ML20053E533
| ML20053E533 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/13/1982 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20053E527 | List: |
| References | |
| PROC-820513-01, NUDOCS 8206080499 | |
| Download: ML20053E533 (15) | |
Text
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'EP IP 200 - Emergency conditions 200-T1 Classification of GSEP Conditions (Primary Responsibility - Station Director)
Riar 1.'
3/85 200-T2 Table of I-131 Equivalents For The Principal Iodine Isotopes On A Reactor Core Rev. 0 7/80 200-1 Declaration of GSEP Condition For Gaseous and Liquid Effluent Releases (Primary Responsibility - Operations Director)
Rev. 0 7/80 200-2 Classification of an Incident Involving Hazardous Material (Primary Responsibility -
Station Director)
Rev. 0 7/80 200-3 Criticality Accident in a Special Nuclear Material Area (Primary Responsibility -
Operations Director)
Rev. 1 5/82 200-4 Fire Fighting (Primary Responsibility - Operations Director)
Rev. 2 f/82. -
200-5 Security Threat (Primary Respo.1sibility - Operations Director)
Rev. 0 7/80 200-6 Corrective Actions Following An Oil Spill (Primary Reyonsibility - Operations Director)
Rev.1 1 2 /81 200-7 Operation During Tornado or Sustained Wind Conditions (Primary Responsibility - Operations Director)
Bev.1 1/82 200-8 Operation During Earthquake Conditions (Primary Responsibility - Operations Director)
Rev. 0 7/80 200-9 Dresden Dam Failure Rev. 0 7/80 (Primary Responsibility - Operations Director) 200-10 Probable Maximum Flood of Unit 1 (Primary Responsibility - Operations, Director)
Hav. o 7/80 200 Probable Maximum Flood of Unit 2 and 3 (Primary Responsibility - Operations Director)
Hav. o 8/80 200-12 Area High Radiation (Primary Responsibility - Operations Director)
Rev. 0 7/80 200-13 High Airborne Activity (Primary Responsibility - Operations. Director)
Rev. 0 7/80 MAY 121982 L
I 8206080499'820528 PDR ADOCK 05000010 0
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'EP IP 1
200 - Emergency Conditions (cont'd) 200-14 High Radioactive Surface Contamination (Primary Responsibility - Operations Director)
Rev. 0 7/80
- 200-15 Emergency Procedure for Obstruction Lights (Primary Responsibility - Operations Director) g v. o 9/80 200-16 UNUSED.NWREIL..,.. _ _
200-17 UNUSED NUMBER 200-18 UNUSED NUMBER 200-19 Unit 1 Control Room Evacuation (Primary Responsibility - Operations Director)
Delete h/82 200-20 Control Room Evacuation / Safe Shutdown (Primarf Responsibility - Operatibns Director)
Rev.1 h/82
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EPIP 200-3 Revision 1 May 1982 CRITICALITY ACCIDENT IN A SPECIAL NUCLEAR MATERIAL AREA (Primary Responsibility - Operations Director)
A.
PURPOSE The purpose of this procedure is to outline necessary action in the event of a criticality accident in a Special Nuclear Material (SNM) area.
B.
REFERENCES
{
C.
PREREQUISITES None.
D.
PRECAUTIONS None.
E.
LIMITATIONS AND ACTIONS None.
F.
PROCEDURE
.1.
The following are designated pemanent SNM areas:
a.
Unit 1 Fuel Building including the trackway, fuel han-dling area and new fuel storage vault, b.
Unit 2/3 refueling floor 613' elevation.
c.
Unit 2 Reactor Building 517' elevation including the reactor trackway.
2.
Any outside or inside area can be designated a temporary SNM area if the following criter.ia are met:
a.
Approval to use the area has been granted by an 'ndi-vidual currently named on the SNM License.
b.
The Rad./ Chem. Supervisor is infomed of the location, c.
The area is equipped with a Radiation Monitor in com-
- pliance with 10 CFR 70.24.
d.
The area is posted in compliance with the Radiation gQND Control Standards.
N 17'87.
e.
An emergency procedure in compliance with the require-ments of 10 CFR 70.24 is prepared and approved.
D.O.SB-1 of 2
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m i i EPIP 200-3 Revision I ss 3.
Immediately evacuate the SNM area if a Radiation Monitor
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Alam is sounded.
Evacuation routes for each SNM area are as follows:
a.
Uni t 1 Fuel Buil_ ding.
3 South exit - turn left as you pass through the door and go to the north side of the calibration facility.
Bend down low while walking to obtain the maximum shielding from radiation.
3 North exit - turn left as you pass through the door and go to the access ' control area.
b.
The Reactor Euilding Uiit 2 517',and Unit 2/3 613' ele-vations.
Evacuate to the Assembly Area on the ground floor of the Unit 2/3 Turbine Building by the Unit 2 Feed Pumps.
If the alam sounds in the 613' elevation, evacuate the area through the closest ' door and descend by stairs to the 517' level. Go through the interlock doors and into the Turbine Building to the Assembly Area.
If the alam sounds on the 517' elevation, evacuate out the Unit 2 or Unit 3 interlock dcors and into the Tur-bine Building to the Assembly Area, 4.
Notify the Shif t Erigineer immediately that a Radiation Mon-itor has sounded.
5.
The Foreman of each work group in the area will make sure all personnel that were working in the area are accounted far and report this to the Shift Engineer.
6.
The Shif t Engineer will notify Radiation Protection, who will perfom radiation surveys.
N 7.
All personnel must remain in the Assembly Area until noti-fied by Radiation Prot'ection that it is safe to leave.
G. - CHECKLISTS No'ne.
H.
TECENICAL SPECIFICATIONS REFERENCES None.
APPROVED MAY 12.'82 2 of z terNAu D.O.S.R.
EPIP 300 EMERGENCY MEASURES 300-1 Initial Notifications and GSEP Responses (Primary Responsibility - Station Director) aav. 3.
.t/8r 300-C1 Micreadlocided55crting Systaa Form (Primary Responsibility - Station Director)
Reir ia, T/8t. -
300-1 On-Going Emergency Ccmmunications (Primary Responsibility - Station Director) ger, t 3/81 -
300-3 Assembly and Evacuation of Personnel (Primary Responsibility - Operations Director)
Ee'v. I h/82 '
300-4 Emergency Dose Limits and Radiological Controls Responsibility - Rad / Chem Director)(Primary for Rescue and Recovery Operations Rev. 0 7/80 300-5 Emergency Treatment of Injured Personnel (Primary Responsibility - Operations Director)
Eev 2 5/82 300-6 Survey of Injured Personnel (Primary Responsibility - Rad /Chen Director)
Rev. 0 7/80
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- 300-7 Personnel Decontamination (Medical -
Decontamination Area) (Primary Respcnsibility
- Rad / Chem Director)
Rev. 0 7/80 300-8 Post-Accident Sampling of Primary Containment Atmosphere (Primary Responsibility - Rad / Chem Director) aer, t 10/80-300-9.
Post-Accident Sampling of Reactor Coolant (Primary Responsibility - Rad / Chem Director)
Rev., 2' 10/8t '
300-10 Post-Accident Sampling and Release Rate Detemination of Radiciodines and Particulates (Prir.ary Responsibility - Rad / Chem Director) aav.1 10/80-300-11 Post-Accident Noble Gas Release Rate Detemination (Primary Responsibility - Rad / Chem Director)
Rey, f 10/80 300-12 Initiation of Envirorrental Monitoring Activities by the Rad./ Chem. Director (Primary Responsibility - Rad./ Chem. Director)
Rev. 0 7/80 300-13 Rad./ Chem. Technicians Actions at Hospital (Primary Responsibility - Rad./ Chem. Director)
Rev. 0 7/80 0
MAY121982 1
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EPIP 300 EMERGENCY MEASL'RES (Cont'd) 300-14 Estimation of Off-site Dose from an Unplanned Release of Radioactive Effluents (Primary Responsibility - Rad./Chec1. Director)
Rev. 0 7/80 300-15 Deployment of the Eberline SAM-2 Stabilized Assay Meter (Primary Responsibility - Rad./ Chem.
Director)
Ber 1 3/8t' i
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EPIP 300-5 Revision 2 l
EMERGENCY TREATMENT OF INJURED PERSONNEL May 1982 l
(Primary Responsibility-Operations Director)
A.
SCOPE This procedure describes the steps to be taken in the event se-vere injuries are sustained by an individual on the plant site.
B.
POLICY AND METHODS 1.
Upon notification of personnel injury, the Shift Engineer will take the following actions:
a.
Notify Radiation Protection giving the nature and num-ber of injuries, the location and the potential for con-tamination.
b.
Dispatch a Shif t Supervisor to the location of the in-jured to direct efforts in administering first aid and to coordinate for other assistance as may be required.
c.
Send additional personnel trained in first aid as re-quested by the Shift Supervisor at the scene.
d.
Arrange for local ambulance service, if required. -Co al City Emergency Squad.
e.
If injuries are mis:or and do not require immediate transportation to a medical facility, take injured to medical / decontamination area for decontamination and treatment.
f.
Notify the main gate security that an ambulance has been called.
g.
Dispatch a Radiatio'n Protection staff member to the main gate to meet and direct the ambulance to the loca-tion of the injured. Radiation Protection staff member is to brief the ambulance attendants on Radiation Pro-tection procedures and the use of film badges.
h.
Declare an Unusual Event if injury involves radiation and requires transpartation to an off site medical fa-cility for treatment.
i.
Notify the Station Director,
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j.
Notify St. Joseph Hospital or other hospitals as appli-cable of the number and nature of injuries. State whether or not the injured is contaminated.
NOTE APPROVED Personnel injuries involving con-MAY 12'82 1 of 3 D.O.S.R.
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EPIP 300-5 Revision 2 tamination or exposure will be han-died with the assistance of local doctors and St. Joseph Hospital.
Radiation Protection personnel will accompany contaminated person (s) to the hospital. Appropriate equip-ment and protective clothing to control the spread or contamina-tion and to contain contaminated material for return to the Station will be available at the hospital.
If notified, a Commonwealth Edison Medical Radiation Consultant will provide advice for the doctors and staff at the hospital to handle such an emergency.
k.
Assure that a member of the Radiation Protection Department accompanies all contaminated person (s) to the hospital.
l 1.
Arrange for a management person to accompany the injured to the medical facility, if deemed necessary.
NOTE The accompanying management person will stay with the injured as much as possible while at the medical facility and will keep the Station informed of events at the hospital relating to the injured person's or persons' treatment.
m.
Just before the injured are transported to the hospital, call the hospital again, verifying the number and nature of injuries and the possibility of contamination.
Notify the Operating Engineer or Personnel Administrator of n.
the injury, action taken and action anticipated. The Oper-ating Engineer and Personnel Administrator will detennine if appropriate action has been taken and/or planned.
NOTE The Operating Engineer or the Per-sonnel Administrator will notify the Southern Division Medical De-partment and the Southern Division Safety Advisor assigned to Dresden during regular business hours.
2.
The Shift Supervisor dispatched to the scene will take the following actions:
APPROVED W 12.'82 2 of 3 v.0.S.R.
EPIP 300-5 Revision 2 a.
If the injured is in a high radiation area, conduct rescue in accordance with applicab': radiation rescue and recovery procedures.
b.
Verify that Radiation Protection personnel monitor ex-posure of rescue teams and first aid personnel..
c.
Assure that personnel trained in first aid are assisting or directing the assistance to the injured.
d.
Detennine the nature and number of injuries and ass.ess I
the potential for contamination.
f Notify the Shift Engineer of the need for an ambulance e.
or other transportation.
f.
If injuries are minor and do not require immediate trans-portation to a medical facility, take injured to medical /
decontamination area for decontamination and treatment.
g.
Assure that the injured are surveyed for contamination by Radiation Protection personnel.
Inform the Shif t Engineer of the results of the survey.
h.
Direct efforts to transfer the injured t; the ambulance and brief the ambulance attendants on the status of the injured as known.
i.
Verify that a member of the Radiation Protection Depart-ment accompanies all contaminated person (s) to the hospital.
j.
Keep the Shift Engineer informed of the status of the injured and of efforts to treat and/or transfer him to the hospital.
C.
REFERENCE Supplement to I.E. Infonnation Notice No. 80-06.
. APPROVED
. gs 12.'82 3 of 3 LCINAU 0.0.S.R.
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EPIP 300 EMERGENCY MEASURES I
300-1 Initial Notifications and GSEP Responses (Primarf Responsibility - Station Director) 3av.: 3.
.1/82^
300-C1 NiicnaFllec5edieforting System Fom (Primary Responsibility - Station Director)-
Re%2N. f/81- "'
On-GoingEmergencyCommunicationY 300-2 (Primary Responsibility - Station Directer)
Rev.1 3 /81 300-3 Assembly and Evacuation of Personnel
~
' h/82' (Primary Responsibility - Operations Director)
Rev. 2 300-4 Emergency Dose Limits and Radiological Controls for Rescue and Recovery Operations (Primary Responsibility - Rad / Chem Director)
Rev. 0 7/80 300-5 Emergency Treatment of Injured Personnel (Primarf Responsibility - Operations Director) adv 2 5/82 '
300-6 Survey of Injured Personnel (Primary Responsibility - Rad / Chem Director)
Rev. 0 7/80
- 300-7 Personnel Cecontamination (Medical -
Decontamination Area) (Primary Responsibility
- Rad / Chem Director)
Rev. 0 7/80 300-8 Post-Accident Sampling of Primarf Containment Atmosphere (Primary Responsibility - Rad / Chem Director)
Rev'; F 5/82 300-9 Post-Accident Sampling of Reactor Coolant (Primarf Responsibility - Rad / Chem Director)
Rev. Z' 1 0/81-2 300-10 Post-Accident Sampling and Release Rate Detemination of Radiciodines and Particulates-(Primary Responsibility - Rad / Chem Director) aav.1 10/80-300-11 Post-Accident Noble Gas Release Rate Detemination (Primary Responsibility - Rad / Chem Dit ector)
Rev. f' 10/80 1 300-12 Initiation of Environmental Monitoring Activities by the Rad./ Chem. Director (Primary Responsibility - Rad./ Chem. Director)
~Rev. 0 7/80 300-13 Rad./ Chem. Technicians Actions at Hospital (Primary Responsibility - Rad./ Chem. Director)
Rev. 0 7/80 MAY 131982 h.__et-m_
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n EPIP 300 EMERGEllCY MEASURES (Cont'd) 300-14 Estimation of Off-site Dose from an Unplanned Release of Radioactive Effluents (Primary Respcnsibility - Rad./ Chem. Director)
Rev. 0 7/80 e
300-15 Deployment of the Eberline SAM-2 Stabilized Assay Meter (Prirary Responsibility - Rad./ Chem.
Director)
Rer' 1.-
3/81 4
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gay 131982 o
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i EPIP 300-8 Revision 2 POST-ACCIDENT SAMPLING 0F PRIMARY CONTAINMENT ATMOSPHERT (Primary Responsibility - Rad./ Chem. Director)
A.
PURPOSE The purpose of this procedure is to provide a back-up means of sampling and analyzing the primary containment atmosphere follow-ing a Regulatory Guide 1.3 or 1.4 Release of Fission Products.
This procedure should only be used if the containment air sam-pling portion of the High Radiation Sampling Systen is inoperative.
B.
REFERENCES 1.
DCP 1400-7, Reactor Off-Gas Isotopic Analysis.
2.
00P 1600-16, Post-Accident Sampling of the Primary Contain-ment Atmosphere and Reactor Water.
C.
PREREQUISITES 1.
Two portable transport carts with lead caves for transport of one vial of gas. One cart will be used to transport the sample within the Reactor Building and intt the Reactor Building Interlock. The second cart will be used to transport the sample from the Interlock to the Hot Lab.
Carts will be stored in specific locations as indicated in the Operational Support Center.
2.
One syringe with 20 cc minimum volume for purging sample line and one evacuated 7.0 cc vial.
3.
Set of tongs and remote handling tool for handling the radio-active gas sample.
4.
High and low range dose instrumentation.
5.
Syringe (0 to 5.0 cc) and needle for making sample dilutions.
6.
A stopwatch to assist in detennining decay corrections.
7.
Swagelok 1/8" tube fitting with needle attached.
8.
Small adjustable wrench to attach Swagelok fitting with needle and to remove cap normally on grab sampling tee.
9.
Eight film badges for use on the portable transport carts.
Four badges will be used on each cart, one on each side.
The badges will be labeled to insure positive identifica-tion as to the cart and position on the cart where the badge is placed.
APPROVED 1 of 4 D.O.S.R.
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EPIP 300-8 Revision 2 10.
A finger ring to be obtained from the Radiation Protection office prior to entry into the Reactor Building.
D.
PRECAUTIONS 1.
A Regulatory Guide 1.3 or 1.4 Release of Fission Products implies extremely high levels of radioactivity. Dose rates may be high enough to prohibit entry to many areas of the plant which are normally habitable.
The Radiation Protec-tion Department should be contacted prior to entry into any M
area when such a release of fission products is suspected.
2.
Wear radiation dosimetry, protective clothing and respira-tory equipment as recmmended by the Radiation Protection Depa rtment.
$N 3.
Once properly outfitted (dosimeters, clothing, mask) and cleared for entry into the Reactor Building, continuously MONITOR dose rates while approaching the area of sampling.
4.
Spend a minimum of time in the vicinity of the sample point as dose rates are expected to increase in this area.
5.
Handle sampling vial with tongs or remote handling tool; the longeg the tongs the better. Concentrations of noble gases to 10 uCi/cc can be expected. This is approximately two orders of magnitude greater than what we have ever experienced.
6.
To minimize the exposure of personnel, the Reactor Building should be entered from the unit which did NOT experience the accident. That is, if the accident occurred on Unit 2, enter from the Unit 3 side. Minimize time spent near the accumulator banks.
j 7.
During sample preparation, care should be taken to maximize the use of shielding and any tools or equipment which could reduce personnel exposure.
E.
LIMITATIONS AND ACTIONS 1.
Sampling of the primary containment atmosphere will be done at the suction to the containment Continuous Air Monitor (CAM) located on the main floor of the Reactor Building. However, if a Group li Isolation has occurred, the sample flow to the CAM is stoppeo and the CAM isolated. When sampling of the containment atmosphere is required, it will be necessary to check with Operations regarding a Group II Isolation and the ability to sample at the CAM.
If a Grouc II Isolation has occurred and it is necessary toltain a sHole, the isola-tion sianals Fa'n~}e_ bypassed oer 00P 1600-16 (see Reference 2).
Once the bypass signal is initiated fra the Control j)
Room, the CAM will restart and the sample flow will resume.
g 1jTl To conserve dose during sam ling, the isolation signal should s
be bypassed and the sample low initiated before entering 9.0.g,$.
the Reactor Building.
2 of 4
4 EPIP 300-8 Revision 2 2.
Also, if the unit has been experiencing leaks in systems inside the Drywell resulting in a super-saturated atmos-phere, the CM may not be in operation due to water-logging problems. The CM will then have to be turned on after entry and allowed to circulate the sample gas for 2 min-utes to insure a representative sample in the lines.
3.
Sampling should be accanplished within 1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br />.
4.
Isotopic analysis of the sample should be accomplished with-
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in 1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> of sampling.
F.
PROCEDURE 1.
Sampling.
a.
When a large inventory of fission products is released from the fuel into the coolant, the containment atmos-phere activity level may also rise. Because this ac-tivity may be discharged to the environment, it is nec-essary to identify and quantify the radioactive gas.
c b.
When a release of fission products of the magnitude men-tiened in Section A is suspected, immediately prepare the items in Steps C.I.through 10. for sampling.
c.
Contact the Radiation Protection Department for recom-mendations as to dosimetry, clothing and respiratory requirements to enter the Reactor Building and also at the point of sampling.
d.
Determine the capability of grabbing a sample at the suction to the containment CM as outlined in Step E.1.
When assured that no-Reactor Building Interlocks are pre-venting CM operation, enter the Reactor Building wi.th the sampling equipment and proceed to the point of sampling; MONITOR dose rates continuously.
e.
Minimize the time at the sample location by pre-plan-ning your sampling technique.
f.
If the CM is not in operation per the reasons in Step E.2, OPEN the manual Isolation Valves,. turn' on the CM and allow the gases to circulate for 2 minutes before sampling.
Continue making preparations for sampling while the drywell gas circulates.
g.
Remnve the cap on the grab sampling tee on the CM suction line.
h.
Prepare the 7.0 cc vial for sampling by removing the wax covering over. the septum.
S gO 3 of 4 0.0.g,
u.. s EPIP 300-8 Revision 2 i.
Attach sampling needle to the sample line. OPEN the sample valve. Using a syringe fitted with a septum, purge the line by piercing the septum with the needle and withdrawing the plunger on the syringe. Prcmptly remove the syringe and CLOSE the valve.
J.
Immediately puncture the sampling vial with the sampling needle. OPEN the sampling valve. Wait 5 seconds. CLOSE the valve. Remove the vial with tongs and place in the lead cave.
k.
Gather all sampling equipment and return to the Reactor Building Interlock, l.
In the Reactor Building Interlock, TRANSFER the sam-pling vial to the second portable transport cart for transport to the Hot Lab.
j m.
Survey equipment to avoid the spread of contamination.
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2.
Sample preparations.
i a.
Expose only the top of the sample container long enough to withdraw approximately 0.5 cc of gas.
b.
Make sample dilutions from the sampling vial as it sets in the lead cave. Follow the guidelines in DCP 1400-7.
(see Reference 1), Steps F.2. through 8., in preparing the sample for counting when dilutions are required.
c.
Note that several dilutions may be necessary before the appropriate analyzer " dead-time" requirements are met.
3.
Sample counting.
a.
Refer to DCP 1400-7 for guidelines on perfonning a noble gas isotopic analysis.
b.
Analyze for all seven noble gases on the first count.
G.
'CHECXLISTS None.
H.
TECHNICAL SPECIFICATIONS REFERENCES None.
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