine if an HP-240/270 or HP-260 is being used. Significant sky shine will invalidate ground surveys taken with these probes.
l NDTE 2: If an HP-210 is being used, the effect of sky shine can be estimated. To do this, take a second measurement with the GM window facing the sky (shield down reading). Then add 1/10 of this figure to the normal backgroundifrom Table 7 and use this sum as the e
c DC0182 20VI
a O
1 AND 2 EP RB-8 DensLO CANYON POWER PLANT UMT NO(S)
DATE 5/2/84 PAGE 21 0F 49 EMERGENCY OFFSITE RADIOLOGICAL W
ENVIRONMENTAL MONITORING
~
corrected background. That is:
(OC 9 Corrected = (Bckg) Table 7 +0.10(CPM) Sky where:
(Bckg) Corrected = background corrected for sky shine (con)
(CPM) sky = gross epm with detector window facing up sed 4)
Calculate the ground deposition frorr the following equation:
Ground Deposition (uti/m2) = c3 x CRNET where:
3 = probe efficiency factor given in Table 10 c
CR net count rate (in cpm) from ground survey
=
net 5)
Report location of measurement, ground deposition, and the type of instrument used to the Emergency Evaluations and Recovery Coordinator or Radiological Monitoring Director.
8.
Determination of Smearable Contamination a.
Equipment Required 1)
Two-inch diameter filters with holders.
2)
Eber11ne E-140/N survey meter equipped with an i
HP-210/270 Standard Probe, an HP-260 pancake probe, or an HP-210 shielded pancake GM probe.
L b.
Procedure 1)
Select a representative smooth surface to smear-test.
Examples are tops of cars, store windows or sills, and walls of buildings.
2)
Wipe the area using a unifonn, moderate fingertig pressure. Estimate the total area smeared, in sgu.are feet or fraction thereof.
l DC0182 21VI m-. rvw--
O s
i
=
1 AND 2 NUPSER EP RB-8 DM9LO CANYON POWER PLANT UNIT NQS)
REVISION 4 OATE 5/2/84 PAGE 22 0F 4g EMERGENCY OFFSITE RADIOLOGICAL l
ENVIRONMENTAL MONITORING 3)- Take c. background count rate measurement and then a i
count'of the filter. Eeter the data in Section 8 of the field Data Sheet along with the time of the survey and the calibration due date of the instrument.
i 4)
Nt the filter into a labeled holder and save it for j
later anylysis in the counting room.
5)
Calculate the smearable contamination as follows:
(0.11)(CRnet) dpm/cm2. _
a (c3)A where:
l net cpm on filter l
3 CR
=
net l
c3 = probe efficiency factor from Table 9 l
A = area smesred. in square feet 1
'6)
Repon the type of surface smeared instrument used, and tht-smearable contamination level to the Emergency Evaluations and Recovery Coordinator or Radiological
,5 Monitoring Director.
x 9
Ho.1tofen.tieTACCt4-ij7(i 'For perpedes of emergency monitoring standardize the
~ Acaley-tiser of using a ten-second count.
~
,0n the NT-29 timer, set ten-seconds.
az
-w s
's
));..The top thuntmheel is set at 1; the middle and lower ences are s.it at 0 (i.e. a reading of 1.00).
a s.'
4 p
'2). 'The MIN-$EC toggle switch is set in SEC.
s
'~
3)
The RANGT, NLTIPLIFR is se; at X10.
b.
Ca the R012 scaler, set the Tf5T/ SCALER toggle switch to 3 CALF.R.s c.
Press the STOP pushbutton, then press the RESET pushbutton
?
(r.he'RCSET pushbutton thwld never be depressed while counts
(
x s
.s..
s 4
s DC0182 22VI
^~
y-
.,[
P x.A.
o s
AND 2 NUMBER EP RB-8 DtAal O CANYON POWER Pt. ANT UNIT NO(S)
REVISION 4 DATE 5/2/84 PAGE 23 0F 4g EMERGENCY OFFSITE RADIOLOGICAL I' M ENVIRONMENTAL MONITORING are being applied to the register; first stop the court by pressing the STOP pushbutton).
d.
Set the PRESET rotary switch to the OFF position.
e.
Press the START but' ton to start a count.
f.
The scaler will begin to accumulate counts and will continue doing so until the preset time period has elapsed. At this point, counting will automatically stop.
g.
The dose rate is determined from the following expression:
DR (uR/hr) =
(t'otal counts)
(counting time in seconds)
For a ten-second count, this becomes:
DR (uR/hr) = itotal counts) 10 h.
Report dose rate to the Emergency Evaluations and Recovery Coordinator or Radiological Monitoring Director.
- 10. "How to read the Pressurized Ion Chamber (PIC)"
l a.
Equipnent l
1)
High Security Pin Tumbler key (in Emergency Kit)
I 2)
Screwdriver with 0.25-inch blade or equivalent b.
Using the screwdriver and key (as applicable), open the door and read the liquid crystal digital display.
l g: The selector switch must be in the " READ" position.
Also some PIC's have a window to view the display so the unit need not be opened.
l c.
Look at the strip chart. Onetraceonit(usuallya straight line) matches one of the markings immediately below the chart. This indicates the range. The second trage will nomally fluctuate. This trace indicates the actual fose rate.
It should correspond with that shown on the digttal display. Using a felt-tip type pen or a pencil, indicate l
DC0182 23VI
osasLO CANYON POWER PL#tt UMT AS) 1 AND.2 EP RB-8 DATE 5/2/84 PAGE 24 0F 49 EMERGENCY OFFSITE RADIOLOGICAL
~ ENVIRONMENTAL MONITORING and write the date, time and initials of person checking the readir.g on the chart.
If the two readings do not agree, use the higher reading.
d.
.Close the cover. Record data on Field Data Sheet. Report the reading.
- 11. Recordkeeping All records generated by the utilization of this procedure for an exercise or emergency shall be forwarded the next working day to the Senior Emergency Planner for review and retention.
a.
Records generated f m exercises will be categorized as non
., permanent and' retained for a minimum of five years, b.
Records generated from actual emergency events will be categori:ed as lifetime and placed into lifetime storage in accordance with procedure " Requirements for Retention and Extended Storage of Operation Phase Activity Records, (AP-E-1-51)."
~
FIGURES 1.
Onsite assembly and Monitoring Locations.
2.
Emergency Offsite Monitoring Locations.
3.
Locations of DER Onsite Environnantal Sampling and Monitoring Locations.
4.
Locations of DER Offsite Environmentc1 Sampling and' Monitoring Locations.
5.
Exploded View of H& logen Cartridge and Particulate Fil,ter in Sampling Head.
6.
Method for Blowing Noble Gases from Halogen Cartridge.
7.
Position.of GM Tube and Cartridge for Gross Iodine Determination.
TABLES
~ ~
1.
Description of Emergency Onsite Monitoring Locations.
i DC0182 24VI
DIASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EP RB-8 DATE 5/2/B4 PAGE 25 0F 49 EMERGENCY OFFSITE RADIOLOGICAL
'"1" ENVIRONMENTAL MONITORING 2.
Description of Emergency Offsite Monitoring Locations.
~
3.
DER Environmental Sampling Locations.
4.
Environmental Radiation Monitoring Network Station of the NRC.
5.
Locatior.s of Selec.ed Dairies.
6.
PIC Locations.
7.
Background Data for 8/3 Dose and/or Cour.t Rate Measuremer.:s.
8.
GM Probe Efficiency Factors for Iodine Determinations.
9.
GM Probe Efficiency Factors for Particulate Determinatf ors.
- 10. GM Probe Efficiency Factors for Ground Surveys.
ATTACHMENTS 1.
Form 69-9259, " Emergency Environmental Monitoring Field Data Sheet".
t.
DC0182 25VI
j l
i
'1 AND ?'
lueER EP R8-8 i
piaaLO CANYON POWER PLANT UMT NCNS)
REVISION 4 l
DATE 5/2/84 PAGE 26 0F 49 EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING i
i FIGURE 1 i
ONSITE ASSEMBLY IN!n G TTORING L0tt.TIONS i
,6 s
tg6tetTT
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a 1 AND 2 EP RB-8 otAaLO CANYON POWER PLANT UNIT NCNS)
DATE 5/2/84 PAGE 27 0F 49 EMERGENCY OFFSITE RADIOLOGICAL I' M ENVIRONMENTAL MONITORING
\\
1 l
FIGURE 2 i
EMERGENCY OFFSITE MONITORING LOCATIONS l
= '
- ,1];,
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1 AND 2 HUMBER EP RB-8 DWGLO CANYON POWER Pl. ANT UpmT %3)
REVISION 4 DATE 5/2/84 PAGE 28 0F 49 EMERGENCY OFFSITE RADIOLOGICAL 7"
ENVIRONMENTAL '9NITORING
+
FIGURE 3 LOCATIONS OF DEPARTMENT OF ENGINEERING RESEARCH'S ON5ITE ENVIRONMENTAL 5AMPLING AND MONITORING STATIONS l
ff
- * *. r--
P d,
3:aar-
- w. A,
gg, is e - ms
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l
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{
l
.. -v saca up LEGEND Nf A DOSIMETRY STATION i
5 AIR PARTICULATE STATION l
- REAL TIME RADIATION MONITORS
~ :
I i
i DC0182 28VI l
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l l
I
(
l L
otAaLO CANYON POWER PLANT UNIT AS) 1 AND 2 EP RS-8
(
DATE 5/2/84 1
PAGE 29 0F 49 i
EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING
{
1 gj v.
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FIGURE 4
-~
Locations of Department of Engine (ring su en Research's Offsite Environmental 9
= =,
Sampling and Monitoring Locations
=
S i
Leoend SC8k'n M'ws i. Air Particulate Station Q 1 2 3 i A Dosimetry Station DC0182 29VI L..
. ~
~~
~
" "" ~
~
i 1 AllD 2 EP RB-8 DansLO CANYON POWER PLANT LANT NO(S)
DATE 5/2/84 PAGE 30 0F 49 EMERGENCY 0FFSITE RADIOLOGICAL ENVIR0f0 ENTAL PONITORING i
~
FIGURE 5 EXPLODED VIEW NN CARTRIDGE AND 5
l PART]CULATE FILTLR IN 5ARPLING HEAD j
i Screen Side with l
backing l
g il llIl 11 la 11 li li 4-E
~
i L
n
- I
~
Draw arrow on cartridge to indicate direction of flow
~.--
I DC0182 30VI
j I
otAato CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-8 REVISION 4 l
DATE 5/2/84 PAGE 31 0F 49 l
EMERGENCY OFFSITE RADIOLOGICAL I'
- ENVIRONMENTAL MONITORING FIGURE 6 i
METHOD FOR BLOWING NOBLE GA5ES FROM HALOGEN CARTRIDGE l
l v
i Cylinder Pressure Gauge i
i Main Delivery Pressure Valve Gauge Adapter Sa le hen Flow Control se y
v I
8lp
. G r-1 c:o=a i
t_ _.
1 i
ie i
C Std.
o
^
f Rubber 1
Hose I
Regulator Air l
Cylinder i
i i
+
l i
I I
h
~ :
d' L
r DC0182 31VI
4 i
1 4
i i
1 AND 2 NUMBER EP RB-8
)
e m Pewsn w w ms)
REVISION 4 DATE 5/2/84 i
PAGE 32 0F 49 EMERGENCY OFFSITE RADIOLOGICAL m'
ENVIRONMENTAL MONITORING i
FIGURE 7 POSITION OF N D CARTRIDGE FOR i
GROSS 10 DINE DETLRMINATION i
I I
1 i
i i
/
r 1
.OOOOO i
i I
l I
h HP-240 MP-ZiU rode (shown)or l
Cartridge HP-260 l
l I
l Y
I l
l I
J i
i l
DC0182 32VI l
l
N e-i i
i 1 AND 2 EP RB-8 OiAst.O CANYON POWER PLANT UNIT NCHS)
OATE 5/2/84~
PAGE 33 0F 49 i
EMERGENCY OFFSITE' RADIOLOGICAL I' M l
ENVIRONMENTAL MONITORING l.
r l^
l j
TABLE 1 DESCRIFTION OF EMERGENCY ONSITE MONITORING LOCATIONS r
Straight Line l
Distance From AC Power Coordinate Plant (Meters)
Description Available N,A 300 South side of road No l
i l
h,NE,A 700 In front of.wooder.
No water tank I
hE,A 420 Adjacent to east Yes reservoi r i
l NE,B 800 North side next to No
[
l road, adjacent to gulley l
l ENE,A 700 South side of switch-No yard at fence i
SE C 700 Air sampler-behind Yes l
north side of GC l
warenouse SE.B 800 Front of GC warehouse Yes SE,A 800 40 feet off the main No i
road on the west side of road SSE, A 700 Adjacent to guard Yes shack on bluff SSE B 700 Adjacent to culvert No on west side of dirt road SSE C 700 West of sandblasting No area 5,A On breakwater
- ;No C
DC0182 33VI
t 1 AND 2 P RB-8 oinsLO CAMON POWER M.MT UNIT NO(S)
DATE 5/2/84 PAGE 34 0F 49 i
EMERGENCY 0FFSITE RADIOLOGICAL ENVIR0 MENTAL MONITORING TABLE 1 (Continued)
Straight Line I
Distance From AC Power Coordinate Plant (Meters)
Description Available 5,8 On breakwater No SSW,A 400 West of met tower -
No
(
requires key for gate - not accessible by i
vehicle l
On breakwater No I
SSW,B i
SSW C On breakwater No SW,A 500 West of met tower-Yes requires key for gate - not accessible by i
vehicle WNW.A 500 Near gulley on south No side - requires - 53 i
- key for gate l
WW B 600 40 feet in front No gate - requires - 53
- key WNW C 600 North side of road No I
in clearing-m y have plant growth i
W,A 600 North side of road No I
in clearing-m y have plant growth
{
W,8 600 Northwest side of No dirt road l
W,C 800 At gate on road leading
~ ' No to north road 7
NNW.A 800 30 feet north of No I
steps leading to pond 1
DC0182 34VI 1
DiasLO CANYON POWER PLANT UNIT NCNS) 1 AND 2 EP RB-8 DATE 5/2/84 PAGE 35 0F 49 EMERGENCY OFFSITE RADIOLOGICAL 7,7 2 ENVIRONMENTAL MONITORING TABLE 2
~
DESCRICTION OF EMERGENCY OFF-SITE HONITORING LOCATIONS Straight Line r
i Distance From.
AC Power i
Coordir. ate Plant (KM)
Descriptione Available N,10,A 9.8 West of Montana de Oro No State Park sign (0.6 miles SW of Rodman Drive on Pecho Road. Gooc radio at path off road south of State Park sigr..
Sign on path reads "No Vehicles".
N,15,A 10.0 End of Alamo Drive in Yes!
Cabrillo Estates.
(Turn off Pecho Road at Rodman and go to the top of the hill. Turn right onto Alamo and follow it to the end). Good radio.
Phone available.
N,15,B 11.6 Sunset Terrace Golf Course Yes2 at Clubhouse. Good radio at west end of Howard Drive or on road running north of the golf course.
N,15,C 11.3 Baywood Park Fire Station Yes (Turn south off of Los Osos t
Road onto Bayview Heights l
Drive. Has a TASC-4. DER's monitoring Station 10 is located at Sunnyside School next door). Good radio.
Phone available.
N,20,A 18.0 Morro Bay Power Plant.
Yes DER's monitoring Station 9 is located here. Good radio. Phone available.
- 7 C
DC0182 35VI
1 AND 2 EP RS-8 m w w es)
DATE 5/2/84 PAGE 36 0F 49 EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING TABLE 2 (Continued)
Straight Line Distance From AC Power Coordinate Plant (KM)
Description Available NNE.15,A 11.3 Intersection of Los Osos No Valley Road and Clark Valley Road (under PG&E transmissionlines).
Good radio.
NNE,15,B 12.9 Los Osos Jr. High School ho on South Bay Boulevard in the playing field.
Good radio.
NNE,20,A 17.6 0.2 miles north along No San Bernardo Creek Road is on the northeast side of Highway 1.
Good radio.
NE 15,A 10.6 Intersection of Los Osos No Valley Road and Turri Road. DER's monitoring Station 11 is located nearby. Good radio at intersection.
NE.20,A 17.4 Sheriff's headquarters.
Yes (EOF) Turn south on Highway 1 at sign indicating Sheriff's Operational Center. Good Radio. Phone available.
NE.20,8 19.2 PG&E substation near Men's Yes Colony, adjacent to northeast side of Highway 1.
Good Radio. Phone available.
i
?'
i DC0182 36VI
e i
i 1 AND 2 EP RB-8 l
otAaLO CANYON POWER Pt. ANT UNIT NO(S)
DATE 5/2/84 l
PAGE 37 0F 4g EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING l
}
~
TABLE 2 (Continued) l Straight Line l
Distance From AC Power
(
Coordinate Plant (KM)
Description Available l
ENE,8,A 9.0 See Canyon Road, 4.2 Yes!
miles up from Sar Luis Bay Drive intersection.
Good radio.
Telephone available.
Rattlesnake hazarc.
ENE,20,A 14.8 Laguna Jr. High School Yes3 I
at intersection of Los Osos Road and Perfumo f
Canyon Road. Good radio.
ENE.20,8 16.0 Fire station at inter-Yes of Los Osos Valley and l
l Madonna Roads. Good l
radio.
l ENE 20,C 18.6 PG&E Information Zone 1 Yes
- substation at corner of r
Walker and Pacific Streets.
DER's Station 12 is also located here. Good radio.
ENE.20,D 15.6 Corner of Foothill Yes!
Boulevard and O' Conner Way. Good radio.
ENE 20,E 15.8 Yancy's Restaurant Yes2 (fonnerly Hob Nob) parking lot. Good radio.
l E.15, A 14.5 PG8E Information Center.
Yes Good radio.
i.
E.15,B 13.4 Bellevue-Sante Fe School.
Yes" Fair Radio.
t i
DC0182 37VI
s 1 AND 2 EP RB-8 osaaLo cAmoN POWER M.MT UMT NCNS)
DATE 5/2/84 PAGE 38 0F 4 9 ',
EMERGENCY.0FFSITE RADIOLOGICAL N
ENVIRONMENTAL MONITORING TABLE 2 (Continued)
Straight Line Distance From AC Power Coordinate Plant (KM)
Description Available E,15,C 11.3 See Canyon Road, 1.7 Yesi i
miles up from San Luis Bay Drive intersection.
l Survey at intersection of See Canyon Road and l
Davis Canyon Road. Good l
radio.
E,25,A 20.2 SLO County Airport. The Yes field on the right of the road to the parking lot. Good radio.
l i
E 25..B 21.5 SLO Country Club. East Yes2 side of parking lot in the fairway. Good radio.
l ESE.4 A 2.6 Turnout on access road, No i
1.6 miles from Security I
Building. Marked with l
red / white fence post.
Radio near plant or near location ESE 10,A ESE.6,A 4.5 Turnout on access road No 2.8 miles from Security Building. Marked with red / white fence post.
6 Radio near plant or near location ESE 10,A.
i 5
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I DC0182 38VI a
~
7
I s
1 AND 2 EP R8-8 DansLO CANYON POWER PLANT UNIT NO(S)
DATE 5/2/84 PAGE 39 0F 49 EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING TABLE 2 (Continueo)
Straight Line Distance From AC Power l
Coordinate Plant (KM)
Description Available ESE 8,A 6.9 Gate next to shack at No road to ruins, 4.3 miles from Security Building along access road.
Marked with red / white fence post. DER station 16 is near here. Radio near plant or near location ESE.10,A ESE,10,A 9.6 Top of San Luis Hills.
No Gate at 6.2 miles from the Security Building.
Fair radio.
ESE,10,8 10.0 Port San Luis Gate.
Yes TASC-4 and DER's Station 27 are located here. Radio on road to Pirates Cove.
ESE,15,A 11.6 Parking lot behind Avila Yes
~
Beach Post Office. Radio on road to Pirates Cove.
ESE,20,A 15.3 Pismo Beach Fire Dept.
Yes on Shell Beach Road.
Good radio.
ESE,20,8 19.2 0.5 miles northwest of Yes!
the Shorecliff Inn on Shell Beach Road. Good radio.
SE,2.A 1,3 Turnout on access road, No 0.8 miles from Security Building near meteorological Tower A.
Marked with red / - ;
white fence post. DER
~
Station 7 is near here.
s' Good radio.
(
DC0182 39VI
r-w 1 AND 2 EP RB-8 osaaLO CANYON POWER PLANT UNIT NCMS)
DATE 5/2/84 PAGE 40 0F 49 EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING TABLE 2 (Continued)
Straight Line Distance From AC Power Coordinate Plant (KM)
Description Available NW,2,A 1.6 0.6 miles north from No Field's property gate (1 mile north from plant, just ENE of Lion Rock).
NW,4,A 3.5 Fields' road near No large watering pond.
NW,8,A 6.1 Near residence by park Yesi gate.
NNW,4,A 2.7 Near wood paneled house.
Yes!
NNW,8,A 5.8 Parking lot near end of No6 road at southern park boundary (near gate to Fields' property). Good radio.
NNW,8,B 7.6 Ranger station over-Yes7 looking Spooner's Cove.
Good radio on road south of Ranger Station at
" Locked Gate Ahead" sign (near parking overlook of Spooner's Cova).
NOTES:
1 Power is available at nearby residences.
2During working hours. Also power is available at nearby residences.
80uring school hours. Also at neartiy residences.
r "During school hours.
l DC0182 40VI
w l
DWGLO CANYON POWER PLANT UNIT NCNS) 1 AND 2 EP RB-8 DATE 5/2/84 4
P GE 41 0F 49 A
EMERGENCY OFFSITE RADIOLOGICAL I#'I ENVIRONMENTAL MONITORING l
l l
TABLE 2 (Notes Continued)
SA dirt road leads to the top of the hill. The intersection of this j
roao with access road is marked with a red / white fence post. A 90909 key is required on the gate. A four-wheel drive vehicle is preferred.
Alternatively; take readings' on the access road at the marked fence post.'
i EPower is available at nearby residence on Fields' property (NW,8,A) and monitoring can be perforced at this latter location.
l 7During daylight hours.
BRadic comments refer to the best result using unaided handi-talkies I
using repeaters (H.P. Frequency).
I Q
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W C
DC0182 41VI
e DiasLO CANYON POWER PUWT UNIT NCMS)
EP RB-8 ON DATE 5/2/84 PAGE 42 0F 49 EMERGENCY 0FFSITE RADIOLOGICAL ENVIRONMENTAL WTORING TABLE 3 DER ENVIRONMENTAL SAMPLING LOCATIONS Radial Radial Distance Code Des'cription Direction O' (Miles) 081 Point Buchon (Station 18)........................
325 3.6 051 Exclusion Fence-Northwest Corner (Station 3).....
320 0.1 052 North Gate (Station 31)..........................
320 0.5 1A1 Crowba r Canyon (Station 13 )......................
327 1.6 ICI Montana de Oro Campground (Station 38)...........
336 4.7 151 Wa s tewa te r Pond (Sta ti on 32 ).....................
330 0.4 201 Sunnyside School (Station 10)....................
10 6.9 2F1 Morro Bay (Station 26)...........................
0 10.9 2F2
.Mo.'ro Bay Power Pl ant (Sta tion 9)................
358 11.2 051 Back Road-300 m North of Plant (Station 33)......
0 0.2 3D1 Clark Valley (Station 40)........................
24 6.2 351 Road NW of 230 kv Switchyard (Station 34)........
23 0.4 4C1 Clark Valley - Gravel Pit........................
45 5.8 4D1 Los Osos School (Station 11).....................
36 7.6 451 Back Road Between Switchyards (Station 35).......
43 0.5 SCI Junction Perfumo/See Canyon Roads (Station 39)...
64 4.7 5F1 SLO Zone 1 Substation (Station 12)...............
68 11.2 SF2 Cal Poly Farm (Station 25).......................
60 12.6 SF3 SLO County Health Department (Station 29)........
70 12.7 551 400 kv Switchyard (Station 4)....................
58 0.4 552 Diablo Creek Wei r (Sta tion 20)...................
65 0.6 553 Microwave Tower Road (Station 8).................
70 0.7 601 Junction See/ Davis Canyon Roads (Station 41).....
89 7.5 651 M icrowave Tower (Station 5 )......................
94 0.5 7C1 Pecho Creek Ruins (Station 16)...................
118 4.1 701 Avila Gate (Station 27)..........................
120 6.6 7D2 Avila Beach Station 14).........................
110 7.6 7F1 Shell Beach Station 17).........................
110 10.8 7F2 Pismo Beach Station 22).........................
115 12.6 7G1 Arroyo Grande (Station 23).......................
115 16.8 762~
Oceano Substation (Station 15 )...................
118 17.3 763 Woodland Dairy (Station 30)......................
122.
17.9 751 Overlook Road (Sta tion 36 ).......................
112 0.3 7S2 Diablo Peak (Station 28).........................
103' 1.1 851 Target Range (Station 6).........................
125- ;
0.5
~.--
a 1
DC0182 42VI
f.
j 1 AND 2 EP RB-8 masLO CANYON POWER M. ANT UMT NCNS)
DATE 5/2/84 PAGE 43 0F 49 EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING i
TABLE 3 (Continued)
Radial Radial Distance l
Code Description Direction O' (Miles) i-852 Southwest Site Boundary (Station 7).....
128 1.1 951 South Cove (Station 37)................
167 0.4 DCC
. Diablo Creek at Diablo Cove (Station 21).........
270 0.1 DCM Diablo Cove (Station 19).........................
270 0.2 ICO Iodine Cartridge Composite.......................
O C.0 LO Lompoc (at City Hall)............................
154 44.6 Mil Meteorological Tower (Station 1).................
185 0.2 SM Santa Ma ria (at Heal th Dept. )....................
127 29.7 SV Solvang (at Sheri ff's Substation)................
144 56.7 Wfil Northwest Gua rd Shack (Station 2 )................
290 0.2 9
~ ~
C DC0182 43VI
i i
1 AND 2 EP RB-8 pianto CANYON POWER PLANT UMT NCNS)
DATE 5/2/84 PAGE 44 0F 49 EMERGENCY OFFSITE RADIOLOGICAL ENVIR0fetENTAL MONITORING l
TABLE 4 l
ENVIRONMENTAL RADIATION MONITORING NETWORK STATION 0F THE NUCLEAR REGULATORY COMMISSION NRC STATION NO.
SECTOR AZIMUTH ZENTH DESCRIPTION 1
SE 125' 1.0 mi.
Site entrance road 2
ESE 119' 4.2 mi.
Site entrance road 3
ESE 107' 6.9 mi.
San Miguel Street, Avila Beach i
4 ESE 109' 10.6 mi.
Corner of Naomi Avenue and Seacliff l
Drive, Sunset Palisades area 5
ESE 113' 14.1 mi.
Corner of Atlantic City Avenue and Front Street, Grover City 6
ENE 68' 9.6 mi.
Perfumo Canyon Road, Laguna Lake Park Area 7
N 359' 11.1 mi.
PG&E Morro Bay Power Plant 8
N 359' 6.6 mi.
Pecho Valley Road, Cuesta by the Sea Area
(
9 NNW 339' 4.7 mi.
Montana De Oro State Park 10 NNW 328' 3.5 mi.
Private Property Road at end of Pecho Valley Road 11 NNW 332' 1.3 mi.
Private Property Road North of Diablo Canyon Plant 12 NE 37' 21.4 mi.
San Diego Road, Atascadero 13 NE 37' 21.4 mi.
San Diego Road, Atascadero 14 NE 37' 21.4 mi.
San Diego Road, Atascadero
~~
l i
DC0182 44VI
I St Damat O CANYON POWER PUWT UNIT NO(S) 1 AND 2 EP RB-8 DATE 5/2/84 PAGE 45 0F 49 EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING
~
TABLE 5 LOCATIONS OF SELECTED DAIRIES DAIRY HERD LOCATION RELATIVE TO DCPP L.F. Domenghini (500 cows)
NNE, 12.5 miles Roemee and Jones-(200 cows)
NNE, 11 miles L
Dutch Maid Farm (100 cows)
NE, 8 miles Dor. Warden (200 cows)
NE, 8 miles Jim Spreafico (150 cows)
E, 9.5 miles SLO Cal Poly Farm ENE, 10 miles l
l Albertoni Farm SE, 23.5 miles (Guadalupe) l I
~
(
DC0182 45VI
e 1 AND 2 EP RB-8 oues.o CANYCM POWER PLANT UMT NO(S)
DATE 5/2/84 PAGE 46 0F 49 EMERGENCY OFFSITE RAN 0 LOGICAL ENVIRONMENTAL MONITORING m.*
TABLE 6 PIC LOCATIONS LOCATION DESCRIPTION Site 1 DCPP North Gate Guard Post Site 2 SSW Corner of Target Range Site 3 715 Harbor Street, Morro Bay.
Small fenced yard on NE corner of Harbor Street and Piney Street intersection.
Site 4 Montano de Oro State Park. At the Park Ranger's residence, adjacent to the emergency siren.
Site 5 Los Osos Fire Department Site 6 SLO County Sheriff's Office.
South of EOF trailer behind retaining wall Site 7 SLO Police Department.
Intersection of Santa Rosa Street and Walnut Street.
Behind fence SW of Walnut Street driveway.
I Site 8 SLO service Center o
Site 9 PGandE Energy Information Center i
Site 10 DCPP Front Gate Site 11 Pismo Beach. From Bellow Street go N.E., turn between Veterans's Memorial and St.
Paul's Church and proceed up
~
dirt road. PIC is on top of '
hill north of pump house and west of water storage tank.
DC0182 46VI
l DMO CANYON POWER PLANT UNIT NO(S) 02 ON i
DATE 5/2/84 I
PAGE 47 0F 49 i
EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING t
i TABLE 6 (Continued) i I
i LOCATION DESCRIPTION l
Site 12
' SLO County Building. Grover City. Exit Hwy. 101 at 4th street. Take 4th to i
Longbranch and proceed NE on i
Longbranch.
County Social Services Building is on corner of 16th and i
Longb ra nch.
t P
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DC0182 47VI
1 AND 2 EP RB-8 DiasLO CANYON POWER PLANT UNrf NO(S)
DATE 5/2/84 PAGE 48 0F 49 EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL POilTORING
~
TABLE 7 BACKGROUND DATA FOR s/y DOSE AND/0R COUNT RATE MEASUREMENTS (3' ABOVE GROUND INSTRUMENT BACKGROUND DOSE RATE (mR/hr)
WINDOW CLOSED WINDOW OPEN Rad Owl 0
0 Victoreen Wadgun 0.02 0.02 HPI-1010 0.015 NA R0-2 0
0 GM PROBE BACKGROUND COUNT RATE (cpm) 5HIELD ON 5HIELD OFF HP-240/270 60 60 HP-260 NA 50 HP-210 NA 50
~
- N I
DC0182 48VI 7
--.,.--._.-y
,,_-n.,,.n.-,
,,__,-w,-.
v,-_
p l
1 AND 2 EP RB-8 Diaat.o CANYON POWER PL. ANT UNIT %S)
DATE 5/2/84 l
PAGE 49 0F 49 EMERGENCY OFFSITE RADIOLOGICAL 7,7g '
ENVIRONMENTAL MONITORING TABLE 8 i
GM-PROBE EFFICIENCY FACTORS, c; FOR IODINE DETERMINATIONS GM PROBE c2 (counts / dis) l HP-240/270 0.013 l
HP-260 0.09 I
l HP-210 0.09 j
l i
TABLE 9 I
GM PROBE EFFICIENCY FACTORS, c,,
FOR PARTICULATE DETERMINATIONS l
GM PROBE c,(counts / dis)
HP-240/270 0.018 HP-260 0.20 i
HP-210 0.18 TABLE 10 l
GM PROBE EFFICIENCY FACTORS, ci, FOR GROUND SURVEYS GM PROBE ci (uti/m2/com) i HP-240/270 0.0042 HP-260 0.0012 HP-210 0.0011
' ~
DC0182 49VI
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o M259 7 M3 M PACIFIC GAS AND ELECTRIC C019ANY P499 1 of 2 IslCLEAR PLANT OPERATI0ms CIABLO CANYON PmER PLANT UnlT N05.1 AfC 2 h
MREDitY ENvtacielENTAL senITORING FIELD DATA $NEET Team Leeder seemeer stonitoring Location
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i l-FGF4E Pacific Gas and Electric Company og 3 DATE 4/16/84 DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 4 DIABLO CANYON POWER PLANT UNIT NCMS) 1 AND 2 EMERGENCY PROCEDURE ACTIVATION AND OPERATION OF THE TECHNICAL IMPORTANT TITLE SUPPORT CENTER TO SAFETY W
C ^
APPROVED
=
PLANTMANAGM DATE SCOPE l
This procedure describes the actions that are to be taken in the evert it becomes necessary to activate and operate the Technical Support l
Center (TSC). Also described are instructions for turning over 7
seierted emergency functions from the Control Roorr to the TSC.
This procedure also describes the TSC's ventilation system and its l
operation. This procedure and changes thereto requires PSRC review.
l l
GENERAL l
The objective of the TSC is to provide personnel and equipment to relieve the control room staff from emergency activities unrelated to i
maintaining the plant in a safe condition. These functions are:
1) l Site emergency response management, 2) connunications with offsite emergency response organizations, 3) offsite emergency response i
coordination, including radiological monitoring and reconnendations for offsite protective actions, 4) accident assessment of plant conditions.
t The TSC serves as the headquarters for the Site Emergency Coordinator, the Emergency Liaison Coordinator, the Emergency Evacuations and Recovery Coordinator, the Emergency Maintenance Coordinator, the Emergency Operations Advisor, the Emergency Radiological Advisor, and l
their staffs.
INITIATING CONDITIONS l
The criteria for activating the TSC will be, but is not limited to the declaration of an Alert, Site Area Emergency or General Emergency as defined in EP 6-1," Accident Classification and Emergency Plan Activation." The emergency signal is sounded or a call out of personnel is initiated to activate and fully staff the TSC in l
accordance with EP G-2 " Establishment of the Onsite Emergency Organization."
}
l l
DC0009 IVI
l NUMBER EP EF-1 DinaLO CANYON PCMER PLANT UNIT NCNS) 1 AND 2 REVISION 3 DATE 4/16/84 PAGE 2 0F 4 ACTIVATION AND OPERATION OF THE TECHNICAL i
TITi.E:
SUPPORT CENTER IMEDIATE ACTIONS 1.
All onsite personnel, upon hearing the emergency signal or being notified of its activation, shall report to their assigned assembly areas in accordance with EP G-4, " Personnel Accountability and Assembly."
i l
2.
The Shift foreman may assign a Liaison Assistant to activate the TSC ssitchboard to receive incoming phone calls and complete notification of plant staff from this location, i
g Figure 1 provides a floor plan of the TSC.
/
SUBSE0 VENT ACTIONS l
)
l 1.
The Site Emergency Coordinator shall activate the TSC by l
establishing the emergency response organization in the TSC and j
l relieving the interim Site Emergency Coordinator (normally the l
l Shift Foreman) of his duties.
l 2.
When the TSC has'been activated and staffed to acceptable minimum t
levels, the Site Emergency Coordinator shall formally announce I
that the TSC has been activated and he (the SEC) is assuming overall management of PGandE emergency response efforts from the interim Site Emergency Coordinator (normally the Shift Foreman in the Control Room).
3.
Interim emergency response personnel will continue their assigned
[
duties until relieved by someone in the long-term emergency i
organization, or dismissed by the Site Emergency Coordinator.
Personnel relieved may be re-assigned to other emergency response j
functions.
l 4.
Plant personne) :ssigned to the TSC shall activate the TSC by first notifying the Site Emergency Coordinator (or Liaison i
Coordinator) of their arrival, and then proceed with their i
activation checklist.
j l
g: If the emergency involves control room inaccessibility l
l personnel should establish casuunications ith the Hot j
l Shotdown panel (X1431 Unig 1. X2432 Unit 2 and/or l
dedicated shutt5m panel LX1355 Unit 1, X2 5 Unit 23 in i
lieu of the control mom.-
j l
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DC0009 2VI
NUMBER EP EF-1 020 CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 4/16/84 PAGE 3 0F 4 ACTIVATION AND OPERATION OF THE TECHNICAL 7gtg SUPPORT CENTER SUPPORTING PROCEDURES G-1 " Accident Classification and Emergency Plan Activation" G-2 " Establishment of the Onsite Emergency Organization" G-3 " Notification of Offsite Organizations" l
G-4 " Personnel Accountability and Assembly" EF-6 " Activation of the Emergency Assessment and Response System" EF-7 " Activation of the Nuclear Data Communicatiens" OP-4 " Operating Order "I hour Reporting Requirements to the NRC" FIGURES 1.
TSC Floor Plan ATTACHMENTS 1.
69-11112-1 TSC Activation and Operation Checklist for the Site Emergency Coordinator.
2.
69-11112-2 TSC Activation and Operation Checklist for the Emergency Liaison Coordinator.
3.
69-11112-3 TSC Activation and Operation Checklist for the Emergency Evaluations and Recovery Coordinator.
l 4
69-11112-4 TSC Activation and Operation Checklist for the Emergency Radiological Advisor.
l S.
69-11112-5 TSC Activation and Operation Checklist for the Emergency Maintenance Coordinator.
6.
69-11112-6 TSC Activation and Operation Checklist for the Emergency Operations Advisor.
7.
69-11112-7 Activation of the TSC Ventilation System for Abnormal Operation.
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l DC0009 3VI l
I ff0N Ot4GLO CANYON POWER PLANT UNIT NCMS) 1 AND 2 DATE 4/16/84 PAGE 4 0F 4 m
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER FIGURE 1 Floor Plan of the Technical Support Center Tac y=
- 1. Office v, =%-
_. a a 3
- i. Computer U
- 2. %
5 Camer L IL/ I C8 "" t q-l i
ga
- 3. Carroutadon s
=-s Camer x
VU l
- 4. plecords I w.
Managemem System w
7
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se EIR M
- 8. HVAC Room dn i-*
yk p 3 p
- 7. m _,
L NOT drawn to scah DC0009 4V i
97 9
.!j 69-11112-1 5/84 (20)
Page 1 of 2 PAtlFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 g
t TSC ACTIVATION AND OPERATION CHECKLIST FOR THE SITE EMERGENCY C00RC NATOR TITLE:
(SEC)
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[
Have the Emergency Liaison Coordinator (ELC) establish manning status of TSC i
1.
(Use Form 69-9370 " Site Emergency Organization Assignments"). Nctify tne G4 if Security Shif t Supervisor of personnel accounted for in the TSC per EG the site emergency signal is sounded.
Notify the Control Room, TSC staf f and interim EOF sta'f that you (the SE '
2.
are assuming overall management of PGandE emergency response efforts 'ece tee ir.terim SEC (normally the Snif t Forer an).
3.
Have the ELC establish and maintain co rtunications with:
aar,Rccr, Serice Centrol Operator's Desk Control a.
v -age-Oceratices Facility. 0:erating ard anal m l c ::ver, a
a e
b.
t-Radiological Emergency Recovery Marager oced' nato orporate Incident Response Center, Corporate Liaison c.
Verify that the equipment in the TSC is operational:
4 Eeergency Evaluations and Recovery Manager a) Ventilation System b) NOCS (Harris) cceputer systems c) Emergency Response Facility Data System (ERFCS-)
l Emergency Radiological Advisor Radiation fronitoring ecuipment in the TSC a) b)
Eftergency Assessment and Respense System (EARS)
Emergency Operations Advisor a) Television monitoring equipment If necessary, provide instructions to personnel at assembly areas (See EP 5.
G-4), authorize the evacuation of non-essential personnel, and specify the evacuation route (see EP G-5).
7 Prior to the arrival of the corporate Recovery Manager at the ECF:
6.
Maintain conynunication with the ACEO and direct all emergency resconse a.
operations performed by PG&E in the San Luis Obispo area.
Authorize company protective action recocinendations to the County.
b.
OC0009 SV!
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w 69-11112-1 S/84,(20)
Page 2 of 2 TITLE: TSC ACTIVATION AND OPERATION CHECKLIST FOR THE SITE EMERGENCY COORDINATOR (SEC) c.
Change the Emergency Action Level Classification as necessary and have the ELC notify required offsite organizations (see EP G-3) and all emergency response groups onsite.
d.
Authorize release of information about the emergency to the news media.
e.
Other responsibilities as given in Table 1 of Procedure EP G-2.
7.
Communicate significant events and decisions to the EOF and Control Room.
8.
Maintain a log of significant communications and decisions.
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w 69-11112-2 5/84 (20)
Page 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 TITLE: TSC ACTIVATION AND OPERATION CHECKLIST FOR THE EMERGENCY LIAISON C00RCINATCR (ELC) 1.
Establish notification status of offs arizations an.d plant persenrel fror the interim Liaison Coordinator anc assicr. tre Liaiscr i
Assistants to relieve the Contro room o that respcnsibility.
~
l 2.
Activate the conmurication links by performing a functional check on the UHF/VHF rad 10 and telephone communications equipment required. Ass 1gn a clerk or liaiser assister.1 to activate the TSC switchboard ard relieve the certe:'
reor of the responsibility of arswering incocing calls.
3.
Direct liaison assistarts notificatices and status updates to of' site orgar.12atice and corrunicatices for TSC personnel. Mairtain conruricatices with:
a.
Contrcl Room, Senior Control Coerator's Desk
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b.
rg y Operations Facility, Operations and Analytical Recovery Pgr.,
I Oroor de Incident Response Center, Corporate Liaison Coordinator, c.
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DC0009 7VI
m
?o 69-11112-3 5/84.(20)
Page 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 TITLE: TSC ACTIVATION AND OPERATION CHECKLIST FOR THE EMERGENCY EVALUATIONS AND RECOVERY COORDINATOR (EERC) 1.
Determine the nature of emergency from the interie Emergency Evaluations and Recovery Coordinatnr (STA).
2.
If necessary, request the Control Poom to switch the TSC from non-vital te vital power (specify Unit 1 or Unit 2). The switches are located in the Urit 2 480V switch gear room (Panels EPTSN and EPTSC).
3.
l Assign data processors to activate the NDCS (harris) computer syster acccccing to Procedure EP EF-7, to monitor the ERF05 and to develop and inter: ret plart l
data for Transmission offsite.
4 Provide the SEC, in consultation with the ERA any recommendations for appropria*.e response actions; and on-site and offsite recommendations for protective actions.
5.
Keep the SEC and the ERA informed of plant equipment and monitoring personnel status and the esaluations and recommendations regarding plart operations.
6.
Assign personnel to monitor the ventilation system and perform any manual detions needed. See Appendix DC69-11112-7.
7.
Maintain a log of significant communications and decisions.
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DC0009 8vl t
u 69-11112-4 5/84.(20)
Page 1 of 2 PAtlFIC GAS AND ELECTRIC COMPANf DEPARTMENT OF NUCLEAR OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 TITLE: TSC ACTIVATION AND OPERATION CHECKLIST FOR THE EMER. RADIOLOGICAL ADVIS0P (ERA) 1.
Verify that radiation monitoring equipment in the TSC is operational.
2.
Assign personnel to operate the Emerger.cy Assessmert and Response Syster (EARS). Have radiological status forms prepared providino apprcpriate re' ease rate, rneteorological and other radiological information for offsite organizations. Forward these to the ELC.
3.
Deterrine the extent o' radiolcgical mocitoring and health physics su;;0'*
recuired in-plant, on-site and off-site (in corsultat'on witn ECF pecs:are' and make personnel assignments for these tronitoring activities.
4 Maintain communications with the Radic'cgical Emergency Recovery Ma*ager ( R E R* ',
at the EOF:
a.
Consult on the pctertial cr real release rates for radioactive material.
b.
Consult on the off-site monitoring and assessment activities with the RERM.
5.
Maintain cormunications with tf chemistry and Radiation Protectice
' Approve all entries to the controlled Coordinator at access contro]oca ton of response personnel.
area and keep informed of the l 6.
Maintain cortunications with the Emergency Evaluations and Recovery Cecedinater (EERC).
a.
Advise the EERC of offsite protective actions appropriate to the situation, b.
Inform the EERC of the radiological exposure status of personrel and ecuipment involved in emergency response.
C.
Determine if plant status changes will adversely affect personnel exposure.
7.
Direct and Control the onsite monitoring team (s).
8.
Have the Emergency Liaison Coordinator call out dosimetry manpower as recuirec to prepare for determining radiation exposure,0f emergency response personnel.
ohn rrick i
OC0009 9Y!
e 69-11112-4 5/84,(20)
Page 2 of 2 i
TITLE: TSC ACTIVATION AND OPERATION CHECKLIST FOR THE EMER. RADIOLOGICAL ADVISOR (ERA) 9.
Maintain a log of significant communications and decisions.
- 10. If the event possibly involves a release, assure that contamination control l
equipment (meter, shoe covers, etc.) is available and operable to avoid I
contamination of the TSC.
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l OC0009 10VI
'l 69-11112-5 5/84,(20)
Page 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 TITLE: TSC ACTIVATION AND OPERATION CHECKLIST FOR THE EMERGENCY MAINTENANCE COORDINATOR (EMC) 1.
Determine repair / damage control and corrective actions for plant mechanical, electrical, and instrumentation and control systems, and coordinate all such activities from the TSC through the appropriate maintenance coordinator.
2.
Keep the Site Emergency Coordinator and the Emergency Evaluatiens and Recevery Coordinator informed of the status of equipment and personnel involved in the repair /camage control effort and the status of personnel availability for in-plant support by coordinating personnel accountability with the Operati:nal Support Center (Security Building Lunchroom) Supervisor.
3.
Keep the Shift Foreman informed of the status'of equiprent and personnel invclved in the repair / damage control effort.
NOTE: ALL ENTRIES INTO A RAD 10 LOGICALLY CONTROLLED AREA WILL REQUIRE A SWP AND THE APPROVAL OF THE EMERGENCY RADIOLOGICAL ADVISOR.
(See Procedure EP RB-4).
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69-11112-6 5/84.(20)
Page 1 of 1 -
PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 TITLE: TSC ACTIVATION AND OPERATION CHECKLIST FOR THE EMERGENCY OPERATIONS ADVISOR (E0A)
-1.
Verify that the control room television monitoring equiemert is operational by obtaining a clear picture of the control room indicators aperc;riate the situation.
2.
Establish communication with the Emergency Operations Coordinator ir the control room.
3.
Kee; the Site Emergency Ccordinator advised as to plant operational activities
'anc any requests for assistance.
4 Assist the Emergency Evaluation and Recovery Coordinator (EESC) in meritoring SDCS information and obtaining plant cata as recuired.
5.
Deterrine the need for assistance in handling radioactive waste and advise the
, Emergency Evaluation and Recovery Coordinator (EERC).
(
DC0009 12VI
p 9r 69-11112-7 -5/84,(20)
Page 1 of 6 PAtlFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS.1 AND 2 TITLE: ACTIVATION OF TSC VENTILATION SYSTEM FOR ABNORMAL OPERATI!ON PROCEDURE Operation of the ventilation system in any mode other than mode 1 is considered ar.
abnormal condition.
A.
Mode 2 - Fire This mode only concerns the control room in the event of a fire.
B.
Mode 3 - Chlorine inthismodetheControlroomandTSCareisoiatedfromalloutsideair.
100',
of the air is recirculated with 9% of the flow passin6 through HEPA arc charcoal filters. This mode can be initiated automatically, as describec in the general operating procedures OP H-5:!V or manually from the control room.
When an alarm is activated or the control room wishes to manually activate Mode 3, the TSC will be notified and asked to perform the following functions for Mode 3 operation.
1.
Check the TSC outside (make up) air fan 05-93 has stopped.
2.
Check the TSC lead filter supply fan 05-94 has started.
3.
Close vent damper 0-18 manually.
4 Verify that vent damper 0-17 is closed.
5.
Open vent damper 0-26 manually.
6.
Verify the following at the annunciator panel PK-75, located in the TSC computation center:
a.
AD "TSC MODE 3 ISOLATION" illuminated.
b.
AE "TSC MODE 1 NORMAL VENT" not illuminated.
c.
BB-1 " NORMAL VENT DAMPER OPEN ON MODE 3 or 4" 0-18 not illuminated.
d.
BB-2 " CARBON FILTER DAMPER CLOSED IN MODE 3 OR 4" 0-26 not illuminated.
e.
BC " NORMAL VENT ON" 05-93 not illuminated.
f.
BD " CARBON FILTER LOW AIR FLOW" not illuminated.
g.
BE "TSC AREA AIR COND. ON" 05-92 illuminated, h.
BE " LAB AREA AIR COND. ON" 05-90 illuminated.
1.
BF "TSC AREA AIR COND. 0FF MODE 3 OR 4" not illuminated.
j.
BF " LAB AREA AIR COND. OFF MODE 3 OR 4" not illuminated, k.
CE " LEAD SUPPLY FAN ON MODE 3 OR 4" 05-94 illuminated.
1.
CF "REDUN. SUPPLY FAN ON MODE 3 OR 4" 05-95 illuminated.
If any of these annunciator lights cannot be verified, consult the section on annunciator lights for further instructions.
c DC0009 13VI
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69-11112-7 5/84.(20)-
Page 2 of 6 TITLE: ACTIVATION OF TSC VENTILATION SYSTEM FOR ABNORMAL OPERATIION C.
Mode 4 - High Radiation or Dilution Mode 4 is automatically activated by high radiation levels at the control room intakes or by a Phase A isolation signal. Mode 4 can also be activated manually. This is used after prolonged periods of Mode 3 to dilute the CO which has accumulated in the TSC. WhentheventilationsystemisinMode3the TSC will be notified and asked to perform the following functions.
1.
Check the TSC outside (make up) air fan 05-93 has stopped.
2.
Check-the TSC lead filtered supply fan 05-94 has started.
3.
Close vent damper 0-18 manually.
-4 Open vent damper 0-17 manually.
5.
Open damper 0-26 manually.
6.
Verify the following at the annunciator panel PK-75, located in the TSC computation center:
a.
AC "TSC MODE 4 PRESSURIZATION" illuminated.
b.
BB-1 " NORMAL VENT DAMPER OPEN MODE 3 OR 4" not illuminated.
c.
BB-2 " CARBON FILTER DAMPER CLOSED IN MODE 3 OR 4" 0-26 not l
illuminated.
d.
BD " CARBON FILTER LOW FLOW" FB-94 not illuminated.
4 e.
BE-1 "TSC AIR COND. ON" 05-92 illuminated.
I f.
BE-2 "LA8 AREA AIR COND ON" 05-90 illuminated.
g.
CA " LEAD DUCT HEATER ON MODE 4" OEH-28A illuminated.
h.
CE " LEAD SUPPLY FAN ON MODE 3 OR 4" 05-94 illuminated.
l If any of these annunciator lights cannot be verified, consult the section on f
annunciator lights for further instructions.
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l 7.
For Mode 4 operation to be completely functional the following doors must be closed, a.
Office space outside water tight door, b.
Office space inside door.
l c.
Computation center outside water tight door.
d.
Computation center inside door.
l e.
NRC Office outside water. tight door.
l f.
NRC Office inside door.
g.
Mechanical room outside water tight door.
h.
Mechanical room air control plate (slide gate) l l
1.
Laboratory outside water tight door (West).
i j.
Laboratory inside door (West).
k.
Laboratory outside water tight door (East).
l 1.
Laboratory inside door (East).
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DC0009 14VI
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69-11112-7 5/84.(20)
Page 3 of 6 TITLE: ACTIVATION OF TSC VENTILATION SYSTEM FOR ABNORMAL OPERATIION D..
Returning to Mode 1 Operation The control room will place the ventilation mode selector switch located at vertical board IVB4(2VB4) in the Mode 1 position to return the system to normal operation. The TSC sha confirm that the ventilation system has returned to normal by verifying the following.
1.
Lead Supply Fan 05-94 is off.
2.
Outs de (make up) Air Fan 05-93 is on.
3.
Damper 0-18 opened manually.
4 Damper 0-17 closed manually.
5..
Damper 0-26 closed manually.
E.
TSC Annun:iator Panel The following is a list of each TSC annunciator panel light with inforration included on what to do in the event a light does not function properly.
AA-l' (RED) High radiation in TSC area.
If illuminated notify the Cor. trol Room and Radiation Protection and follow radiation control procedures.
AA-2 (RED) High radiation in TSC airflow.
If illuminated follow radiation control procedures.
AB-1 (RED) High radiation in lab area of TSC. If illuminated follow radiation control procedures.
AB-2 (RED) High radiation in lab area airflow. If illuminated follow radiation control procedures.
AC (WHITE) TSC Mode 4 pressurization.
If not illuminated during Mode 4 pressurization check the procedure for Mode 4 operation.
AD (WHITE) TSC Mode 3 isolation. If not illuminated during Mode 3 isolation, check the procedure for Mode.3 operation.
AE TSC Mode 1 normal ventilation.
Illuminated in normal operation Mode 1.
AF.
SPARE. Not illuminated.
BA-1 Normal vent damper open Mode 1.
Illuminated in normal operation Mode i
1.
If not illuminated in Mode 1 verify manual operated camper 0 18 is open.
c DC0009 15VI
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i 69-11112-7 5/84.(20)
Page 4 of 6 l
TITLE: ACTIVATION OF TSC VENTILATION SYSTEM FOR ABNORMAL OPERATIION BA-2 Carbon filter damper closed in Mode 1.
Illuminated in normal l
operation Mode 1.
If not illuminated in Mode 1 verify manual i
. operated damper 0-26 is closed.
i 88-1 Normal vent damper open in Mode 3 or 4.
Illuminate when damper 0-18 is open in Mode 3 or 4 operation. Damper 0-18 must be closed manually.
l 88-2 Carbon filter damper closed in Mode 3 or 4.
Illuminated when damper l
0-26 is closed in Mode 3 or 4 operation. Damper 0-26 must be opened i
manually.
BC Normal vent fan on 05-93.
Illuminated in normal operation Mode 1.
Should be off in Mode 3 or 4 operation.
j 80 Carbon filter low air flow F8-94.
Illuminated when there is not enough airflow through carbon filters in Mode 3 or 4 operation.
I Check lead and redun. Supply fans 05-94 and 05-95 for one of them to be running with corresponding damper open, 0.-24 or 0-25.
t BE-1 TSC Area Air Condition on 05-92, illuminated in all operations.
BE-2 Lab area air condition on. 05-90.
Illuminated in all operations.
8F-1 TSC aree air condition off in Mode 3 or 4 05-92.
Illuminated when air conditioner for TSC is not in operation during Mode 3 or 4 Investigate circuit breakers (PPTSC) to put back into operation.
v i
BF-2 Lab area air conditioner off in Mode 3 or 4, 05-90.
Illuminated when l
air conditioner for lab ' area is not in operation during Modes 3 or 4 Investigate circuit breakers (PPTSC) to put back into operation.
CA Lead duct heater on Mode 4 operation, OEH28A.
Illuminated in proper i
Mode 4 operation.
}
l C8 Lead duct heater malfunction, OEH28A.
Illuminated when a malfunction i
j is triggered in Mode 4 operation. To troubleshoot check the i
following:
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a.
Check circuit breaker panel PpTSC3 to be on.
b.
Check motor starter switch LPTSC3 to be on with green light illuminated.
c.
Check damper 0-17 to be open.
If the lead duct heater still will not function turn the starter l
switch LPTSC3 off and energize LPTSC4 for rudun. supply heater OEH288.
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nC0009 16VI
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69-11112-7 5/84.(20)
Page 5 of 6 TITLE: ACTIVATION OF TSC VENTILATION SYSTEM FOR ABNORMAL OPERAT110N f
i CC No duct heater on Mode 4 ope-ation OEH28B illuminated in l
proper Mode 4 operation.
CD Re' dun. duct heater malfunction, OEH2BB.
Illuminated when a f
malfunction has tripped a sensor. To trouble shoot check the i
following:
a.
Check circuit breaker panel PpTSC4 to be on.
b.
Check motor starter switch LPTSC4 to be on with green light illuminated.
c.
Check damper 0-17 to be open.
If both OEH-28A and OEH-28B both cannot be energized, notify Control Room that Mode 4 Operation of ventilation system is not functioning.
CE Lead supply fan on Mode 3 or 4, 05-94 Illuminated in normal Mode 3 or 4 operation.
If inoperable in Mode 3 or 4 check the following.
a.
Check circuit breaker panel PPTSC-6 to be on.
+
b.
Check at local disconnect switch LPTSC-5, place in on position and verify green light is illuminated.
c.
Press start button and verify green light is out and red light is illuminated with fan running, d.
Verify corresponding damper is open 0-24 or 0-25.
If the fan will not operate properly turn local disconnect switch LPTSC-5 off and LPTSC-6 on for fan 05-95.
CF Redun. supply fan on Mode 3 or 4, 05-95.
Illuminated in Mode 3 or 4 when 05-94 is not functioning.
If 05-95 is also inoperable refer to checklist on panel CE.
If neither fan will operate notify the control room of malfunction.
DA TSC radiation monitor failure or loss of AC power.
Illuminated when the TSC radiation monitor fail or lose AC power. Switch the TSC to vital AC power. If still illuminated, notify the shift foreman.
DB Fire Detector.
Illuminated when fire is detected in HVAC Room.
DC SPARE. Not illuminated.
00-1 Pressurization damper closed in Mode 4. 0-17.
Illuminated when damper 0-17 is closed in Mode 4 Damper 0-17 must be opened manually.
00-2 Pressurization damper open in Mode 1, 2 or 3, 0-17. ' Illuminated when damper 0-17 is open in Mode 1, 2, or 3.
Damper 0-17 must be closed.
c DE SPARE. Not illuminated.
DC0009 17VI
F 69-11112-7 9/83.(20)
Page 6 of 6 TITLE: ACTIVATION OF TSC VENTILATION SYSTEM FOR ABNORMAL OPERATION FIGURE 1 Annunciator Panel l
A B
C D
E F
T5C A8tA TSC LAD AntA TSC De0t 4 TSC mot 3 TSC N00t I l
NIGN W Nik AA0 Petssual2Afl0m 150LATION N0 anal vtNT
$ pang g
i T5C AIR 3084 T5C AIR 90NN MIGH RAD MIGl RAC N0 anal vlief NONNAL vtMT TSC AatA T5C AREA MR PEN DANMR OMN NonNAL 70T Can30m FILTER AIR CONO. ON AIR ConD. Orr ME1 800C 3 OR 4 FAN ON LOW AIR FLOW 05-92 N00t J Ua 4 8
o la e-is 05-i2 CAas0N FILTER caaDum FILTER 05-93 F8-94 g gagg lag AREA OAN M R CLO$to DAMMR CLOSED AIR Cole' el AIR COND. OFF nuot 1 0-26 j
0 2.uut J Da 4 IN n 05-M
' WOE J Os 4 05.,0 m
M l
LEA 0 OuCT LEAD QuCT W OuCT RtouM. DUCT LEAD SUPPLY REDum. SUP'LY I
C NEAftR ON MEAftR NEATER ON MEATER FAN ON FAN ON sept 4 seRLFUNCTION sept 4 NALFUNCTION scot 3 De 4 NODE 3 On 4 OG 28A OEH 28A OEM 288 OEM 288 05 94 05 95 Pat $$ DANMR
$!LthCE ACK N I" f5C RAD IGN D
'u'E o' he PnE55 GAMPit OM N IN 840E 1 2 On 3 0-17 TEST Rt3ET mummme LIGif5 in Rio 1
DC0009 1811
4 w
NUMBER EP EF-3 l
FGues Pacific Ses aml Electric Company REVISION 4 DATE 4/16/84 DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 3 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE NPORTANT ACTIVATION AND OPERATION OF THE EMERGENCY f
TO TITLE OPERATIONS FACILITY SAFETY Y$
APPROVED PLANTMANAJ))
DATE SCOPE This procedure describes the actions to be taken in the event it becomes necessary to activate and operate the Emergency Operations Facility (EOF). The EOF is considered to include all facilities provided by PGandE at the San Luis Obispo County Sheriff's Complex, including the EOF /EOC building and the Media Center. This procedure and changes thereto requires PSRC review.
GENEPAL The principal purpose of the EOF is to provide a location for management of overall emergency response and facilitate the coordination of emergency response activities between PGandE, county, state and federal agencies. The EOF is co-located with the San Luis Obispo County Emergency Operations Center (E0C). The EOF serves as the headquarters for the Recovery Manager in directing emergency response and recovery efforts. the EOF /EOC provides a central point of data assessment for PGandE, federal, state and local agencies.
It also serves as a centralized location fer dissemination of informatior to the public.
INITIATING CONDITIONS The criteria for activating the EOF will be, but is not limited to the declaration of an Alert, Site Area, or General Emergency as defined in j
EP G-1, " Accident Classification and Emergency Plan Activation".
i IMEDIATE ACTIONS 1.
Upon declaration of an Alert, Site Area, or General Emergency at the Diablo Canyon Power Plant, the Shift Foreman shall assume the duties of the Site Emergency Coordinator and shall notify c
DC0102 IX
D t
oweLO CANv0N POWEM PLANT UMT NO(S) 1 AND 2 NUMBER EP EF-3 REVISION 4 DATL 4/16/84 i
PAGE 2 0F 3 8
l 7m.
ACTIVATION AND OPERATION OF THE EMERGENCY
~
OPERATIONS FACILITY personnel to staff the EOF in accordance with EP G-3,
" Notification of Offsite Emergency Organizations" and EP G-2,
" Establishment of the Onsite Emergency Organization".
J g: The Recovery Manager shall notify the corporate emergency organization in accordance with Procedure 1.1 of the Corporate Emergency Response Plan following his l
notification.
SUBSEQUENT ACTIONS 1.
Plant personnel assigned to the EOF shall notify the Watch l
Connander on duty at the San Luis Obispo Sheriff's Dispatch Center, that they are at the EOF to man it and then proceed with l
their activation c'hecklist.
r 2.
Plant personnel assigned to the EOF will continue to their i
assigned duties until relieved by corporate EOF Personnel, or I
dismissed by the Site Emergency Coordinator. Personnel relieved l
may be re-assigned to other emergency respepe functions, or may provide backshift coverage of corporate EOF functions, as needed.
j 3.
If an event is classified as an Alert, the Advisor to the County t
Emergency Organization should determine if corporate EOF i
i personnel are proceeding to the EOF, and if not, arrangements to provide relief plant personnel at the EOF may be needed.
4 When the EOF has been activated and staffed by the long-tem EOF organization to acceptable minimum levels, the Recovery Manager l
shall formally arnounce that the EOF has been activated b i
assuming overall management of PGandE emergency PGAE Corporate Organization and he (the Recovery Manager is efforts from the Site Emergency Coodinator in the TSC.
5.
When menned, status updates to San Luis Obispo County will be provided by the E.0.F.
Changes in emergency classification or l
information on the estimated potential for time of or extent of a release will be insiediately provided to offsite organizations as l
authorized.
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M DuGLO CANYON POWER PLANT UNIT %S) 1 AND 2 NUMBER EP EF-3 REVISION 4 DATE 4/16/84 PAGE 3 0F 3 TTa ACTIVATION AND OPERATION OF THE EMERGENCY OPERATIONS FACILITY SUPPOPTING PROCEDURES G-1, " Accident Classificaticn and Emergency Plan Activation" G-2, " Establishment of the Onsite Emergency Organization" G-3, " Notification of Offsite Organizations" EP EF-6 " Activation of the Emergency Assessment and Response Syster" EP EF-7 " Activation of the Nuclear Data Communications System" ATTACHMENTS 1.
69-10781-1 EOF Activation Checklist for the Advisor to the County Emergency Orgarization.
2.
69-10781-2 EOF Activation Checklist for the Interim Radic!cgical Recovery Manager.
3.
69-10781-3 EOF Activation Checklist for the Interim EARS Operator.
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4 69-10781-4 EOF Activation Checklist for the Interim Operations and Analytical Recovery Manager.
5.
69-10781-5 EOF Activation Checklist for the Interim Public Information Recovery Manager.
6.
69-10781-6 EOF Activation Checklist for the Technical Assistant to the Public Irformation Recovery Manager.
e DC0102 3X
69-10781-1.5/84 (25)
Page 1 of 2 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS c
-DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 i
TITLE:
EOF ACTIVATION CHECKLIST FOR THE ADVISOR TO THE COUNTY EMERGENCY ORGANIZATION (ACEO) 1.
Use the recovery manager's office.
2.
Establish manning status of EOF.
i i
3.
Contact shift cler l
yet filled.
or callout status of positions not 4
Call out any additional EOF personnel required, the County Liaison and the Monitoring Team Liaison Coordinator will reavire i
callout if not already done, t
5.
Contact the liaison Coordinator at the C
h Provide status of EOF activatien and provide names ard a.
i positions of personnel at the EOF.
b.
Determine nature of emergency.
Determine general plant status.
l c.
d.
Request copies of notific tien.and data forms via Panafax I
i (EOF Panafax PT&
i If the TSC i n
et functional - call the control roem liaison coordinator
^
6.
Contact the corporate Liaison coordinator at CIRC Provide status of EOF activation and provide names and a.
positions of personnel at the EOF.
7.
Get emergency ir formation updates from the interim RERM and 0 ARM.
8.
Contact the Site Emergency Coordinator at the TSC and obtain permission to brief the county emergency organization and 1
assume responsibility for updating the county EOC.
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69-10781-1 5/84 (25)
Page 2 of 2 TITLE: EOF ACTIVATION CHECKLIST FOR THE ADVISOR TO THE COUNTY EMERGENCY ORGANIZATION (ACE 0) 9.
Contact county perso'nnel at the EOC and UDAC (use county liaison as needed),
a.
Provide status of EOF activation, b.
Provide briefing on plant status, Inform them that updates are to be provided through the EOF, c.
and information to the sheriff's dispatch office will cease, d.
Provide normal status updates approximately every 15 minutes.
hgTE:
Irwediate notification of a change of classification or change in, the potential for a release will be made to the county.
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,/84 (25)
Page 1 of 2 69-10781-2 5
PACIFIC GAS AND ELECTRIC COMPANY t
DEPARTMENT OF NUCLEAR PLANT OPERATIONS I
O!ABLO CANYON POWER PLANT UNIT N05. 1 AND 2
{
TITLE:
EOF ACTIVATION CHECKLIST FOR THE INTERIM RADIOLOGICAL RECOVERY MANAGER (RERM) 1.
If you are the initial person at the EOF assume the duties of the ACEO, and complete Form 69-10781-2, " EOF Activation Checklist for l
the Advisor to the County Emergency Organization ( AECO)," first, 2.
Use the RERM's office.
{
a 3.
Check manring status for EARS operater and field team liaison coordirator, and assist in fillirs positions as needed.
j 4
stablish contact with emergency radiological advisory (ERA),
in the TSC.
a.
Provide status of EOF activation and provide na ms and i
positions of personnel at the EOF.
b.
Cetermine nature of emergency, Determine general plant status.
c.
d.
Ottain the available information on radiological conditions.
If the TSC is not yet functional, call the rim emer en evaluations and recovery coordinator (STA),in l
5.
Report status to the Advisor to the Count Eme gency Organization (ACEO) in the Recovery Manager's Office 6.
Advise County UDAC personnel of radfological conditions and Plant status under direction from the AECO.
7.
Establish contact with the f1 te MEML g
or through the service center 8.
Direct field teams as required.
Transmit EOC decisions on protective actions (i.e. One way traffic due to evacuations etc.)
to the field team. Coordinate these activities with the ERA.
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y 69-10781-2.5/84 (25)
Page 2 of 2 TITLE: E0F ACTIVATION CHECKLIST FOR THE INTERIM RADIOLOGICAL RECOVERY MANAGEO (RERM) 9.
Provide radiological data to the clerk for distribution as required, using forms found in Emergency Procedure 6-3.
Brief the AECO and 00AC as needed.
- 10. Evaluate plant radiological conditions and provide status and recommendations to the ACEO as required.
- 11. Assign a clerk to maintain the UDAC radiological status board as status updates are obtained.
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'flTLE EOF-ACT!_ VAT!6K CHECR'.lST FOR THE INTERIM EARS OPERATOR s
'1.
' Contact. EARS.,orirator' i% TLC If the TSC'is not
,.yet-fu cti,9nal', ce W itt i evalu_ations ard 1
r recovery' coo.rdinator (STA'
- 2. ' NActivatt EAR 5 sequins.'t as per Ernergency, Procedure EF-6, "Acti.ation si-the Ernergency Assessrr,ent and Response Systerr."
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Provide.assistante to'RERH.as required in obtaining additional perschnel, rad 1QLgical calculdjons, contacting field tearts,
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69-10781-4 5/84 (25)
Page 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 TITLE:
EOF ACTIVATION CHECKLIST FOR THE INTERIM OPERATIONS AND ANALYTICAL RECOVERY MANAGER (OARM) 1.
If you are the initial person at the EOF assume the duties of the AECO, see Form 69-10781-2 " EOF Activation Checklist for the Advisor to the County Emergency Organization (AECO)," first.
2.
Contact Shift Cler o determine clerk call out status, if clerks are not ye ava able.
3.
Check Emergency Response Facility Data !ystem (ERFDS) furctice.irg.
4 Activate Nuclear Data Comrunications Syster (NDCS) terminal as per Emergency Procedure EF-7, "Activatioc of the Nuclear Data Connunications Syster."
i 5.
Contact data processor in the TS provide status of the SPDS syster and NDC terminal.
6.
Call the liaison coordinator in the TS ard inform that you are ready to receive plant data.
rrange 6r a telecopier check.
7.
Report status to the ACEO.
B.
Have a clerk distribute radiological and plant data sheets as they become available, using forms found in Emergency Procedure G-3.
Provide briefings to the AECO as needed.
9.
Have a clerk maintain plant, radiological and chronolooical status on status boards on West wall of operations off1ce.
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Page 1 of 1 c
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DEPAETHENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05, 1 AND 2 I_
TITLE:
EOF ACTIVATION CHECKLIST FOR THE INTERIM PUBLIC INFORMATION RECOVERY MANAGER (PIRM) i 1.-
Contact the Technical Advisor to the P!RM and have him brief you on emergency status. Begin preparation of a news bulletin as soon as sufficient information is available.
(Refer to Emergency Procedure OR-2,." Release of Information to the Public).
2.
Contact additional PGandE local public information personnel to assist if not already done.
3.
Establish communications with the county public inf,ormation org a ni z a t i or.,
4 Determine plans for cortacting the news media.
5.
Contact the corporate public information coordinator c' provide status and media contacs
. rs.
6.
Participate in media briefings as per Emergency Procedure OR-2.
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69-10781-6_.5/84 (25)
Page 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE:
EOF ACTIVATION CHECKLIST FOR THE TECHNICAL ADVISOR TO THE PIRM 1.
Contact and be briefed by the RERM and the OARM.
2.
Deterrine plant status.
3.
Contact the liaison coordinator in the TSC lc clarify details if necessary.
4 Assist PIRM in preparing news releases, contacting personnel, and supporting the. county news orgarization in news releases as per Energency Procedure OR.2, " Release of Information to the Putlic."
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69-10782 5/.84 (25)
Page 1 of 1 PAtlFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AN 2 TITLE:
AUX 1LIARY TRAILER CALL OUT LIST Call Out Instructions:
1.
Contact only one person.
2.
Contact first listed available person (preferred position holder); if unavailable, contact next available person, a.
A. G. CALLAHAN...................
COMPANY PHONE:
HOME PHONE b.
RON LARGE........................
COMPANY PHONE:
HOME PHONE
- c.
DON BURNER.......................
COMPANY PHONE:
i HOME PHONE
- d.
JIM (J.D.) LIEFER................
COMPANY PHONE:
HOME PHONE
- e.
RHONDA HART-N0REllus............. COMPANY PHONE:
HOME PHONE
- f.
STEVE STAAT......................
COMPANY PHONE:
HOME PHONE
- ALTERNATE ON-CALL SUPERVISOR
- CLASS ONE LICENSE HOLDER
f' 4;
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^h UNITED STATES
.[
'g NUCLEAR REGULATORY COMMISSION g
E WASHINGTON, D. C. 20555
%,,*...+[
June 25, 1984 i
50-275/323 Diablo Canyon 4
MEMORANDUM FOR: Chief, Document Management Branch, TIDC FROM:
Director, Division of Rules and Records, ADM
SUBJECT:
REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The Division of Rules and Records has reviewed the attached document and has determined that it may now be made publici available.
. /
- /
. M. Felton, Director r
'g'/[
ivision of Rules and Recor Office of Administration
Attachment:
As stated r
b t
a y.
,