ML20032A047
| ML20032A047 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/02/1981 |
| From: | Blackman L, Brunner E, Scott D COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20032A044 | List: |
| References | |
| PROC-811002-01, NUDOCS 8110280199 | |
| Download: ML20032A047 (15) | |
Text
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DAP 9-2 ORESDEN STATION PROCEDURE ROUTING Revision 11 PROCEDURELCOORDINATORNOT5FIED O
pff3 DarE Incex Nu=cer Unit M//IProcedure 67
'JJ "C d Revision No.
I Tit 1e
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Req'd. Compl. Date Record Retention Requirements:
Actice Item No.
1.
Is a Surveillance affected?
/VO (Submit DAP 11-2 pgs. 5 or 6)
Modification No.
2.
Is a Station Record Type being established?
No Draft Review:
a.
If "yes", specify record Deletion?
4/d retention requirements.
l Posted Procecure?
W (as per Tech. Spec. Sec.
Posted Location?
Ud 6.5, ANSI N45.2.9 App. A Typing Required?
I / eE 4 or DAP 2-3)
Index Change Requirec?
e.6 4 b.
If "yes", obtain record type g
number
_,(see R3 Coordinator) gh
- 1. l2lW
..,______________________________________O_r_ig_i_n_a_t_o_r_____________________________________________
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,7/3 Department Supervisor gn. Staff Supervisor Wf0 M/4 M/A
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Verifier
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Surveillance Coorcinator j/
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Protecures parc1/Fator Maint. Asst. Sup, Rac./Cnem/ Sup.
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Procecures Manager
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APPROVED INSERT:
TT 02 '81
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I hereby acknowledga receipt of the above.
(Sign and return this fom to the Procedures Manager.)
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CAP 9-2 PROCEDURE HISTORY Procedure h[). [/dd - G /
Rev. No.
N Description of Procedure Revision or of New Procedure
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Supportive References Fom 9-2B O
APPROVED OCT 02 '81 19 of 24 i
D.O.S.R.
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CAP 9-2
',O s^r:Tv tv^ue^rios aevisica i' (10 CFR 50 53)
Oces :his prececure/ revision cens:i:ute a enange :c crecedures as described in Safety Analvsis Eccor-?
l No Q()
Yes ( )
e r
9
[is a enange in :ne Technical lSoecificatien involved?
No ( )
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~5AFET( EV ALUATi CN : Answer One folicwing cuestions wi tn a "yes" er "no", and provide speci fic reascns justi fyir.g the decision:
1.
Is the pecbability of an occurrence, the consequence of an zeci-dent, er :r:al function of safety related equi;.T.ent, as previcusly evaluated its the Final Safety Analysis Reper:, increased?
Yes
)( No, because:
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2.
is the possibility for an-accident or :r.al function of a di fferent:
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A type than any previcusly evaluated in the Final Safe:y Analysis
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Report created?
Yes
)(No, because:
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3 is the.iargin of safety, as defined in the :: asis for any Tech-nical Specificatien, reduced?
Yes X No, because:
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p ANY Answer - Yes ()
r All Answers Ne f
Request anc receive Nuclear negutaccry cce=iss' "
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APPROVED authart:atsen ce change.
OLT 02 '81 Authoriza-ren acceivee ( )
D.O.S.R.
k
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- NOTE:
l ini:iate Prteccure Any answer check 2d "yes" l
Imcle-enta:icn l
should be recer:cd in the v
Performed 5y c.
L. 6 n..f u annual re::cr: to :he N.C.
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J Date TOPJ: c-20.
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EP IP O
100 - Station Group Directtr's Cuties 100-1 Supervision.of Emergencies, Drills and Exercises (Primary Responsibility - Station Director)
Bev.1 5/81 100-C1 Station Director - Checklist of Initial GSEP Responsibilities Rev.1 1 /81 100-C2 Operations Director - Checklist of Initial GSEP Responsibilities Rev. 1 1 /81 100-C3 Technical Director - Checklist of Initial GSEP Responsibilities Rev. 1 3/81 100-C4 Maintenance Director - Checklist of Initial GSEP Responsibilities Rev.1 3/81 100-CS Stores Director - Checklist of Initial GSEP Responsibilities Rev. 1 7 /81 100-C6 Administrative Director - Checklist of Initial GSEP Responsibilities Rev. 2 1 0/81 100-C7 Security Director - Checklist of Initial GSEP O
aesPoasidiiities nov. i i/8i 100-C8 Rad / Chem Director - Checklist of Initial GSEP Responsibilities Rev.1 1 /81 100-C9 Emergency Reports Checklist (Primary Responsibility - Operations Director)
Rev.1 3/81 100-C10 Record Of GSEP Activities Rev. 0 1/B1 100-C11 Environs Dinctor - Checklist of Initial GSEP Respom4h414 ties Rev. 0 7/81 O
oci021981 I
~
EPIP 100-C6 ADMINISTRATIVE DIRECTOR Revision 2 (Checklist of Initial GSEP Responsibilities)
October 1981 AV NOTE This cnecklist is provided solely for the convenience of the Admin-istrative Director.
It is not necessary to follow this checklist i-step by step.
Its completion is not required and its use is deter-mined by the Administrative Director.
I.
Coordinate with Station Directors and control access to the Technice? Support Center (TSC).
Restrict the number of personnel in the TSC to those with essential task.
II.
Verify that two communicators are dispatched to the Operational i
Support Center (0SC) and one additional communicator is dispatched to the Control Room.
l III.
Maintain a master log of major GSEP-related activities (dictaphone, stenographer, etc).
IV.
Assess the need for typists, telecopy operators and/or switch-board operators at the TSC and the Emergency Operations Facility l
(EOF).
I V.
Collect and compile completed Checklists of Initial GSEP Responsibilities and Records of GSEP Activities.
VI.
Identify manning relief requirements and ensure that an individual is a.ilable to call reliefs (reliefs for communicators, for TSC personnel, for OSC personnel and for other emergency crews).
VII.
Ensure that training schedules are established for Radiation Protection and Security courses as appropriate.
VIII.
Arrange for food and sleeping facilities for the on-site employees.
IX.
Record subsequent GSEP-related activities on Record of GSEP Activities (EPIP 100-C10)..
O APPROVED (D 02 '81 1 of 1IRNAL)
D.O.S.R.
DAP 9-2 DRESDEN STATION PROCEDURE ROUTING Revision 11 i
PROCEDURES COORDINATOR NOTIFIED S co G V M S1
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OATE Fincex Ndd6 r Unitd Procedure NN
'h Revision No.
E Tit 1e
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Reg'd. Compl. Date A N f Recor Retention Requirements:
Action Item No.
MO 1.
Is a Surveillance affected?
A/#
(Submit DAP 11-2 pgs. 5 or 6)
Modification No.
N 2.
Is a Station Record Type being established?
NO Draft Review:
a.
If "yes", specify record Deletion?
N retention requirements.
{
Posted Procecure?
vo A/.4-(as per Tech. Spec. Sec.
Posted Location?
Nu 6.5, ANSI N45.2.9 App. A Typing Required?
ws or DAP 2-3)
Index Change Requireci vm b.
If "yes"I,,Aobtain record type
/
I (see R3 Coordinator) number Y kWr$6 M...p 1.
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Verifier Sury ~i ance Coor nator 4.
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Protecuref Coor'olnator Mtaint-Asst u
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TRANSMITTAL RECEIPT er No.
,N APPROVED
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REMOVE:
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INSERT:
OCT 02 '81
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D.O.S.R.
I hereby acknowledge receipt of the above.
(O Signed Date (Sign and return this fann to the Procedures Manager.)
j F0P}19-2A 18 of 24 i
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OLP 9-2 Revision 11 O'
eRoceouRe ms=v EW CC 'h Rev 1
Procedure Description of Procedure Revision or of New Procedure hAiVLotev1$u<tblu Wm cy) Nod (t>yh b.
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2 Justification for New or Revised Procedure l
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Fonn 9-28 O
APPROVED OCT 02 '81 19 of 24 1
D.O.S.R.
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1 CAP 9~2 i
SAFETY EVAI.UATION P.evisica 11 O
Oces this pr:cacure/ revisica ccnsti tute a enange te orccedures as described in Safety Anaivsis 9.coce:7 Yes ( )
No M e
I is a enange in ene Tecnnical Soect ficaeion involved?
No (>[
i SAFETI EVALUATION: Answer tne folicwing questicas wi:n a "yes" cr "no", and prcvide specific reascns justifying the decision:
1 1.
Is the probability of an cecurrence, the ccesequence of an acci-dent, or malfunction of safety related equipment, as previously evaluated in the Final Safety Analysis Report, increased 7 Yes No, because:
g()h/tL44-it.A ^
i Is the possibility for an-accident or malfunction of a different 2.
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type than any previcusly eval ated in the Final Safety Analysis O
O Report created?
Yes No, because:
&m &
3 Is the margin of safety, as defined in the basis for any Tech-nical Spect ficacica, reduced 7 Yes
%' No, because; fh(/%bV
~Ab
, M-I All Answers no
)
Any Answer
- Yes ( )
e Reque.Sc anc reces vs Nuclear APPROVED
~
negulatory ccemission authori:ation for change.
OCT 02'81 D.O.S.R.
Authori:acien Rece. ed ( )
1 iv 4
a
- NOTE:
iniciate Prwccure y imcle-enestien (
Any answer checked "yes" t
should be reported in the dIA Performec-3y annual recort to the n.'ic.
YObY Date ro.m e-2c.
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l-23 of 24 p
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EPIP O
300 E!!ERGENCY MEASURES 300-1 Initial Notifications and GSEP Responses (Primary Responsibility - Station Director)
Bev. 2 3/81 300-C1 Nsileas AccidedReporting System Form (Primary Responsibility - Station Director)
Rev. 2 - 5/81 300-2 On-Going Emergency Communications (Primary Responsibility - Station Director) g.,, j 3/31 300-3 Assembly and Evacuation of Personnel (Primary Responsibility - Operations Director)
Rev.1 2/81 300-4 Emergency Cose 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 (Primary Responsibility - Operations Director)
R4v.1 10/80 300-6 Survey of Injured Personnel (Primary Responsibility - Rad / Chem Director)
Rev. 0 7/80 0
300-7 gersonnei Decontaminat4cn (nedicai -
Decontamination Area) (Primary Responsibility
- Rad / Chem Director)
Rev. 0 7/80
~
300-8 Post-Accident Sampling of Primary Containment Atmosphere (Primary Responsibility - Rad / Chem Director)
Rev. 1 10/80 300-9 Post-Accident Sampling of Reactor Coolant (Primary Responsibility - Rad / Chem Director)
Rev. 2 1 0/81 300-10 Post-Accident Sampling and Release Rate Detennination of Radioiodines and Particulates (Primary Responsibility e Rad / Chem Director)
Rev. 1 10/80 300-11 Post-Accident Noble Gas Release Rate Determination t
I (Primary Responsibility - Rad / Chem Director)
Rev. 1 10/80 300-12 Initiation of Environmental Monitor't.g 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 I
0
~
OCT 021981 I'L
I I
EPIP r
O 300 EMERGENCY MEASURES (Cont'd) 300-14 Estimation of Off-site Dose from an Unplanned Release of Radioactive Effluents (Primary Responsibility - Rad./ Chem. Director)
Rev. 0 7/80 i
300-15 Deployment of the Eberline SAM-2 Stabilized Assay Meter (Primary Responsibility - Rad./ Chem.
Director).
Rev.1 3/81 i
l i
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OCT 021981 lO l
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~
EPIP 300-9 POST-ACCIDENT SAMPLING 0F Revision 2 REACTOR COOLANT october 1981 (Primary Responsibility - Rad./ Chem. Director)
A.
PURPOSE This procedure outlines the steps necessary to obtain, prepare and isotopically analyze a reactor coolant sample corresponding to a Regulatory Guide 1.3 or 1.4 Release of Fission Products.
It is intended to be an interim procedure pending completion of major sampling modifications by January 1,1981.
B.
REFERENCES 1.
DCP 1100-39, Reactor Water Isotopic Analysis.
2.
D0P 1600-16, Post-Accident Sampling of the Primary Con-tainment Atmosphere and Reactor Water.
C.
PREREQUISITES 1.
Two portable carts with lead caves for transport of one 25.0 milliliter (ml) umple vial. One cart will be used l
to transport the sample within the Reactor Building and into the 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 Canter (OSC).
O 2.
Approximately 25.0 31 vial for sample collection.
l 3.
Set of tongs and remote handling tools for handling l'
the radioactive sample.
i-4.
High and low range dose rate instrumentation.
5.
Syringe and lambda pipettes with volumes down to 1.0 lambda (0.001 ml) for making sample dilutions.
6.
Eight film badges for use on the transport carts.
Four badges will be used on each :: art, one cn each side. The badges will be labeled to insure positive identification as to the cart and position on the cart where the badge is placed.
7.
A finger ring to be obtained from the Radiation Protection office before entering the Reactor Building for sampling.
8.
Small lead pig with handle for the transfer of the sample from one cart to the other, j
l.
APPROVED I
O OG 02'81
- 5 D.O.S.R.
[
EPIP 300-9 Revision 2 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 nomally habitable. The Radiation Protection Department should be contacted prior to entry into any area when such a release of fission products is suspected.
2.
Wear radiation dosimetry as recommended by the Radiation Protection Department.
3.
Wear protective clothing and respiratory protection as recommended by the Radiation Protection Department.
4.
Once properly outfitted (dosimeters, clothing, mask) and cleared for entry into the Reactor Building, con-tinuously MONITOR dose rates while approaching the area of sampling.
5.
Spend a minimum amount of time in the vicinity of the sampling point as dose rates are expec*ed to increase in this area.
6.
Handle sampling vial' with tongs or remote handling tool, the longer the better. Dose rates from a 5.0 cc sample could range up to 50 R/hr.
O 7.
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.
8.
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.
Samplin.;; of the reactor coolant is limited to three separate sample poirits.
If the Clean-up Demineralizer System is oper-ational, a sample can be taken from the clean-up filter inlet at the third floor sample hood in the Reactor Building.
If the Clean-up Demineralizer System is out of service, a sample can be taken from the recirculation sample line.
This sample point is also located at the third floor sample hood.
If the Reactor is depressurized and the previously mentioned sample points are not working, a sample may be taken from the Shutdown Cooling System, provided it is in service.
Its location is on the ground floor elevation in the Reactor Building near the accumulators and approximately twenty ' feet beyond and nearly AppRO g in iine witn tne second interiockca door providing access to Q
j the Reactor Building.
2 of 5 D.O.S.R-g
EPIP 300-9 Revision 2 2.
Sampling should be accomplished within 1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br />.
3.
Isotopic analysis of tha sample should La accomplished within 1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> of sampling.
4.
In the event that the elevator is out of service, a special lead pig has been prepared which can be hand carried up or down the stairs. This pig is stored in the cabinet underneath the Unit 2 reactor water sampling hood.
Use this method to return the sample to the Hot Lab only after dose estimates have been made based on the radiation field surrounding the closed pig with the sample inside.
If the projected exposure will be too great, notify the nSC by radio and return, leaving the sample in place n. che pig.
F.
PROCEDURE 1.
Sampling.
a.
When a large inventory of fission products is released from the fuel into the reactor coolant, it is necessary to sample the coolant to improve efforts to assess and control the course of an accident.
b.
When such a release is suspected, immediately prepare the items in Steps C.1. through 8. for sampling.
nU c.
The sample point to be used will be determined by Radiation Protection Management. Some knowledge of which systems are operational is needed at out-lined in Step E.1.
d.
Once the sampling location is detemined, contact the Radiation Protection Department for recommendations as to dosimetry, clothing and resniratory requirements to enter the Reactor Building ane also at the point of sampling.
e.
Enter the Reactor Building and MONITOR dose rates l
continuously to the point of sampling.
l NOTE 1
Consider alternate paths to the sampling location if needed.
For example, the third floor sample i
hood may be more readily access-l ible via the Turbine Building.
Radiation Protection Management l
will recommend an appropriate path to the selected sample point.
ET02'81 3 of 5 D.O.S.R.
f
a EPIP 300-9 Revision 2 C) f.
Minimize the time at the sample location by pre-planning your scmpling technique.
v g.
OPEN sample valves and collect 1 to 2 ml of the sample from the pre-selected location using the vial and tongs.
Do not fill the sample vial completely. MONITOR dose l
rates. CLOSE the sample valves.
I h.
Cap the sample vial and immediately place the sample into the small lead pig located within the lead brick shield or. the cart.
i.
Return to the Reactor Building Interlock and change into street clothes.
If the pathway to the elevator on the third floor of the Reactor Building is obstruct-ed, descend one level and procead to the ground level via the elevator on the unit not experiencing the accident.
J.
TRANSFER the sample and the small lead pig to the second cart located in the Interlock.
Return to the Hot Lab with the sample, k.
Have sampling equipment surveyed to help reduce the spread of contamination.
Q 2.
Samole preparation.
a.
Leave the sample container in the lead brick shield.
Expose only the top of the container long enough to withdraw app.roximately a 1.0 lambda sample.
b.
Deposit the sample in a 450 cc glass counting' bottle.
i Make appropriate rinses of the pipette into the count-j ing bottle.
c.
Fill the counting bottle to the shoulder with lab monobed water. The sample is now ready for isotopic analysis.
3.
Sample counting.
a.
Refer to DCP 1100-39 (see Reference 1) for guidelines on perfonning a reactor water isotopic analysis.
b.
If the sample should be too " hot" to analyze according l
to the guidelines of DCP 1100-39, make appropriate l
dilutions from the sample just prepared in Section l
F.2.
t O
APPROVED 4 of 5 D.O.S.R.
~
EPIP 300-9 Revision 2 g
c.
Analyze for as many nuclides as possible using one count.
U-G.
CHECKLISTS
)
i None.
H.
TECHNICAL SPECIrICATIONS REFERENCES None.
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APPROVED s of s (FINAU WT. 02'81 D.O.S.R.
4 I-r i.