ML20084A284
| ML20084A284 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/29/1984 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| PROC-840329-01, NUDOCS 8404240490 | |
| Download: ML20084A284 (49) | |
Text
... . -. . .-
h EP Index N '
EMERGENCY PLAN PROCEDURES JNDEX Paga 1 bt#q.
PEACH BOFKM UNITS 2 AND 3 0 8/
Review Rev. Revision sen Number Title Date No. Date EP-101 Classification of Emergencies 01/10/84 8 01/10/84
EP-104 Site Emergency Response R.A.KANKUS08/01/83 9 08/01/83
. EP-105 General Emergency Response 08/01/83 9 08/01/83 EP-110 Personnel Assembly and Accountability 06/20/83 1 06/20/83 EP-201 Technical Support Center (TSC)
Activation 08/01/83 6 08/01/83 EP-202 Operations Support Center (OSC) Activation 10/27/83 5 10/27/83 EP-203 Emergency Operations Facility (EDF) Activation 08/01/83 6 08/01/83
. . EP-205 Radiation Protection Team Activation 4 04/25/83
( ,
04/25/83 EP-205A Chemistry Sampling and '
Analysis Group 05/25/82 4 05/25/82 EP-205A Operation of Post Accident
.1 Sampling Station 11/29/83 4 11/29/83 EP-205A Obtaining Drywell Gas Sanples
- - .2 from Containment Atmosphere Dilution
'~
Cabinets 05/26/82 .0 05/26/82 l
l EP-205A Retrieving and Changing Sanple
.3 Filters and Cartridges from the Drywell Radiation Monitor During Emergencies 04/25/83 1 04/25/93 r
EP-205A Obtaining Drywell Gas Sanples
.4 from the Drywell Radiation Monitor Sanpling Station 05/25/82 0 05/25/82 EP-205A Obtaining Reactor Water Sanples ,
- 5
. from Sanple' Sinks Following Accident .
Conditions 05/25/82 ~0 05/25/82 EP-205A Obtaining Canal Discharge Water
.6 Sanples Following Radioactive Liquid
- t Releases After Accident Conditions 05/25/82 0 05/25/82 -
8404240490 040329
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- Paga 2
% LMD G NCY PLAN PHOCEDURES INDEX Rev. 39
- PEACH BOP 1m UNITS 2 AND 3 03/08/84
.7 Particulate Samples from the Main Stack and Roof Vents Following Accident Conditions 11/21/83 2 11/21/83 EP-205A Gbtaining Liquid Radwaste Samples .
.8 from Radwaste Sample Sink Following Accident Conditions 05/25/82 0 05/25/82 EP-205A Obtaining Sa g les from Condensate
.9 Sample Sink Pollowing Accident conditions 05/25/82 0 05/25/82 EP-205A Obtaining Off43as Samples from
.10. the Off-Gas Hydrogen Analyzer Pollowing Accident Conditions 05/25/82 0 05/25/82 EP-205A Sample Preparation and
.11 llandling of Highly Radioactive f.lquid Samples 02/29/84 2 _02/29/84
- EP-205A Sample Preparation and Handling
.12 _of Highly Radioactive Particulate Filters and Iodine Cartridges 01/10/84 3 01/10/84 EP-205A Sagle Preparation and Handling of _
.13 Highly Radioactive Gas Samples 02/29/84 2 02/29/84
- EP-205A Offsite Analysis of High-
.14 Activity Sagles 11/23/83- -0 11/23/83 EP-205A Guidelines for the Order of
.15 Analysis on Post-Accident Samples 02/29/84 0 02/29/84 *
~
EP-2058 'Radir.tlun Gurvey Groups .04/25/83 4 04/25/83 EP-205C Personnel Dosimetry Bionssay ~
and Respiratory Protection Group 04/08/82 2 04/08/82 EP-206 'OELETED DELETED EP-206A Fire Fighting Group 01/10/84 6 01/10/84 SP-2060 Damage Repair Group 05/31/83 3 _05/31/83 EP-207 Personnel Safety Team Activation 04/25/83 5 04/25/83 EP-207A Search and Rescue 04/13/83- 3 04/13/83 SP-2073 DELETED DELETED -
,_ EP Imiex 1:MSHGENCY PIAN PHOCEDURES INDEX g }9 ,
2 PEACH BOPIO4 UNITS 2 AND 3 03/08/84
- Review Rev. Revision Nu;ter Title Date No. Date EP-207C First Aid 02/29/84 4 02/29/84
- EP-207D INacuation Assembly Group 04/25/83 3 04/25/83 EP-207S Vehicle and Evacuee Control Procedure 08/01/83 2 08/01/83 ,'
EP-207F Vehicle Decontamination Procedure 05/31/83 1 05/31/83
. EP-208 Security Team 05/31/83 1 05/31/83
, EP-209 Telephone List For Emergency Use 12/23/82 6 12/23/82 EP-209 Dmiediate Notification Call List Appendix A 08/23/83 8 06/24/83 EP-209 0ELETED DELETED Appendix B ll if EP-209 Peach Bottom Station Supervision Appendix C ,
02/29/84 11 02/29/84
- 4 SP-209 on Site Emergency Team Leaders Appendix D-1 02/29/84 8 02/29/84
- EP-209 Radiation Protection Team Appendix D-2 03/08/84 12 03/08/84
- EP-209 Pire and Damage Team Appendix D-3 01/10/84 9 01/10/84 EP-209 . Personnel Safety Team Appendix >4 03/08/84- 12 03/08/84
- EP-209 Security Team
, Appendix D-5 03/08/84 7 03/08/84
- f[
l EP-209 Re-Entry and Recovery Team Appendix D-6 08/23/83 3 04/11/83 EP-209 . Technical Support Center Group Appendix o-7 03/08/84 11 03/08/84
- EP-209 _ Corporate Emergency Team Leaders and Appendix E Support Personnel 01/10/84 10 01/10/84 ,
, EP-209 U. S. Government Agencies Appendix P 08/23/83 5 06/24/83 EP-209 cmergency Management Agencies ".
Appendix G 08/23/83 3 04/11/83
+ n n , = - , , , . , -.r, - - - - - - - , . e , - -
SP Inuex N G:NCY PLAN PROCEDURSS INDEX Pags 4 Rev. 39
- PEACH BOP 1U4 UNITS 2 AND 3 03/08/84
- Review Rev. Revision Number Title Date No. Date EP-209 Company Consultants Appendix 11 01/10/84 8 01/10/84 EP-209 Pield Support Personnel Appendix I-l 03/08/84 13 03/08/84 * .,'
EP-209 Chemistry & Health Physics Contractor Appendix I-2 Call List 03/08/84 10 03/08/84
- EP-209 Nearby Public and Industrial Users Appendix J Of Downstream Waters 08/23/83 5 06/24/83 EP-209 Miscellaneous Appendix K 08/23/83 6 06/24/83 EP-209 Local PECo Piones Appendix L 03/08/84 5 03/08/84
- EP-209 0ELETMD DELETED Appendix M EP-209 Medical Support Groups Appendix N 08/23/83 6 06/24/83 EP-209 Staffing Augmentation - 60 Minute Appendix P Call Procedure 01/10/84 8 01/10/84 EP-210 Dose Assessment Team 04/25/83 0 04/25/83 BP-301 Operating the Evacuation Alarm and Pond Page System 12/23/82 1 12/23/82 L
EP-303 - Partial Plant Evacuation 06/20/83 ,2 06/20/83 l
l l
EP-304 0ELETED EP-305 Site Evacuation 06/21/83 5 06/21/83 i-EP-306 Evacuation of the Information Center 05/25/82 2 05/25/82 EP-307 Reception and Orientation of Support Personnel 04/12/82 0 04/12/82
. EP-311 Handling Personnel with Serious
- Injuries, Radioactive Contamination Exposure, or Excessive Radiation
[ 3 04/08/82 Exposure Emergency Director Functions 04/08/82 EP-312 Radioactive Liquid Release (Emergency Director Functions) 04/13/83 1 04/13/83 i
w u~a tMudENCY PLAN P10CEDURES INDEX Paga 5 Rev. 39
- PEACH IDMGM UNITS 2 AND 3 03/08/84
- Review Rev. Revision Number Title Date No. Date EP-313 Control of Thyroid Blocking (KI)
Tablets 04/08/82 0 04/08/82 EP-316 Cumulative Population Dose 3 05/31/83 Calculations 05/31/83 EP-317 Direct Recomendations to Ccunty Onergency Management and Civil Defense Agencies 05/31/83 2 05/31/83 EP-318 Liquid Release Dose Calculation Method for Intake Water at '
Lxunstream Facilities 04/13/83 1 04/13/83 EP-319 Liquid Release Dose Calculation Method for Fish 04/13/83 1 03/13/83 EP-320 Procedure for Leaking Chlorine 03/12/82 1 03/12/82 EP-325 use of the Containment Radiation Monitor to Estimate Release Source Term 06/09/82 0 06/09/82 EP-401 dntry for Emergency Repair and .
- operations 04/13/83 4 04/13/83 EP-500 Review and Revision of Emergency -
Plan (FE Appendix 0) 04/01/81 0 04/01/81 e
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' EP-205A.ll Pagn 1 of 3, Rev. 2 lb I
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C PHILADELPHIA ELECTRIC CCNPANY PEACH BorIO! UNITS 2 AND 7 ,
I i
! EP-205A.ll SAMPLE PREPARATION AND HANDLING OF HIGHLY RADIOACTIVE LICUID SAM PURPOSE: i
- The purpose of this peccedure is to provide some guidelines for consideration, during sangle preparation and handling of highly radioactive samples following accident conditions with major fuel damage.
CONTROLLED APPROYED COPY- l APPARARE: VOID PREVIOUS ISSUE DISTRIBUTION: Dt**
Appropriate Health Physics Survey Equipment
- Air Sampler (low voltans) if required g u . fgna m b . 6fc.
Respirator Protection Equipment if required SS - Ssv Anti-C Clothing if required Control Rs.
Station Super.
+ Appropriate Lead Shielding Office i Appropriate Microsyringes 14.4 ml off-Gas Vials with Septums i
l- Extremity Dosimetry , , .
l- 'g T
REFERENCES:
CA-2A' l- Ch-75A '
i HPA-7D PHBCAUTIONS:
i A. In all steps of this yshe, an ALAnh concept is marustory. This' procedure provides same philm in pre-planning for sangle prepara-tion (dilution) and analysis of highly radioactive liquid samples. In addition to reviewing this procedure, an AIARA' review of the sample preparation and analysis should be performed prior to beginning prep-aration and analysis. If an analysis is nest really needed or a lower dose method is possible to obtain the same data, do not perform the- ,
analysis.
B. At no time, may'NRC exposure limits (either airborne or body dose) be
- exceeded during the sample preparation and chemical analysis. If it appears that an overexposure could reasonably occur during sample l
L preparation or analysis g proceed without written NRC approval. ,
l' ' C. 3 should be placed in plastic begs prior to ganna isotopic yeis to prevent contamination of the counting equipment.
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. Paga 2 of 3, Rev. 2 D. Satples shall be counted on the closest possible shelf to the detector
( in order to obtain a dead time of less than 30% Sanples with greater than 30% dead time must be counted on a more distant shelf and/or diluted. In general, samples with dose rates less than 2 mReWhr ,
can be counted on the 3 cm shelf and sangles with dose rates greater
! than 2 mReWhr but less than 200 mReWhr can be counted on the 30 an ,
shelf.
j PROCEXXJRE: ,
,, 1. Obtain the survey data obtained when the sample was taken and trans-ported to the Chemical Lab. Brief Health Physics personnel on the same preparation and chemical analysis to be performed. Health Physics shall determine air sangling requirements.
i 1
i l' 2. Health Physics qualified personnel shall sonitor does rates during the sanple preparation and handling. Based on their analysis, stay times shall be determined. During sangle preparation and handling, extremity i
doses should be limiting. However, whole body exposure shall also be considered. Extremity dosimetric devices should be worn. An RWP should be assigned to this activity.
L l 3. Sanple preparation shall be done in a ventilation hood or other
! ventilated area where respiratory protection equipment is not requir-ed if possible. When possible sample analysis shall also be done in
- a ventilation hood or where other engineering controls (like portable (y
~
i HEPA/charocal vent. units) may be used.
- 4. Consider the use of tongs or other remote tooling during sanglo
- preparation and analysis. ,
- 5. Lead shielding shall be used, when handling or diluting reactor coolant. At a minimas, lead bricks stacked around the.sangle shall be used. A small gap between the top lead bricks may be made for
- the insertion of a microoyringe needle into the sample bottle. The amount of sample rc.oved and the dilution volume shall depend on the sangle dose rate. After removing a sample close the gap in the lead
- brick top to reduce dose rates. Monitor the dose to the hands during micropipeting.
- 6. Consider the use of more elaborate shielding during sanple prepare-tion if dose rates merit its use.
- 7. ,cr sangles greater than 200 mr/hr,'before actual sample preparation or ohmaical analysis is performed, a dry run using domin water should be made. An ALARA review should also be done. Based on these dry l runs and the AIARA review, changes to sample preparation and analysis procedures shielding or equipment shall be made to minimise exposure.
Health Physics and Chemistry Supervision shall also, review the possibility of not performing the sample preparation and analysis at all. . .
< .. ,or . _ n a 1, sis, re,er to CA-2,..
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EP-205A.ll Page 3 cf 3, Rev. 2
- 9. To calculate the samle volume for ganma isotopic analysis, divide the original sample volume by the dilution factor. Verify the cal-
{ culated sample volume with Chemistry Supervision prior to analysis.
- 10. Consideration shall be given to tha final disposition of the samples, the remainder of the coolant sample and the waste produced.
- 11. Sanples and the remainder of the coolant sample which are kept for l additional analysis shall be stored in an appropriate location based on their dose rate and Radiologica1 hazard.
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EP-205A.13 j , ,
- Page 1 of 3, Rev. 2
(
.:2 a r/sy j PHILADELPHIA IIDCIRIC CMPANY PEACl! BOPICM UNITS 2 AND 3 a
EP-205A.13 SAMPLC PREPARATION AND HANDLING OF HIGHLY RADIOACTIVE GAS SAMPLES l
PURPOSS:
The purpose of this procedure is to provide sane guidelines for consideration during sample preparation and handling of highly radioactive gas sanples
- follwing accident conditions with major fuel damage.
, APPAlWTUS:
+
l Appropriate Health Physics survey equipment CONTROLLED APPROVID COPY-l Air Saupler (low volume) if required VOID PREVIOUS ISSUE 2 Respirator protection equipment if required *Qi r*. .
Anti-C clothing if required DISTRIBUTION
- Appropriate lead shielding m,$ntabM.
Appropriate microsyringes S6 - SSV l
l
( 14.4 al off-gas vials with septums Extremity dosimetry REFEHENCES:
control Rs.
station Super.
Office _
CA-75A
- HPA-7D I
PleCAlff!ONS: ,
A. In all steps of this procedure, an ALARA concept is mandatory. This procedure provides scan philosophy in pre-planning for sangle prepara-tion (dilution) and analysis of highly radioactive gas sangles. In addition to reviewing this procedure, an AIARh review of the sanple preparation (dilution) method should be performed prior to beginning preparation and analysis. If an analysis is not really needed or a lower dose method is possible to obtain the same data, do not perform
'the analysis.
B. At no time may NRC exposure limits (either airborne or body dose) be
! ==w during the aanple preparation and analysis. If it appears that an overexposure could reasonably occur during- le preparation 1 or analysis DO NDP pid without written IEC .
Samples should be placed in plastic begs prior to giues isotopic l'
i C.
analysis to prevent contamination of the ocunting equipment. * ;
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- Pags 2 of 3, Rev. 2 i
D. Samples shall be counted on 'the closest possible shelf to the detector in order to obtain a dead time of < 30%. Samples with > 30% dead time must be counted on a more distant shelf and/or diluted. In general, samples with dose rates < 2 mrem /hr can be counted on the 3 cm shelf I and samples with dose rates > 2 mrem /hr but < 200 mrem /hr can be counted on the 30 cm shelf.
PHOCEDURE:
- 1. Obtain the survey data octained when the sample was taken and trans-ported to the chemical lab. Brief Health Physics personnel on the same preparation (dilution) if required and analysis to be performed.
Health Physics shall determine air sampling requirements.
- 2. Health Physics qualified personnel shall monitor dose rates during the sample preparation and analysis. Based on their analysis stay times shall be determined. During sample preparation and analysis, extremity doses should be limiting. However, whole body exposure shall also be considered. Extremity dosimetric devices shall be worn. An RWP should 1
be assigned to this activity.
- 3. Suggested sample dilution procedure for s ples > 200 mR/hrt
- a. Adjust the pressure in the off-gas vial to absmih ric pressure by inserting a microsyringe needle and allow the pressure to (w
equalize.
- b. Evaculate a new 14.4 ml off-gas vial with septum.
- c. Determine amount of dilution required. Based on this dilution, determine the amount (volume) of gas to remove from the hot off-gas vial. -
- d. Inject a volume of air with a microsyringe into the hot off-gas vial which is equal to voltne of gas to be removed for dilution.
- e. Mix the gas in the hot off-gas vial by punging the $crosyringe in and out.
- f. Set the microsyringe to the volume of gas to be removed from the j hot off-gas vial and remove the microsyrine.
1
- g. Inject the gas in the microsyringe to a new evaculated 14.4 ml off-gas vial.
- h. Measure the dose rate of the vial to determine if additional dilution is necessary.
l 1. Additional dilutions may be done by repeating Step 5.
- 4. Sanple dilution shall b; done in a ventilation hood or other venti-
- lated area where respiratory protection equipnent is not required, if possible.
~
- 5. Consider the use of tongs or other remote tooling if additional sample
' dilution is required. ,
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! , . . Paga 3 of 3, Rev. 2 ,
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( 6. Lead shielding shan be used, when handling samples > 200 mRenVhr. At a minimum, lead bricks stacked around the sample shall be used. A sman gap between the top lead bricks may be made for the insertion of a microsyringe needle into the sample bottle. Before removing a volume gas for dilution insert a microsyringe needle into the bottle to adjust i the bottle pressure to atmospheric. The amount of sa m le removed and
! .the dilution volume shan depend on the sample dose rate. Before re-
! noving a volume of gas from the vial, inject an equal amount of air to '
3 ca pensate for the volume removed. Mix well before removing sanple. {
' After removing a sample close the gap in the lead brick top to reduce ;
dose rates. Monitor the dose to the hands during micropipeting. ,
f 7. Consider the use of more elaborate shielding during sagle dilution if dose rates merit its use.
- 8. Before actual sa m le dilution is performed a dry run using air should be made. An AIARA review should also be done. Based on these dry runs and the ALAHA review changes to sanple dilution procedure shielding or ,
i equipnent shall be made to minimize exposure. Supervision shan also :
j review the possibility of not performing the sangle dilution and l analysis at all.
l
- 9. For H2 or 02 analysis, refer to CA-75A.
- 10. To calculate the sanple volume for gauna isotopic analysis, use
! the fonowing formula.
{
. y c = Vi x Vs l 14.4 + Vi .
Where Vc is the voltane to be input into the ocuputer as the sample voltane, Vi is the voltane of air injected (equal to the volume out>-
sequently removed for dilution, and vs is the original sample voltane.
. This formula must be used for each sucomesive dilution.' Verify the
- final Vc value with Chemistry Supervision. ,
- n. Consideration shall be given to the final disposition of the samples, the remainder of the gas sample and the waste produced.
- 12. Samples and the remainder of the gas sample which are kept for j
l additional analysis shan be stored in an appropriate location based
- on their dose rate and Radiological hasard.
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Pag 2 1 of 2, Rev. 0 GKB:c' b apw PHIIADELPHIA ELECTRIC ODMPANY PEACH BOI'IQ'i UNITS 2 AND 3 EP-205A.15 GUIDELINE ADR THE ORDER O? ANALYSIS ON POSP-ACCIDOTP SNiPLES PURPOSEi s The purpose of this procedure is to provide a, guideline for the order in which analysis should be performed in the event a sanple must be taken from the Post Accident Sampling Station (PASS) . CONTROLI,ED AFFROVE COPY-VOID PREVIOUS ISSUE REF N s I*
- DISTEIBUTION:
2 SA. 1 g EP-205A.13 Control Rs.
gg st.tm so...
Office CA-75A HPA-7D series
{ NOrd: This procedure provides a GUIDSLINE for the order of analysis on samples taken from the PASS System. Deviations from this guideline may be performed with the permission of Chemistry Supervision.
PIOCEDURE:
PARP A,
- 1. Gas sanples which need not be diluted for gansna isotopic analysis should be counted on the detectors prior to analysis by qas chromato-graphy for hydrogen and/or oxygen content according to CA-75A.
- 2. Gas sanples which must be diluted for gamma isotopic analysis should be analyzed for hydrogen and/or oxygen content prior to dilution and subsequent ganna isotopic analysis.
PART tl
- l. If the undiluted sample need not be diluted for gamna isotopic analysis, it should be counted on the detector prior to any sub-sequent analysis.
- 2. Undiluted liquid sangles may be analysed for boron, if desired, ty/
renoving 5 ml of the liquid and analysing according to CA-270.
Assuming proper concentration of boron in the renctor coolant, baron i analysis should be performed on a diluted (small volume) PASS sanple ,
(see Part C below).
~ -
- _= . - - . . _- - . . _ _ _ _ .- . . - --_ - _ _ . - ._
.. EP-205A.15
. Pag) 2 of 2, Rev. 0
- 3. A 0.2 ml aliquot of the remaining undiluted sample from Steps 1 or 2 above may be analyzed for pH according to CA-2A.
- 4. If cnloride analysis is desired, a separate undiluted PASS sample may be taken and sent to an off-site facility for subsequent analysis.
PARf C
- 1. If the diluted sample need not be further diluted for gamma isotopic analysis, it should be counted on the detector prior to any sub-sequent analysis. A boron analysis may then be performed on a 5 ml aliquot of the sample according to CA-27D.
I
- 2. If the diluted sample must be further diluted for gamma isotopic analysis, it should be analyzed for boron, if desired, using CA-270 prior to dilution and subsequent ganna isotopic analysis.
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w-4v,u Pag 3 1 cf 7, Rev. 4
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. CONTROLLED APPROVID COPY-VOID PREVIOUS ISSUE M MWN Ph9 1STRIBUTION: #* ,
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, EP-207C FIHST AID SS - SSV l Control Ra..
Station Super.
! Office __
i PURPOSE To define the actions of the Personnel Safety Team First Ai# i Scarch and Rescue Group regarding first aid.
REFERiiNCES ,
+
i i 1. Peach Bottom Atomic Power Station Emergency Plan i
Section Title 5.2.1.5.7 Personnel Safety Team j 6.9.2 Decontamination and First Aid p 7.1.10 First Aid and Medical Facilities l
- 2. NUREG 0654 Criteria for Preparation vad Evaluation I
, b of Radiological Smargenca Response Plans and Preparednes: in Support of Nuclear Power i
Plants.
l
- 3. EP-311 HandlingPersonnelwithSeriousInjuries,Radie active Contamination Exposure or Excessive Radiation ,
Exposure, Energency Director Functions.
I APPEGIX 1
> EP-2070-1 Injured Personnel Report Perm I EP-2010-2 First Aid Equipment Imoations in Power Block
- ACFIQ6 IEVEL
! The First Aid phase of the First Ai# Search and Rescue Grog l
+
will be activated whenever a personnel injury is classified as an
. Unusual Event and at any other emergency action level as determined !
by the Emergency Director. Also, EP 207A, Search and Rescue, shall -
- ,, be implamented in conjunction with this procedure.
- PRECWr!CNB '
1
. 1. Life-saving first aid treatment has priority crser !
decontamination or treatment for radiation exposure. . i
- 2. Minimise radiation exposure and avoid group member I
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. _ . _ . _ _ _ . - - - . . - - _ _ . . - _ _ ~ - . . _ _ _ . . _ . . . _ ..,_ ,._._ _ .._.. ~,_.. _ -. _ _ _ _ _
- . . -. - -_ .- - _ _ - . . - _ - - . _ - - - _ = - . . .- _ . -
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Pag 2 2 of 7, Rev. 4 l !
! contamination as mch as practical. .
j
( 3. If gross external contamination is found, internal '
4 contamination should be suspected.
- 4. Any material removed from a contaminated person shan be recovered and used for isotopic analysis. .
- 5. The First Aid / Search and Rescue Group Leader win l
' maintain contact with the Personnel Safety Team Leader i at the designated assembly area. .
I -
- 6. Objects causing contaminated wounds should be recovered or uneared for isotopic identification, if possible. ,
- 7. The Emergency Director win approve any team member exceeding Peach Bottom quarterly exposure limits.
j, 8. If First Aid Team is unable to move injured person, local antulance assistance mst be utilized.
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' I MEDIATE ACTIONS 1.0 Personnel Safety Team Leader sha n:
1.1 Assign members from the Personnel Safety Team at the designated aMy area to form First Ald/8earch and Rescue Group (s) . Each group shan consist of at least three members; f,
- f. one must be sultimedia qualified, one must be first aid
} qualified, and one must be a Health Physics Technician. All
!! should be familiar with the plant.
e i
1.2 Appoint the most qualified person of the group to be i the First Aid /Bearch and Rescue Group Leader and to carry .
out Section 2.0 of this procedure. ,
- 1.3 Obtain exposure limit from the Emergency Director for this activity. If subsequent first aid operations are l'
j, necessary, the Emergency Director will adjust the radiation
- exposure unit accordingly.
,6 1.4 If outside medical help is neccesary, request the Director to contact the noosemary help as descr in section 4.0 of this procedure.
1.5 Arrange for inventory and restock the first aid kits, if necessary. If the victim is transported to Narford Memorial, instruct the safety 'mut member aooanganying i*
i the victim to prepare a list of items used frcus the
. . radiation emergency equipmen ies which are kept at the hospital. The list forwarded to the
, site Radiation Management Corporation interface persos (currently the Respiratory Protection Coordinator). .
I' l.6 Make necessary cans (as per EP-209) to arrange for ambulance 3--- , ,., - _ . y.- - ,. _--. ,.. .-... w-, , ~ , , _ - . - . . - . , _ . . . ~ , -,,_y .-,.-s-.. ---e ,. . - - . _ - - - - . . _ . , . . - , . ~ . . . . , , _ , - - - . .
= - . . . . . ._
EP-207C i
Paga 3 of 7, Rev. 4 I -
or hospital services. . ,
i j
i
(. 2.0 First Aid / Search and Rescue Group Leader shall 2.1 Determine the extent of the injury and direct adminis-l tration of first aid. See attached Appendix EP-207C-2 i
for listing of first aid equignent location in the plant, i
Insure objects causing contaminated wounds are recovered or smeared for isotopic identification, if possible.-
l 2.2 Report to the Personnel Safety Team Leader the extent
! of the individual's injuries and roccumnend =_rin.tary medical actions as necessary (i.e., hospitalisation).
Complete Appendix EP 207C-1 (if possible) and attach to injured person prior to shipping in ambulance.
4 2.3 Direct the First Aid / Search and Rescue Group to transport l
the injured person to a site first aid facility, if practicable. ,
l Iccations:
! 1. Radweste Building, elevation 135'
- 2. Outside the security fence, along the fence just north of the circulation water pung house (Site Medical Dispensary) .
- i 3.0 First Aid / search and Rescue Group members shall -
i
(. 3.1 Adninister first aid, as necessary.
i NOTE: If contamination is suspected, survey the injured area. If contamination is found, go to step 3.4 i of this procedure. 3 l 3.2 Perform a radiation and contamination survey of the '
e . person and subsequently the area.
3.3 Transport the injured person to a Site First Aid Facility if practicable.
I 3.4 perform the following if contamination is suspected
!~ an the injured person.
3.4.1 Wear necessary anti-contamination clothing II
. PRRCT3CANA1 NOIE: W 'ns Duustr Is asVERE, DOEDINTE MIDICAL TRWmWNP IS OF THE NIGWrt PRIORITY AND
- anDerimcar. coprBota Ass ss2MoutY.
. 3.4.2 Administer appropriate first aid, being careful to limit the spread of contamination and limit .
( personal exposure.
90 .
- Pag] 4 cf 7, Rev. 4 3.4.3 Prepare the person for transportation by ,
covering the contaminated area with a protective
{ . wrap. This may require covering the stretcher and placing the person on the stretcher and wrapping the cover around the person or wrapping the injury in protective wrap. (Avoid excessive wrapping to prevent dehydration of the person).
3.4.4 Transport the injured person to the Site First Aid Facility for treatment by the Site Physician's Assistant or local physician.
NOIE: If the injured person is going to be transported to an offiste medical facility, it may not be feasible to bring the person to the First Aid Facility, instead move the person to a safe place which is easily accessible for the transfer to a vehicle, s 3.5 Recover any contaminated articles of clothing that may have been renoved frcan the perscn for isotopic analysis.
4.0 Site Physician's Assistant or his designes shall:
4.1 Provide guidance to the First Aid / Search and Rescue Group as much as practicable through the Personnel Safety Team Leader.
L 4.2 Prepare the Site Medical Dispensary or radwaste building (elev.135') first aid facility for receiving injured personnel.
4.3 Under direction of the Emergency Director call the following offsite agencies for assistance, as necessary:
(See EP 209, Appendix N for additional telephone numhers, if needed.
Ambulance Service:
C Delta-Cardiff (TelephoneFire No. and Ambulance Ccspany]
l Hospital-Contaminated Injured Personnels l r- Harford Memorial Hospital I L (Telephone No.
- Hospital-Injured Personnel-No Contamination York Hospital or Harford Hospital tore When contactirs offsite agencies, give them the following information.
a) Numberofinjuredpersons .
b) Estimated Time of Arrival (Hospitais only)
{ .. .
EP-207C Page 5 cf 7, Rev. 4 c) Nature of trauma C d) hhether individual (s) contaminated or not.
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Pag 3 6 cf 7, Rev. 4
Injured Person's Name Age . .
Harshaw Badge No. or .
Social Security No.
Male ramale Type and location of Injury Radioactive Contamination Yes No Level tocation Radiation Exposure Estimate
"(
Where did injury occur 4
Prepared by First Aid Group Leader 3 signature ,
Group Members 4
i l If practicable forward original, with the person, to the Site First Aid Facility or Hospital as appropriate.
l t
4
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EP-207C W Pag) 7 of 7, Rev. 4 APPENDIX EP-207C-2 ,
FIRST-AID REIATED EQJIPMENP IN POWER BIDCK First Aid Stretchers Kits Blankets Unit .2 Rx Bldg Elevator Stairwells 116' Elev X X X 135' Elev . X X X 165' Elev X X X 195' Elev X X X 234' Elev X X X Unit 3 Rx Bldg Elevator Stairwells 116' Elev X X X 135' Elev X X X 165' Elev X X X 195' Elev X X X 234' Elev X X X t
Turbine Bldg Elevator 116' Elev X 135' Elev X 150' Elev X 165' Elev X Turbine Bl&J Laundry acom 116' Elev X X X
,(
Radweste Bldg Medical /Decon Room 135' Elev X* X i Diesel Gen Bldg (Each Room) .
X 4
Emergency Cooling Tower X ,
2SU Switchgear Bldg X 350 Switchgest Bldg X
- 2 Orthopedic stretchers located here.
NOTE: 1/2 mile rays (emergency flashlights) are located just outside door to Unit 2 side of main control room in cabinet.
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EP-209 APPENDIX C - PEACH 30!'IU4 STATICN SUPERVISION g '=
Control Rs.
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Shif t Superintendent H. L.
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APPDCTX C l
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- APPENDIX D-1
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APPDOIX D-2 A
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EP-209 APPENDIX D-2 RADIATION PICIECTIN 'IEAM
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CONTROLLED APPROVHD COPY-3/2M :
VOID PRNVIOUS ISSUE
. DISTRIBUTION:DlO Radiation Protection eam Leader Hcrae Phone Ce trex33%337 ,h h -
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i Control h .- ,
N. Gazda Station Super.
Ottice Alternate Radiaticn 1 Protection Team Leader S. Nelson 1
i Those merrbers with (*) have emergency plan training and may be directed by shift supervision to serve as leader.
j Personnel who are trained in HP practices but not in the 1 emergency serve as augmentation forces, working under the
., direction of trained team leaders. ..
) f
.h Field Survey Group Leader l
l Mark Dedrich Alternate Field Survey Group Leader Steve Malin interim Field Survey Group Leaders (*) & Me:rbers L. Hewell T. Stone G. Smith -
t B. Shortes i
S. Schymanski J. Creedon Page N. Weissenrieder Page ,
R. Bicnli Page L.-.. _ ..- .. _ _ _ _ _ . - _ _ _-- - _ . _ _ - . - _ _ _ _ _ ,.m - . . - _ _ _ . . . . _ . - . _ _ _ _ _ _ _ . _ _ - - . _ _ _ _ _ - - _ - - - .
- ' EP-209
- APPaOIX D-2 Page 2 of 5, Rev. 12 a
J. Poteet Page B. Gostuy Page T. Taylcr Page l,
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Supple:nental Forces are available from Bartlett Nuclear Appendix. ,
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- ' EP-209 APPENDIX D-2 Page 3 of 5, Rev. 12 RADIATION PR7IECTION 'IEAM - CHEMISTRY SAMPLING G100P
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Engineer - Chemistry Home Phone Centrex i
Harry Watson %$.{v((.5.Qd;{ialg, TW. . ::?r
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Supplemental Forces are available from Rad Services Inc. Appendix I-2.
DOGIMETP3, BIOASSAY, RESPIRA'IQLY GOUP Hme Phone Centrex Leaders (*) ard Members -
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DOSE ASSESSMENT TEAM Leaders (*) and Meltbers Ha e Phone Centrex
- A. Hilsmeier l
- - *F. Crosse ,
i G. McCarty l
R. Smith J. Mayer . -
D. Rockwll r
i HEALTH PHYSICS DATA TAKERS FOR RADIATION PtOCu.nCN_
TEAM AND PERSCW EL SAFErY TEAM Chronister, J.D.
f Mareino, C.E.
.{ Tucker, E.K.
Sunday, M.N.
Bishop, R.N. f Volz, F.J.,Jr.
i Nixcm, R.D.
Freed, M.E.
l l Workinger, R.L.
l Shutt, L.M.
Arnold, D.M. .-
Wilson, E.N.
1 Kern, D.E. -
Schenning, R.M. -
- Hostetter, L.E. Jr. .
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Perry, A.R.
Ccraniskey, J.J.
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, EP-209
- APPmoIx o-2
, ,. Page 5 of 5, Rev. 12 l -
oeneen, T.L. Je.
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Shuler, M.E.
Pendleton, D.D. III i
Brcun, D. A.
Townsend, B.V. -
Waters, M.M.
Secretaries
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J. Miller - Jr. Stenographer A. Alneney Typist 1
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EP-209 APPD; DIX D-4 PERSCNNEL SAFEI'Y TEN 4 l
1 l
Personnel Safety Team Leader _
- Hane Phone Centrex R. W. MacAllester f
Alternate Personnel Safety Team Leaders Arthur Beward i
Interim Personnel Safety Team Leaders and Team Members S. I. Cohn L. R. Rhodes h W. A. Bradley I
W. T. Gleaves ,
D. E. Kauffman J. A. Barbour ,
J. M. Weaver The following people are team members but not Interim Team Leaders l
l W. M. Eajles, III l
R. C. Proctor B. E. Saxman T. A. Megashko D. G. Falcone W. C. Watsen ,
R. E. Rcxjers G. W. Tharpe l
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fbh.O O! , f_ ,h i'; *N Dick Sware sh... P.d.;...
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Alternate Search and Rescue /First Aid Group Leader Carl Koppenhaver Search and Rescue /First Aid Group Members George Menard Jerry Adams Phil Turturici James Morgan James Arnold David Grove -
' Patrick Welch Robert Bickhart John Sarsfield James Herrick Plant Survey Group Leader Hane Phone Centrex Steve Grosh T MN ~ ' ' ~ ' -
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Alternate Plant Survey Group Leader p .g,g:.g ig
( Glen Faden M M M N+g
EP-209 APPENDIX D-4 Page 3 of 4, Rev. 12 Plant Survey Group Members t,
i Tan Albright
- Craig Hoffmaster Joe Volz i Steve King ,'
i Ibdd Fleisch:rann i
Keith Gordon
- l. George Glessner i Detbie Perrine Robert Arters )
l
.j Frank Kovacs l i Dan Dreddy I Gary Fay John Nelson l Terry Reisinger i
! Tim Kirkpatrick I
l l Evacuation Assembly Area Group Leader Hane Phone Centrex I
I
, Bill Downey Alternate Evacuation Assembly Group Leader Ted Hoopes Evacuatico Asse:rbly Area Group Members
~
Alex Parducci ,,
Don Fay Jack Purcell .,
Dan Hines i
. EP-209 APPENDIX D-4 Page 4 of 4, Rev. 12 Rob McCoy 1-301-658-3840
( Health Physics Data Takers for Personnel Safety Team and Radiation Protection Team 1 J. D. Chronister C. E. Mareino 7 E. K. Tucker M. N. Surday R. N. Bishop f F. J. Volz, Jr.
R. D. Nixon M. E. Freed R. L. Workinger L. M. Shull l D. M. Arnold b E. N. Wilson ,
t D. E. Kern R. M. Schenning L. E. Hostetter, Jr.
A. R. Perry J. J. Ccmiskey T. L. Deneen, Jr.
M. E. Shuler D. D. Pendleton, III D. A. Brown B. V. Townsend [
M. M. Waters l
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' P of:tes IILADMSHIA ELTrrnT N TW aae djhQg PEACH B01'ICM UNITS 2 & 3 EP-209 APPENDIX D-5 SECL"dITY WAM
- l Security Team Leader Telephone No.
j S.Q. Tharpe (Security Supervisor) i
.- -f t l
l Alternates C.W. Myers (Capt. of the Guards) l K.L. Knouse (Training Lt.))
Security Team - Sergeants L.C. Kissinger L L.D. Smith Sr.
S.A. Spencer ,
W.F. Strauser A. R. Wyatt
[ t Assist. To PECo Security Supervisor Lt. J.C. Lewis I
Clerk D.S. Watkins l
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EP-209 APPENDIX D-5 Page 2 of 6, Rev. 7 S'ecurity Team Members - Guards Telephone No.
{
- 1. Altland, Eugene R.
- 2. Ashby, Dewey D.
- 3. Biggs, Jams Z. ,
- 4. Buckingham, Charles L. ,'
- 5. Dallas, Richard O.
- 6. Dennison, Robert L.
- 7. Edwards, Perrilee T.
- 8. Frazier, George H.
- 9. Hess, Martin R.
- 10. Hulshart, George R.
- 11. Hutton, William R.
- 12. Malucci, Paul C.
. ( 13. Merryman, Jeffrey B.
- 14. McLain, Lester S.
- 15. Morris, Lawrence A.
- 16. Murphy, Priscilla A.
- 17. O'Shell, Dcnald R.
'18. Salano, Jorge
- 19. Shaw, Louis L. -
- 20. Smith, Steven M. ,
- 21. Stewart, Ralph E.
- 22. Taylor, Roger L.
. 23. Warner, Bradley E.
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- 24. Williams, Urlo C.
- 25. Wilson Jr., James P.
( .
- EP-209 APPENDIX D-5 Page 3 of 6, Rev. 7 I .
Security Team Members - Watchoerson_ Telephone No.
- 1. Alban, Renee L.
l
- 2. Behm, Carl T.
- 3. Brennan, Joann K. .
i 4. Bristol, Kevin M. .
- 5. Brcun, Russell E.
- 6. Buckingham, William C.
- 7. Clay, Kathleen M.
- 8. Cosgrove, David L.
- 9. Dennison, Gregory L.
' 10. Dressler, Michael C.
- 11. Freeland, Ame L.
l
- 12. Halsted, Carol L.
b 13. Harrington, Julia M. .
- 14. Jordan, Darlene L.
- 15. Knight, Barbara A.
- 16. Kossiakoff, Donna A.
'17. Ledford, James C.
- 18. Major, Janes. D.
- 19. Morningstar, Robert L.
- 20. Parthree, Dianna D.
l
- 21. Risser Jr., Robert G.
1
- 22. Roberts, Linda M.
~
- 23. Robertson, Jeffrey L.
- 24. Searle Jr., Richard E.
- 25. Seguin, Rcxnano C.
- 26. Shaffer, Bot:by R.
- - - - - - _____ - __ - - - _ .__ _ -__ y
I EP-209 APPENDIX D-5 Paga 4 of 6, Rev. 7
- 27. Sipe, Steven P.
' C 28. Smith, Christopher A.
- 29. Smith Jr., Larry D.
- 30. Taylor, Dwayne D.
i i
- 31. Taylor, Jacalyn .
- 32. Testerman, Pauline H. ,
- 33. Whisner, Jean F.
- 34. Williamson, Denise M. '
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' APPENDIX D-5 Page 5 of 6, Rev. 7 I'
Secondary Alarm St. & Control Alarm St.
f b Attendants Telephone No. l l
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- 1. Armentrout, Treva C.
- 2. Baker, Paul N.
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- 3. Beal, Norma J. ,
- 4. Brooks, Kimberly A. -
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- 5. Casey, William L. l
- 6. Duh, Anita F. t r
- 7. Guilbault, Denise A. ,.
- 8. Haga Jr., Charels L. ,
- 9. Haga, Leisa
- 10. Runkl.e, Brian K.
- 11. McLaugh:in, Carol A. l
- 12. Williams, Teresa C.
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. APPDOIX D-5 Page 6 of 6, Rev. 7 Part Time Security Team Members - Guards Telechone No.
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- 1. Cantler, Ronald A. .
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- 2. Green, Robert A. ?
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- 3. Robinson, James H. p .,5 .;-j
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- 4. Johnson, Donald P. .a@. i ;-:-J o.l Ce
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- 5. Williams, Thcznas B.
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- EP-209 APPENDIX D-7
' Page 2 of 3, Rev. 11 l
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i l Reactor Engineer j
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A. J. Wasong tgg y Of 7 9.A.We . w v.M" .:A R r.3. o :. . . .s c < .; .. :..q z .w ; w ;n ;n ;.M.
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H. L. Watson 1 i N l? " E l*;,'..ic'% .i.:o' L p.M.,
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- 1. I Alternate C. S. Nelson . . gg.f g. p ;d.g y :y;.$; g Record Keeper and Contunicator l See EP-209 Appendix I-l for personnel to fill this positicm.
i Data Display Operator'3 - 2 required l Notify one of the five persons in the order listed below. The person .
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- 2. K. T. Voight - { [4
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', EP-209 APPENDIX D-7 i
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i i Secretaries 2 required Hane Centrex l
L. McCleary ,
L. Davis W. Felts i
T. Hutton ~
C. Brainerd
- S. Holgate ,
J. Hoopes '
J. Williams J. Wiley W
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E h EP-209 APPENDIX I-1 FIELD support p CONTROLLED APPROVID COPY-VOID PRSVIOUS ISS!;E Phcne 5I*
DISTRIBUTION:
J. T. Budzynski
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D. P. Helker Control Es.
Station Super.
C. E. Koppenhaver J. J. Yacyshyn ,
R. H. Wrighe
-4 J. G. Hufnagel P. L. Bushek M. S. Meckley C. N. Swenson G. A. John h
K. J. Goetz M. J. Lingenfelter K. May G. F. Verba
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K. R. Moser L. F. Vernacchio K. J. Bunch J. F. Kozilski K. A. Schoenk. % t D. L. Keene S. M. Hess - ,
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- - EP-209 APPENDIX Z-1 Page 2 of 3, Rev. 13 a ,
(~ l C. E. Watkins M. Coleman S. Herr D. Wheeler ', i I.
J. Bogen:: user ,
i D. Foss >
l j B. F. Maguire ,
j J. Capperella ,.
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l I J. Clupp j M. Zarroli ;
G T. Geyer C. Schell S. Rex J. J. M r.ormick, Jr. ,
C. S. Kerr W. C. Frederick M. J. Kelly G. Siefert , f M. Restaino l B. Geiger f l
P. Maguire !
J. Heyne ,
S. Gresh l
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.* APPDDIX I-l Paga 3 of 3, Rev. 13 l .
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J. Gallaher i
l M. S. Sattler T. Bluna l i '
I R. A. Brower -
J G. H. Gellrich J. E. Hessler, Jr.
S. J. Mannix F. F. Mascitelli G. Siefert
! S. L. Wcokey l 1 J. Troiano . .
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- . , APPENDIX I-2 Page 1 of 1, Rev. 10 D 3Clh A ., . Etnicib E 12s ) )~,,, 7 'Eb
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'3 Zf EP-209 APPENDIX I C1340rys%Nd HEAIdIN3Id A.WY CONT 30IL6 g p C W f LIST VOID PREVIOUS ISSUE DISTRIBUTION:
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4SS S5V. WA. .
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EP-209 APPENDIX L
--*4 ILCAL P!DCO PIDES t's a -d 3{ ,
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CONTROLLED APPROYED COPY- l Peach Bottom VOID PREVIOUS ISSUg '
DISTRIBUTION: I'- '
Switchboard: tr. rough rotatim '
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Control Re. I Station Super. l Catalytic Office ,
i Constructicn: i (Administration Building) .
Control Rran: (L.D. Emergency)
Information Center:
ISI Trailer:
NRC Office:
Rad Services:
Storeroom:
Susquehanna Test.
220 KV House: (Emergency) -
Utility Building:
{ Guard House l Others 1
Delta Office:
Delta Service Building (Day)
Claude Ya.e) ,
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--____,____--___--__----------,_-----n- ..,-----w-m* - -
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i > I PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 (zis) s41 so20 M J CQOP.E Y
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harch 20, 19E4 lie : Docket t.oc. 50-.77 50-278 Dr. T. E. Muridy, Administrator Region I Citice et Increction and EnforcETent U. S . liuclear Pe.;ulatory Cort.mi ccion 631 Park Avenue l'.ing of Fruccia, PA 194CC -
Dear Dr. Murley:
Enclosed are two copies of: additional revisions to thh' Peach B,ottom Atomic Power Station Emergency Plan Implementing Procedures. These procccurec are submitted,..within 30 days of the change, per regulations in 10 CFR 50, Appendix E, Section V.
The procedures being stytnitted are th6 following:
CP-205A. 11, Rev. 2 EP-209 App. D-2, Rev. 12 EP-205A. 13, Rev. 2 EP-209 App. D-4, Rev. 12 ,
EP-205A. 15, Rev. O EP-209 App. D-5, Rev. 7 EP-207C, Rev. 4 EP-209 App. D-7, Rev. 11
-EP-209 App C, Kev. 11 EP-20S App. 1-1, Rev. 13 EP-209 App. D-1, Rev. 8 EF-209 App. 1-2, Rev. 10 EP-209 App. L, Rev. 5
' Pursuant to Eection 2.7$0 of the Commis: ion's~
regulatibns, it is hereby requested that the telephone numbers anc addresses listed in precedures EP-207C,-page 4; EP-209, '
App, C; EP-209, App. D-1; EP-209, App. D-21-EP-209, App. D-4; ~
EP-209, App. D-5;,EP-209, App. D-7;bEP-209, App. I-1; EP-209, App. I-2; EP-209, App. L, beLwith' held from public disclosure, e,
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, - an affidavit retting forth the grounca in support of this recuest
- is attached hereto.
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T*.to copies have been sent under separate cover to the Document Control Desk.
Very truly yours, 5
i-
' Enclosure s.
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- Dccument Control Desk
! U.S. Nuclear. Regulatory Conmission
. Kashington, DC 20555
{ Site Inspector - Peach'Bettom t
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UNITED STATES NUCLEAR REGULATORY COMMISSION WA$HINGTON, D. C. 20555
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MEMORANDUM FOR: Chief, Document Management Branch, TIDC FROM: Director, Divistdn' of Rules and Records, ADM /
SUBJECT:
REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION TheDivisionofRulesandRecordshasrkviewed-theattacheddocument and has determined that it may now be made publicly available.
' / /
. M. Felton, Director t
ivision of Rules and Recor 'g',f, p Office of Administration :
Attachment:
As stated
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