ML20081B693
| ML20081B693 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 11/30/1983 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| PROC-831130-04, NUDOCS 8403090290 | |
| Download: ML20081B693 (80) | |
Text
I O Kugu, o UNITED STATES l 8 ' 't NUCLEAR REGULATORY COMMISSION !
- . $ WASHINGTON, D, C. 20555
%,...../
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 publicl available.
/Y
. M. Felton, Director ivision of Rules and Recor Office of Administration g/[
Attachment:
As stated jk 8403090290 831130 PDR ADOCK 05000352 F -PDR 9
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PHILADELPHIA ELECTRIC COMPANY
. 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 sHIELos L. DALTnoFF stsc're'ic Eion December 12, 1983 Re: Docket Nos. 50-352 50-353 Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Schwencer:
Enclosed are two copies of Limerick Generating Station Emergency Plan Implementing Procedures. These procedures are submitted per regulations in 10 CFR 50, Appendix E, Section V.
The procedures being submitted are the following:
EP-llO, Rev. O EP-307, Rev. 0 EP-208, Rev. O EP-312, Rev. O EP-221, Rev. O EP-313, Rev. O EP-251, Rev. O EP-318, Rev. O EP-252, Rev. O EP-319, Rev. O EP-304, Rev. O EP-401, Rev. 0 EP-305, Rev. O EP-500, Rev. O Pursuant to Section 2.790 of the Commission's regulations, it is hereby requested that the telephone numbers
, listed in procedures EP-252, EP-304, EP-305, EP-312 be withheld l from public disclosure. An affidavit setting forth the grounds in support of this request is attached hereto.
m=:2 ##f; ,
.' r Page 2 Mr. A. Schwencer Two copies have been sent under separate cover to the Document Control Desk.
Very truly yours, r >
4 9 Enc'losure cc: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 Site Inspector - Limerick Generating Station _
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l COMMONWEALTH OF PENNSYLVANIA :
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QUNTY OF PHILADELPHIA :
S. L. Daltrof f, being first duly sworn, deposes and states as follows:
- 1. He is Vice President of Philadelphia Electric Company (hereinaf ter referred to as the " Company"); he is authorized to execute this Af fidavit on behalf of the Ccmpany; and he has reviewed:
EP-252, Rev. O EP-305, Rev. O EP 304, Rev. O EP-312, Rev. O (hereinaf ter ref erred to as "the Documents" ), and knows the contents thereof.
- 2. The part of the Documents which are sought to be withheld f rom public disclosure is the listing of the home telephone numbers and home addresses of employees of the Company, direct-line work telephone numbers of employees of the Company which are not listed in public telephone directories, and home and work numbers of emergency response support personnel and.
organizations.
- 3. To the best of his knowledge, information and belief, the telephone numbers and addresses set forth in the
s Documents have been treated as confidential information and have been withheld f rom public disclosure by the Company.
4 .' The home telephone numbers and home addresses in the Documents should be considered by the Nuclear Regulatory Commission as confidential and proprietary information and be withheld from public disclosure on the grounds that disc'.osure of the home telephone numbers and home addresses of the employees of the Company and emergency support personnel could constitute an unwarranted invasion of the personal privacy of the individuals involved, disclosure of the work telephone numbers of the Company's employees and of the emergency response personnel and organizations could adversely af fect the capability of prompt notification in the event of an emergency; such disclosure is not required in the public interest; and such disclosure could adversely affect the interests of the Company and its ability to ef fectively implement the notification requirements of the Emergency Plan Procedures.
s f pC '
, il Subscribed and sworn to before me this IN day og Ds.w.ic z, l' M Ii
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To U
.l Notary Public JUDITH Y. FRANNUN
'i Notary Public. Phila.. Phila. Co.
3 My Commission Esowee Jufy 28.1987 j
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s EP-110 Rev. 0 Page 1 of 6 VA MP /mla
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/,, n/s/83 PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-110 PERSCNNEL ASSEMBLY AND ACCOUNTABILITY l 1.0 PURPOSE y The purpose of this procedure is to provide the steps
- s. i necessary when personnel assembly and accountability of PECo personnel and contractors is required when an Alert or partial plant evacuation is declared.
This procedure does not apply to Unit 2 Bechtel and sub-contractor personnel since they will be assembled per Bechtel procedures. -
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2.0 RESPONSIBILITIES 2.1 PECo personnel and contractors shall report to designated Emergency Assembly Areas for purposes of accountability.
2.2 Emergency Assembly Area Coordinators shall perform an accountability check of personnel at the designated area and report missing persons to
> Security.
2.3 Security shall assemble a list of missing persons for the Emergency Director.
2.4 The Emergency Director shall direct the Personnel Safety Team Leader to activate the Search and Rescue Group to locate missing personnel. ;
3.0 APPENDICES 3.1 EP-110-1, Emergency Assembly Areas 4.0 PREREQUISITES -
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None l 9,
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, . s EP-110 Rsv. 0 Page 2 of 6 VAV/ MPG /mla 5.0 SPECIAL EQUIPMENT None ,
6.0 SYMPTOMS -
None 7.O ACTION LEVEL This procedare should be implemented whenever an Alert is declared and may be executed when an Unusual Event is
, declared at the discretion of the Emergency Director.
b After a site evacuation is declared, this procedure no longer applies. ,
] 8.0 PRECAUTIONS 8.1 Only the following personnel may authorize support personnel without Limerick badges access to the site at an Alert, Site or General Emergency.
8.1.1 Site Emergency Coordinator 8.1.2 Emergency Director 8.1.3 Security Team Leader 9.0 PROCEDURE ,
i 9.1 IMMEDIATE ACTIONS
! 9 .1.' l PECO PERSONNEL AND CONTRACTORS shall:
9.1.1.1 ' Report to the area designated in Appendix EP-110-1, Emergen.cy Assembly Areas, when l the announcement for personnel assembly -
occurs. .
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, . s EP-110 Rov. O Page 3 of 6 VAV/ MPG /mla 1
- 1 9.1.1.2 Check themselves for contamination if j leaving a radiologically controlled area.
If contaminated, contact Health Physics at the Operations Eupport Center.
9.1.1.3 Report to the Emergency Assembly Area Coordinator for ourpose of -
accountability.
1 9.1.1.4 Await further instructions from the Emergency Assembly Area Coordinator.
9.1.2 EMERGENCY AREA ASSEMBLY COORDINATORS shall:
9.1.2.1 Perform accountability of personnel. If personnel are unaccounted for, check with the Technical Support Center first for those in your group who may have reported to the Technical Support Center.for emergency response roles. -
9.1.2.2 Report to Security the names of those identified as missing, if any. If possible, report the last known location of the missing persons.
9.1.2.3 Await f urther instructions from the Emergency Director.
9.1.3 Security shall:
9.1.3.1 Contact the Emergency Assembly Areas that have not reported in within 15-30 minutes after the assembly announcement is made.
l 9.1.3.2 Inform Emergency Director or Interim Emergency Director of 'he t accountability status within 30 minutes after the assembly innouncement is made.
9.1.3.3 Suspend access to the protected area except for those involved in Emergency Response Teams until accountability check I is completed. , ,
1 9.2 FOLLOW-UP ACTIONS 9.2.1 Emergency Director'or Interim Energency Director shall:
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Page 4 of VAV/ MPG /mla 9.2.1.1 Contact the Personnel Safety Team Leader to activate the Search and Rescue Group if required to locate missing personnel.
9.2.1.2 Contact the Personnel Safety Team Leader for status updates.
REPSRENCES 1.0 Limerick Generating Station Emergency Plan 9 9 e
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EP-110 Rev.
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APPENDIX EP-110-1 , ,
DIERGENCY ASSEMBLY AREAS h
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PRIMARY ASSEMBLY AREAS ALTERNATE ASSEMBLY AREAS l
GROUP AND TELEPHONE NUMBERS AND TELEPilONE NUMBERS ASSEMBLY. AREA COORD'INATOR(S)
Technical Support Center None Emergency Director Technical Support Personnel Sa fety Team Leader Center Sta f f : Display Area Ext.
HP Technicians Operations Ad min. Bldg. Senior HP TA/ Technician Support Center 2ND Floor, IIP &C Area Ext. - Ext.
'Picnt Operators Operations Support Control Room Senior Ranking Ext. P.O., A.P.O., or A.O.
Auxiliary Plant Center Operators Ext.
Admin Guard Station None Security Assistant
- Security Guards Alt
- Captain of the Guard Ex t.
Normal Workinq Of fice None Supervisors Bechtel or Subcontractors in Restricted
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-110 Pav. 0 Jage 6 of E-VAV/ MPG /mla#
APPENDIX EP-110-1
- EMERGENCY ASSEMBLY AREAS PRIMARY ASSEMBLY AREAS ALTERNATE ASSEMBLY AREAS -
. GROUP AND TELEPHONE NUMBERS AND TELEPilONE NUMBERS ASSEMBLY AREA COORDINATOR (S)
- ontrol Operators Control Room Safe Shutdown Panels Shift Superintendent coit. Control Ext. For Units 1 and 2 Alt
- Shift Superviisor berators hift Supervision (Only if Control Room
'tu -
not habitable) heuictry Cold Lab 217' El. 2nd Floor Main Supervisory Chemist or
'schnicians Bldg. Chemistry Office Chemist Ext. .
. ECO Field Engineers Field Eng. Office None Senior PECO Supervisory '
j scorted Plant Gate 3 None Senior Ranking PECO Escort
'i nitrirs 1.inistrative Normal Working Office None Mmin. Engineer or Ea ff and Unescorted in Main Bldg. or Alternate Senior Engineer loitors
- Individual Supervisors in the Main Bldg. or (nnex report unaccounted for personnel to tho Main Engineer or Alternate) 4 ,
EP-221 Rev. O Page 1 of 4 VAW/ G/mla
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Q PHILADELPHIA ELECTRIC COMPANY .
LIMERICK GENERATING STATION EMERGENCY PIAN IMPLEMENTING PROCEDURE
. I EP-221 PERSCNNEL DOSIMETRY, BIOASSAY, AND RESPIRATORY PROTECTION GROUP 1.0 PURPOSE The purpose of this procedure is to provide guidelines for
, the actions of the Personnel Dosimetry, Bioassay and Respiratory Protection Group.
2.0 RESPONSIBILITIES .
2.1 The Personnel Dosimetry, Bioassay and Respir'atory Protection Group Leader shall direct the issuance of emergency dosimetry, respiratory protective equipment
_ and direct the bioassay program by performing the necessary steps in this procedure.
3.O APPENDICES None .
4.0 PREREQUISITES None 5.0 SPECIAL EQdIPMENT None
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EP-221 Rev. O Page 2 of 4 VAW/ MPG /ala 6.0 SYMPTOMS None I
7.0 ACTION LEVEL The Personnel Dosimetry, Bioassay, and Respiratory Protection Group shall be activated during an emergency whenever there is a need for issuing dosimetry, respiratory protective devices or for bioassay monitoring as datermined by the Radiation Protection Team Leader.
)
8.0 PRECAUTIONS None 9.0 PROCEDURE 9.1 Ir. mediate Actions
- 9.1.1 Personnel Dosimetry, Bioassay, and Respiratory Protaction Group Leader shall:
9.1.1.1 Report to the TSC and discuss the sit'uation with the Radiation Protection Team Leader.
WHEN LEAVING THE RESTRICTED AREA, PERSONNEL
~ REMAINING ON SITE SHALL CARD OR SIGN OUT (IF THE SECURITY COMPT 7FER IS NOT AVAILABLE) BtFr KEEP DOSIMETRY. ,
9.1.1.2 Assemb'le the necessary personnel in the Whole Body Counting Room in the TSC for a briefing of the situation.
9.1.1.3 Direct the group to perform the.following tasks as necessary.
9.1.1.4 Emergency Dosimetry Issuance A. Take the emergency dosimetry devices from storage to the Personnel Entry Area at the TSC.
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. B. Coordinate with Security, issuing dosimetry to emergency team personnel and off-site emergency response teams (i.e., ambulance crews, fire-fighting crews, etc.). in'accordance with Health Physics Procedures.,
C. Maintain a list of the personnel to whom dosimetric devic'es are distributed in accordance with Health Physics Procedures.
9.1.1.5 Personnel Bioassay A. Verify that the Whole Body Counter is operational and calibrated. If need be, follow Health Physics Procedures to start up and calibrate the system.
B. Verify that a supply of bion.ssay specimen containers is on hand., Obtain more containers from the storeroom if needed.
C. Perform Whole Body Counts or collect bioassay samples from these individuals
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who are directed to report by the Radiation Protection Leader. .
MONITOR BACKGROUND RADIATION LEVELS IN * '
THE WHOLE BODY COUNTER AREA. IF DOSE RATE EXCEEDS (LATER) MR/HR, THE COUNTER CANNOT BE USED.
D. Have all personnel entering the Whole Body Counter Roca perform a thorou,gh
. frisk. If contamination greater than or:
equal to 500 cpm above background is found, have the person report to the Personnel Decon Area at the Radwaste Enclosure 217' or at the Technical g Support Center. Contamination less than 500 cpm above background will be reduced to acceptable levels in the Whole Body Counter Room showerbefore entering the
,, Whole Body Counter.
9.1.1.6 Respiratory Protegtion A. Perform-quantitative fit tests as needed.
EP-221 Rsv. O
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, VAW/ MPG /mla B. Distributa respiratory protective equipment in accordance with Health Physics Procedures.
9.2 Follow-up Actions 9.2.1 Personnel Dosimetry, Bi.oassay, and Respiratory Protection Group shall:
9.2.1.1 Emergency Dosimetry Issuance A. Establish a dosimetric device collection station in the TSC Guard House.
B. Arrange to have dosimetric devices processed in accordance with Health Physics Procedures.
9.2.1.2 Personnel Bioassay A. Have the bioassay samples analyzed.
B. Compare the results of the bioassay analysis with the most recent analysis performed on the person (if available) prior to the emergency. If internal contamination is identified, notify the Radiation Protection Team Leader of the situation.
9.2.1.3 Respiratory Protection A. Recover respiratory equipment and process for re-use in accordance with Health Physics Procedures, as the
, situation permits. ,
9.'2.1.4 Report' status and results to the Radiation Protection Team Leader.
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10.0 REFERENCES
10.1 Limerick Generating Station' Emergency Plan 10.2 NUREG 0654 Criteria for Pr'eparation and Evaluation of Rev. 1 Radio?ogical Emergency Response Plans in Suppo t of Nuclear Power Plants.
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EP-208 Rev. O
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"l40 LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-208 SECURITY TEAM ACTIVATION
'l . 0 PURPOSE The purpose of this procedure is to provide guidelines for the activation and conduct of operation for the Security Team, a
2.0 RESPONSIBILITIES 4
2.1 The Guard Sergeant or alternate shall assume the role of the Interim Security Team Leader and perform the steps of this procedure until relieved by the Security t
Team Leader.
2.2 The Security Team Leader shall relieve the Interim Security Team Leader and perform the steps of this procedure not completed by the Interim Security Team Leader.
3.0 APPENDICES
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3.1 Appendix EP-208-1 Access Control Group Location f
4.0 PPJ!: REQUISITES None ,
i 5.0 SPECIAL EQUIPMENT None ,
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6.0 SYMPTOMS Mone
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EP-208 Rev. O Page 2 of 6 VAW/ MPG /rgs j: 7.0 ACTION LEVEL
- This procedure shall be implemented when an Alert or higher classification is declared, a site evacuation is declared or at the discretion of the (Interim) Emergency Director.
8.0 PRECAUTIONS None 1
9.0 PROCEDURE 9.1 Immediate Actions 9.1.1 The Guard Sergeant shall:
9.1.1.1 Assume the role of the Interim Security Team Leader.
9.1.1.2 Call the Security Team Leader and team members using EP-278 Security Team Phone -
List, if necessary.
9.1.1.3 Assign available personnel to functional groups as necessary and direct them to perform the appropriate sections of this procedure.
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A. Access Control Group (9.2.2)
B. Personnel Accountability Group (9.2.3)
C. Plant Security Group (9.2.4) 9.2 Follow-Up Actions l
9.2.L The Security Team Leader shall:
9.2.1.1 Report to the Technical Support Center.
9.2.1.2 Review the current status of the emergency and relieve the Interim Security Lesder. -
9.2.1.3 Ensure that the necessary groups are staffed and performing the appropriate sections of this procedure. Augment groups as necessary.
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EP-208 Rev. O l Page 3 of 6
, VAW/ MPG /rgs 9.2.1.4 Advise the (Interim) Emergency Director concerning the need for off-site security personnel, if necessary. Use EP-278 Security Team Phone List for these off-site agencies.
9.2.1.5 Coordinate the actions of off-site security team personnel if their assistance is required.
9.2.1.6 Have a log maintained throughout the incident.
9.2.1.7 Keep the (Interim) Emergency Director updated on status of the team's activities.
9.2.2 The Access Control Droup shall:
9.2.2.1 Station a guard at each of the following locations to limit access to the plant when an alert or higher event is declared and a site evacuation is not needed unless the access point is locked:
A. Technical Support Center Personnel Exit Area B. Admin Guard Station Personnel Exit Area C. Main Access Gate (Gate 1)
D. Back Access Gate (Post 10) 9.2.2.2 When a site evacuation-is declared, station a guard at the following locations per EP-254 Vehicle and Evacuee Control Group to 1
limit access and to direct traffic flow.
See Appendix EP-208-1 for map locations. ;
l A. Technical Support Center Personnel Exit I Area B. Admin Guard Station Personnel Exit Area C. North Parking Lot '
D. Post #3 E. Main Access Gate (Gate 1)
F. Gate #2 G. Back Access Gate (Post 10) s
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EP-208 Rev. O Page 4 of 6 VAW/ MPG /rgs I 9.2.2.3 When a site evacuation is declared, the guards posted at the Technical Support Center and Admin Guard Station Personnel Exit Area shall direct personnel to deposit security badges in the buckets provided but I
to keep dosimetry. If the security computer is not operable, compile a list of the badge numbers of those evacuating as they are leaving.
9.2.3 The Personnel Accountability Group shall:
9.2.3.1 In the event of a site evacuation:
A. Obtain the security badges or badge list if the computer is not operable of evacuated personnel from the Access
. Control Group.
B. If the security computer is operable,
' card out' all of the security badges i
and compile a list of personnel that are onsite.
C. If the security computer is not operable, determine the personnel onsite. A suggested method is by crossing out all those badge numbers on the evacuee list and badges not in use from the master badge list and visitor's list.
D. Determine from the guards stationed at '
the North Parking Lot and Post #3 if any Bechtel/ Subcontractor personnel are unaccounted for.
E. Compile a list of Bechtel/ Subcontractor personnel missing and a list of all those in the protected area from steps B
. or C. Inform the (Intaria) Emergency Director of unaccounted for personnel.so that EP-252 Search and Rescue /First Aid can be implemented. -
l F. Forward the list of unaccounted personnel to the Personnel Safety Team Leader.
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,' s EP-208 Rev. O Page 5 of 6 VAW/ MPG /rgs 9.2.3.2 When personnel are assembled in cecordance with EP-llo Personnel Assembly and Accountability and with Bechtel Project Evacuation procedure, check with the Emergency Area Coordinators and security at the North Parking Lot and- Post #3 15-30 minutes af ter assembly was called for any unaccounted for personnel and compile a list for the Personnel Safety Team Leader.
9.2.4 The Plant Security Group shall i 9.2.4.1 Maintain plant security in accordance with emergency security procedures, and as directed by the (Interim) Emergency Director.
9.2.4.2 In the event of a Partial Plant Evacuation, assist personnel in the evacuation of affected areas.
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10.0 REFERENCES
10.1 Limerick Generation Station Emergency Plan 10.2 Limerick Generating Station Security Plan and Procedures 10.3 EP-278 Security Team Phone List 10.4 EP-254 Vehicle and Evacuee Control Group i
10.5 EP-110 Personnel Assembly and Accountability l
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. . J EP-208 Rev. O Page 6 of 6
- VAW/ MPG /rgs i
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. BACK { LONGVIEW
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ACCESS ROAD
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APPENDIX EP-208-I LOCATION OF ACCESS CONTROL POINTS l
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. v MPANY ION PHILADELPHIA ELECTRIC COLIM sMERGENCY PLAN IMPLEMENTING sp.251 Flawr sunvsY GROUP _ -
PURPOSE i s to provide guidelines for 1.0 The purpose of this procedureof -the Plant Survey Group. .
the actions RESPONSIBILITIES. l be responsible to 2.0 ds by performing the 2.1 The Plant Survey Group leader shaldirect the steps in this procedure. be responsible to l t Survey Group 2.2 The Plant Survey Group Squads shallcondu leader. .
3.O APPENDICES _ lines EP-251-L Emergency Exposure Guide .
3.1 r
4.0 PREREQUISITES _
. None a
- 5.0 SPECIAL EQUIPMENT _
Plant survey Kit
- e 6.0 STMPTOMS_
eW pP None .
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i EP-251 Rev. O l
Page 2 of 4 VAV/ MPG /mla
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- , 7.0 ACTION LEVEL 7.1 The Plant Survey Group shall be activated by the Personnel Safety Team leader when necessary.
8.0 PRECAUTIONS ,
8.1 Planned radiation exposures should be limited to the administrative guide levels in Appendix EP-251-1, Emergency Exposure Guidelines.
- 8.2 Continuous coverage by Health Physics Technicians nay be substituted for a Radiation Work Permit.
9.0 PROCEDURE 9.1 Immediate Actions 9.1.1 The Plant Survey Group leader shall:
9.1.1.1 Report to the Operations Support Center (OSC) or other assembly area as directed by Personnel Safety Team Leader.
9.1.1.2 Discuss the situation with the Personnel Safety Team leader.
9.1.1.3 Form the necessary number of plant survey squads from available. personnel. A squad shall consist of two individuals at .least one of which is a Health Physics Technician.
9.1.1.4 Discuss the situation with each squad, and direct them to specific locations in the i
pl ant '.
9.1.2 Plant Survey Squad members shall:
9.1.2.1 Report to the Plant Survey Group leader at j' the Operations Support Center or other l assembly area as , directed by Personnel
- Safety Team Leader. -
9.1.2.2 Take the necessary survey equipment from the equipment locate 4 in the Operations Support
'; Center or normal Health Physics stores .
9.1.2.3 Ensure that the survey equipment is working
> properly and have the equipment on when travnling through the plant to observe-changes in radiation conditions.
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EP-251 Rev. O
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I VAV/ MPG /mla 0.1.2.4 Ensure that direct reading dosimeters are zerced before leaving the Operations Support Center.
9.2 Follow-up Actions 9.2.1 The Plant Survey Group leader shall:
9.2.1.1 Report results to the Personnel Safety Team leader.
9 2.1.2 Provide the plant survey squads with status updates as to changes in plant conditions.
9.2.1.3 Direct the plant survey squa'ds to other locations as necessary.
9.2.1.4 Inform the Personnel Safety Team leader for the need of additional. personnel if. t necessary. .
9.2.2 Plant Survey Squad members shall:
9.2.2.1 Conduct surveys as directed by Plant Survey Group Leader, use the methods outlined in Health Physics Procedures modified as necessary to minimize exposure to survey squads.
9.2.2.2 Report survey results to the Plant Survey Group leader.
9.2.2.3 Post areas , as necessarye to prevent the
, spread of contamination and accumulation of large doses of radiation to operating '
. personnel.'
9.2.2.4 Report to the Operations Support Center or other assembly area for further instructions from the Personnel Saf ety Team leader.
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10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 NUREG'0654, criteria for Preparation and ' Evaluation of Rev. 1 Radiological Emergency Response Plans in support of nuclear power plants.
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EP-251, Rov. O Page 4 of 4 VAV/ MPG /mla APPENDIX EP 251-1 Emergency Exposure Guidelines Projected .
Whole Body Thyroid Authorized Function Dose Dose By.
- 1. Life Saving and Reduction of Injury 75 rem
- 375 rem Emergency **
Director
- 2. Operation of Equipment to Mitigate an Emergency 25 rem
- 125 rem Emergency **
Director
- 5. Re-entry / Recovery Station Station Activities Administra- Administra- -
tive Guide- tive Guide-lines lines N/A
Reference:
EPA-520/1-75-001 Tabl e 2.1
- Such exposure shall be on a voluntary basis e
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EP-252 Rev. 0
- Page 1 of 12 VAW G/rgs ;
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- ,1 PHILADELPHIA ELECTRIC COMPANY s LIMERICK GENERATING STATION
- EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-252 SEARCH AND RESCUE /FIRST AID 1.0 PURPOSE The purpose of this procedure is to define the requirements
- - and the actions of the Search and Rescue /First Aid Group.
2.0 RESPONSIBILITIES 2.1 The Personnel Safety Team Leader 'shall control the Search and Rescue /First Aid Group exposure and provide of fsite medical support by performing the necessary steps in this procedure.
2.2 The Search and Rescue /First Aid Group Leader shall direct operations by performing the necessary steps in this procedure.
2.3 The Search and Rescue /First' Aid Group members shall perform rescue operations by performing the necessary steps in this procedure.
3.0 APPENDICES ,
3.1 EP 252-1 Emergency Exposure Guidelines 3.2 EP 252-2 First Aid Equipment Locations 3.3 EP 252-3 Injured Personnel Report Form 3.4 EP-252-4 Medical Support Group Phone List j l
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4.0 PREREQUISITES
.None 8
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EP-252 Rev. 0
' . Page 2 of 12 VAW/ MPG /rgs 5.0 SPECIAL EQUIPMENT 5.1 First Aid Kit 6.0 SYMPTOMS -
6.1 Missing personnel or personnel with injury requiring first aid.
s 7.0 ACTION LEVEL 7.1 The Search and Rescue /First . Aid Group is activated whenever personnel are known to be missing or in need of help.
8.0 PRECAUTIONS 8.1 Personnel shall participate in search and rescue operations on a voluntary basis.
8.2 Proper radiological controls shall be followed as much as practicable during search and rescue operations. I continuous coverage by Health Physics tech,nician may be substituted for a Radiation Work Pernit.
8.3 Planned radiation exposures should be limited to the administrative guide levels in Appendix EP-252-1 Emergency Exposure Guidelines .
8.4 Life-saving first ai'd treatment has priority ov'r e decontamination or treatment for radiation exposure.
8.5 Radiation exposure and group member contamination should.be minimized as much as practical.
8.6 If gross external contamination is found, internel contamination should be suspected.
8.7 Any material removed from a contaminated person shall '
be recovered for potential *use for isotopic analysis.
8.8 The Search and Rescue /First' Aid Group Leader will maintain contact with the Personnel Saf ety Team Leader at the designated assembly area.
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EP-252 Rev. 0 Page 3 of 12 I
- VAW/ MPG /rgs 8.9 If first aid team is unable to move an injured person due to the nature of the injury, assistance of local ambulance personnel may be utilized.
9.0 PROCEDURE 9.1 IMMEDIATE ACTIONS 9.1.1 Personnel Safety Team Leader shall:
9.1.1.1 Select a qualified person at the OSC to be the Search and Rescue /First Aid Group Leader and to carry out Section 9.1.2 of this procedure.
9.1.1.2 Inform the Interim Emergency Director or the Emergency Director that search and' rescue /first aid groups have been formed and of their intentions to enter the plant for search and rescue operations. (Attempt to locate missing person (s) by utilizing plant paging system just prior to actually dispatching the search and rescue group (s)) .
9.1.1.3 Obtain exposure limits f rom the Emergency Director. If later search and rescue operations are necessary, the Emergency Director may adjust the radiation exposure limits accordingly. If waiting for Emergency Director- approval could endanger personnel, the search and rescue /first aid group leader may decide to remove injured person.
9.1.1.4 If offsite medical help is necessary, have the ambulance, hospital or physician contacted by using Appendix EP-252-4 Medical Support Groups Phone List. Always state the '
number of individuals involved, type of injury and if contamination is involved.
9.1.1.5 Notify security so that the offsite medical response group's access to the Restricted i
Area can be expedited, if necessary.
9.1.1.6 Recall the search and rescue groups when search and rescue. operations are no longer necessary.
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EP-252 Rev. O Page 4 of 12 VAW/ MPG /rgs 9.1.2 Search and Rescue /First Aid Group Leader shall:
9.1.2.1 Select volunteers from available personnel to form search and rescue /first aid squads.
Each squad shall consist of at least three members; two must be qualified in first aid and one must be a health physics technician.
9.1.2.2 Ensure that cach member has the necessary respiratory equipment, radsurvey equipment, anti-contamination clothing, and personal dosimetry. This material can be obtained from emergency survey kits at the OSC or from normal HP stocks.
9.1.2.3 Discuss the situation with the Personnel Safety Team Leader. Th's following ,
information should be obtained prior to !
performing search and rescue operations:
A. Number of missing persons.
4 B. Name of individuals.
C. Last~ known location of individuals .
D. The job being worked. .
E. Any significant plant conditions that may affect the search and any special ins tructions .
9.1.2.4 Ensure the. group is equipped with a first aid kit, or can get one enroute. See attached Appendix EP-252-2 for listing of first aid equipment location in the plant.
! 9.1.'2.5 coordinate search and rescue /first aid l squads to minimize duplication of effort and l unnecessary radiation exposure.
9.1.2.6 Direct the groups to the last known 3.7 cation of the missing individual. If necessary, expand the search to adjacent areas.- Ens ure most expeditious . routes available are taken to minimize team exposure.
(' 9.1.2.7 Inform the Personnel Saftey Team Leader of l' the actions of the group and whenever the I group locates any missing personnel, and-the identity of located personnel.
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EP-252 Rev. O Pace 5 of 12
- VAW/ MPG /rgs 9.1.2.8 Determine the extent of the injury and direct administration of first aid.
9.1.2.9 Report to the Personnel Saf ety Team Leader the extent of the individual'" injuries and recommend supplementary medical actions as necessary (i .e . , hospitalizstion) . Complete t Appendix EP 252-3 (if possible) and attach
- to injured person prior to transporting in ambul ance .
9.1.2.10 Direct the first aid group to transport the n injured person to a site first aid facility, if practicable.
Locations: ;
I A. Radwaste Building,' Elevation 217'. ,
- B. In. Administration. Building elevation f
217'.
9.1.2.11 Report to the Personnel Saf ety Team Leader when the search and rescue /first aid group has finished its task.
9.1.3 Search and Rescue /First Aid Squad Members shall .
" 9.1.3.1 Perform a radiation and contamination survey of the person and subsequently the area.
9.1.3.2 Transport the injured person to a site first aid f acility if practicable. .
9.1.3.3 Perform the following if the injured person-is contaminated.
A. Wear necessary anti-contamination clothing if practicable.
. IF-THE INJURY.IS-SEVERE, IM4EDIATE MEDICAL TREATMENT IS OF THE HIGHEST ,
PRIORITY AND. RADIOLOGICAL CONTROLS ARE SECONDARY.
B. Adm.'nister appropriate first aid, being careful to limit the spread of-contamination and limit personal e xposure .
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EP-252 Rev. 0 l Page 6 of 12
. VAW/ MPG /rgs C. IF INJURY IS NOT SEVERE, DECONTAMINATION i SHALL BE ATTEMPTED.
D. Prepare the person f or transportation by covering the contaminated area with a protective wrap. Avoid excessive wrapping to prevent dehydration of the person.
IF THE INJURED PERSON IS GOING TO BE TRANSPORTED TO AN OFFSITE 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.
E. When transporting the victim to an l offsite medical facility, a Health
! Physics Technician shall accompany the victim to assist the medical staff.
9.1.3.4 Recover any contaminated articles of clothing that may have'been removed from the person for isotopic analysis.
9.2 Follow-Up Actions 9.2.1 Search and rescue group members shall:
': 9.2.1.1 Report results of their actions to the o Personnel Safety Team Leader.
9.2.1.2 Follow normal decontamination and disposal procedures when their tasks are complete.
9.2.2 Personnel Safety Team Leader shall:
9.2.'2.1 Verify the victim's arrival at the medical facilities.
9.2.2.2 Inform the Emergency Director of rdsults of search and rescue efforts.
9.2.2.'3 Have the Health Physics technician d
accompanying victim to the hospital, call the Personnel Safety Team Leader when informed by the hospital that his services are no longer needed. With the concurrence of the Personnel Saf ety Team Leader he may.
procede to another assignment.
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t e EP-252 Rev. 0 Page 7 of 12 VAW/ MPG /r,gs 9.2.2.4 Arrange for inventory and restocking of first aid kits, if necessary.
.9.2.3 The Emergency Director shall:
9.2.3.1 Have the Medical Director and Corporate Communications informed of the identify and condition of the victim (s).
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 NUREG 0654, Criteria for Preparation and Rev.1 Evaluation of Radiological Emergency Response Plans and Preparedness In Support of Nuclear Power Plants.
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EP-252-1 Rev. O Page 8 of 12
. VAW/ MPG /rgs l i
APPENDIX EP 25;-1 :
Emergency Excosure Guidelines Projected Whole Body Thyroid Authorized-Function Dose Dose Bf
- 1. Life Saving and Reduction of Injury 75 rem
- 375 rem Emergency **
Director
- 2. operation of Eculpment to Mitigate an Emergency 25 rem
- 125 rem Emergency **
Director
- 5. Re-entry / Recovery Station Station Administra- Adminis-Acti viti es tive Guide- trative -
lines Guide-lines N/A
Reference:
EPA-520/1-75-001 Table 2.1
- l. ** such exposure shall be on a voluntary basis
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EP 252-2 Rev. 0 Page 9 of 12 VAW/ MPG /rgs APPENDIX EP-214-2 FIRST-AID EQUIPMENT LOCATIONS )
FIRST AID STRETCHERS KITS BLANKETS Unit 1 RX Encl. Elevator Stairwells Elev. 177' X X X Elev. 201' X X X
", Elev. 217' X X X Elev. 239' X X X Elev. 253' X X X Elev. 283' X X X Elev. 313'. X X X Elev. 351' X X X Elev. 352' X ,
X X Unit 2 F.X Encl. Elevator Stairwells -
Elev. 177' X X X Elev. 201' X X X Elev. 217' X X X Elev. 239' X X X Elev. 253' X X X Elev. 293' X X X Elev. 313' X X X Elev. 331' X X X Elev. 352' . .
I g Turbine Encl. East & West
- Stairwells Elev. 200' X
' Elev. 217' X Elev. 239'. X Elev. 269.' X .
Turbine Encl.
. Equipment Hatch Elev. 217' X X
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EP 252-2 Rev. O Page 10 of 12 VAW/ MPG /rgs FIRST AID STRETCHERS KITS BLANKETS Control Enclosure Elevator Stairwells Elev. 180' X X X Elev. 200' X . X X Elev. 217' X X X Elev. 239' X X X Elev. 254' X X X Elev. 269' X X X Elev. 289' X X X r Elev. 304' X X X Elev. 332' X X X Radwaste Encl. North Stairwell Elev. 162' X X Elev. 191' X X Elev. 217' ,
X X Elev. 237' X X Elev. 257' X X Cire. Water Pump House X 220 Switchyard Encl. X 500 Switchyard Encl. X {
'mr : 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-304 Rev. 0 Page 1 of 4 W p/rgs PHILADELPHIA ELECTRIC COMPANY c./ ' \ a//D LIMERICK GENERA' 'TG STATION \
EMERGENCY PLAN IMPLE. 'ING PROCEDURE EP-304 PARTIAL PLANT EVACUATION 1.0 PURPOSE The purpose of this procedure is to define the actions to be perf ormed in the event that a partial plant evacuation is required due to uncontrolled hazards in two or more operating areas. -
2.0 RESPCHSIBILITIES 2.1 Personnel in affected areas requiring evacuation shall evacuate the area and notify the control room.
2.2 The Interim Emergency Director or Emergency Directoi shall direct the partial plant evacuation by performing the appropriate steps in this procedure.
3.O APPENDICES None
- 4. 0' PREREQUISITES _
None 5.0 SPECIAL EQUIPMENT
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None ,
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EP-304 Rev. O
- Page 2 of 4 VAW/ MPG /rgs
. 6.0 SYMPTOMS 6.1 An increase in the area radiation monitors or continuous air monitor indications to greater than alarm' levels in two or more large operating areas .
6.2 Radiation levels greater than 1DO mR/hr within two or more large operating areas which normally experience l less than 10 mR/hr. l 6.3 Airborne radioactivity greater than 3N8 uCi/cc for an unidentified isotope, (except for noble gas activity) or 10 MPC for identified isotopes in restricted areas in two or more larga operating areas.
6.4 Release, leakage or spill of a toxic reagent such that the concentration of chemical vapors makes the areas uninhabitable in two or more large operating areas.
6.5 other hazards such as flood or fire aff ecting two or more large operating areas 7.0 ACTION LEVEL This procedure shall be implemented by the Interim Emergency Director or Emergency Director when the symptoms of section 6.0 of this procedure occur. Two or more large operating areas is defined as two or more elevations in a single enclosure or cne elevation in two or more enclosures.
8.0 PRECAUTIONS , ,
None 9.0 PROCEDURE ;
9.1 Immediate Actions ,
,~ 9.1.1 Personnel in the affected area not directly' involved in controlling the hazard shall evacuate to a safe area. Notify the control room of the type and locat 8.on of the hazard.
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EP-304 Rev. 0 Page 3 of 4 VAW/ MPG /rgs
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9.1.2 The (Interim) Emergency Director or Shift Supervision shall:
9.1.2.1 Upon receiving inf ormation f rom personnel in the field that a hazardous condition or from control room indications, evacuate the affected areas. Assemble personnel for i I
purposes of accountability per procedure EP-llo, Personnel Assembly and Accountability by making the following announcement:
"This (is ) (is This not)isa drill. This (is) a Partial Plant (is not) a drill.
Evacuation. Evacuate (locations of hazard ) .
All personnel report to Emergency Assembly Areas. This (is) (is not) a drill. This (is) (is not) a drill."
9.1.2.2 If the hacard has a potential to spread to Unit 2, evacuate construction personnel by notifying Bechtel Saf ety S or Bechtel Security Direct them to call for either:
PARTIAL EVACUATION - ASSEMBLY AREA between the Main Construction Of fice and the Change House.
TOTAL PROJECT EVACUATION - ASSEMBLY AREAS at the upper parking lot and Post 43.
9.2 Pollow-Uo Actions 9.2.1 The (Interim) Emergency Director shall:
9.2.1.1 Evaluate the situation and if conditions worsen call for an evacuation of the site in accordance with procedure EP-305 Site Evacuation.
9.2.1.2 If the hazard can be contained and when conditions permit, perform recovery / cleanup operations in accordance with EP-401 Entry ,
for Emergency Repair and Operations.
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EP-304 Rev. 0 Page 4 of 4 VAW/ MPG /rgs
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 NUREG 0654 Criteria for Preparation and Rev. 1 Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 10.3 EP-110 Personnel Assembly and Accountability 10.4 EP-305 Site Evacuation 10.5 Bechtel Evacuation Procedures 10.6 EP-401 Entry for Emergency Repair and Operations e
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.p EP-305 Rev. O Page 1 of 4 VW/ MPG /rgs PHILADELPHIA ELECTRIC COMPANY d LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-305 SITE EVACUATION
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1.0 PURPOSE The purpose of this procedure is to define the actions to be performed if a site evacuation is required.
2.0 RESPONSIBILITIES 2.1 The Emergency Diractor or Interim Emergency Director shall direct the evacuation of the site by performing the necessary steps in this procedure.
2.2 Security shall perform accountability of personnel during the evacuation.
2.3 Bechtel/ Subcontractor personnel shall evacuate in accordance with Bechtel procedures.
2.4 Non-essential Unit 1 personnel shall exit through the security areas and assemble at Post #3 prior to leaving the site.
3.0 APPENDICES None t
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l 4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT ,
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! None
EP-30$ Rev. O Page 2 of 4 VAW/ MPG /rgs 6.0 SYMPTOMS 6.1 General Emergency has been declared.
6.2 An actual or potential release exceeding that specified as an Alert or Site Emergency levels in EP-101 Classifications of Emergencies.'
6.3 Major toxic or hazardous gas release.
7.0 ACTION LEVEL This procedure shall be implemented when a symptom of section 6.0 occurs or at the discretion of the Emergency Director or Interim Emergency Director.
8.0 PRECAUTICNS
~
None 9.0 P ROCEDURE 9.1 Immediate Actionc 9.1.1 Emergency Director or Interim Emergency Director shall:
9.1.1.1 Notify security that a site evacuation is being initiated and to carry out applicable security procedures.
9.1.1.2 Implement the evacuation of the information center in accordance with EP-306 Evacuation of the Infornation Center.
9.1.1.3 Y For an actual or potential adverse radiological condition, inform the Personnel Safety Team Leader and direct him to prepare for a site evacuation in accordance with EP-254 Vehicle And Evacuee Control Group.
9.1.1.4 Inform Bechtel Safety that a site i
evacuation is being called.
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EP-305 Rev. O Page 3 of 4 VAW/ MPG /rgs j 1
l 9.1.1.5 Select the Assembly Areas and Unit 1 exit points from the following:
Assembly Areas Unit L Exit Points Day shift Upper Parking Lot and Post 3 TSC and Admin Bld7 Afternoon Shift Upper Parking Lot and Post 3 Admin Bldg Night Shift Post 3 Admin Bldg 9.1.1.6 Direct the activation of the alarm in accordance with EP-301 Operating the Evacuation Alarm and River Warning System.
9.1.1.7 When the Personnel Safety Team leader is ready if needed per step 9.1.1.3, announce a site evacuation as follows:
" ATTENTION ALL PERSONNEL. THIS (IS)(IS NOT)
A DRILL. THIS (IS)(IS NOT) A DRILL. THIS IS A SITE EVACUATION. EMERGENCY TEAMS REPORT TO DESIGNATED AREAS. NON-ESSENTIAL UNIT 1 PERSONNEL EXIT THROUGH THE (TSC)
(AND) (ADMIN BUILDING). PERSONNEL ASSEMBLE AT THE (UPPER PARKING LOT) (AND) (POST 3).
THIS (IS)(IS NOT) A DRILL. THIS (IS)(IS NOT) A DRILL."
9.1.1.8 After the alarm has stopped, repeat steps 9.1.1.6 and 9.1.1.7.
9.1.1.9 Direct the workers at the RMC #= 'li on Fricks Lock Road to evacuate. -
9.2 Follow-Up Actions 9.2.1 Security shall:
9.2.1.1 Perform accountability of personnel in accordance with E?-209 Security Team Activation.
9.2.1.2 Inform the Emergency Director or Interim Emergency Director of unaccounted for personnel.
EP-305 Rev. O Page 4 of 4 VAW/ MPG /rgs I
. 9.2.2 Emergency Director or Interim Emergency l Director shall:
9.2.2.1 Direct the Personnel Safety Team Leader to initiate search and rescue operations for any unaccounted for personnel in accordance with EP-252 Search & Rescue /First Aid.
9.2.? Bechtel/ Subcontractor Personnel shall:
9.2.3.1 Evacuate in accordance with Bechtel procedures.
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9.2.4 Non-Essential Unit 1 personnel shall:
9.2.4.1 Exit the protected area through the Admin Guard House or Technical Support Center by carding out but retaining dosimetry unless otherwise instructed.
9.2.4.2 Report to the Post #3 area for evacuation instructions f rom Security. -
10.O REFERENCES 10.1 Limerick Generating Station Emergency Plan 10.2 NUREG 0654, Criteria for Praparation and Evaluation of Rev. 1 Radiological Emergency Response Plans and
- Preparedness in Support of Nuclear Power Plants.
, 10.3 EP-252 Search and Rescue /First Aid 10.4 EP-101 Classification of Emergencies 10.5 EP-254 Vehicle And Evacuee Control Group
, 10.6 EP-30'l Operating the Evacuation Alarm and River Warning System 10.7 EP-306 Evacuation of the Information Center l
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- EP-307 Rev. O Page 1 of 3 I
, VAV/M /ala r
- it lN PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE o
EP-307 RECEPTION AND ORIENTATION OF SUPPORT PERSCENEL
. 1.0 PURPOSE 4 This procedure defines the actions to be taken to. receive and train those support personnel who will be coming on site to respond to an emergency.
2.0 RESPONSIBILITIES 2.1 The Planning and Scheduling Coordinator shall direct -
the reception and orientation of support personnel by performing the necessary steps in this procedure. i 2.2 Personnel from the Nuclear Training Section or their'
\
contractors shall train the support personnel by
, performing the, necessary steps in this procedure.
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3.0 APPENDICES None
\
440 PREREQUISITES
} 4.1 Emergency Support Center or other reception area is l activated .
l 4.2 Off-site personnel needed for -assistance and arriving at the reception area.
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k 6.0 SYMPTCMS
.' EP-307 Rev. O Page 2 of 3 VAV/ MPG /mla s
6.0 SYMPTOMS None 7.0 ACTION LEVEL This procedure shall be implemented when the arrival of off-site support personnel requested by the Philadelphia Electric Company is anticipated and the Emergency Support Center or other reception area is activated.
8.0 PRECAUTIONS None 9.0 PROCEDURE
. 9.1 Immediate Actions 9.1.1 Planning and Scheduling Coordinator shall:
9.1.1.1 Direct the Security Team Leader to assign a Security Team Member to report to the Emergency Support Center or othdr designated area to issue security badges in accordance with Security procedures.
9.1.1.2 Direct the Radiation Protection Team Leader to assign a Personnel Dosimetry, Bioassay,
. Reapiratory Protection Group Member t'o report to the Emergency Support Center or other designated area and issue dosimetry in accordance with Health Physics procedures.
9.1.1.3 Direct Training personnel through the Training Coordinator to report to the Emergency Support Center. ,
9.2 -
Follow-up Actions
! 9.2.1 Training personne,1 shall:
9.2.1.1 Request f rom the Planning and Scheduling
( CoordinatoJ information regarding the team or staff to which the Support personnel are to report.
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EP-307 Rev. O' l
, Page 3 of 3 l VAV/ MPG /mla',
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9.2.1.2 Reauest from the Planning and Scheduling Coordinator information regarding the plant status.
'g 9.2.1.3 Assemble personnel in the classroom and i' provide them with the -following information:
A. Basic description of the plant status. j 1
B. Work shif t hours they will be assigned I to. l C. Arrangements for hotels, meals and transportation.
D. Person to whom they are to report.
9.2.1.4 With the same group conduct a General Employee Training Class. Also, if necessary, conduct a General Respiratory Training Class and Respiratory Fit' Test.
9.2.1.5 conduct training sessions on special topics as necessary such as use of potassium iodide i, tablets, evacuation plans, etc.
9.2.1.6 Contact appropriate Station personnel assigned the responsibility for supervising the support personnel. Request authorization to release personnel to these Station personnel and have them meet the support personnel at the entrar.:c of the Technical Support Center, if activated or the Administration Building Guard Station.
, 9.2.2 Planning and Scheduling Coordinator shall: )
9.2.2.1 Inform the Site Emergency Coordinator and Emergency Director when the designated
. Support personnel have been properly
- indoctrinated and trained and are ready for 4 work in the plant or on the site. ,
REFERENCES"
- 10.1 Linarick Generating Station Emergency Plan N.
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EP-312 Rev. O Page 1 of 4 i VAW PG/rgs l
PHILADELPHIA ELECTRIC COMPANY stl50/03 i, LIMERICK GENERATING STATION
- EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-312 RADIOACTIVE LIQUID RELEASE
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1.0 PURPOSE The purpose of this procedure is to provide guidelines for ,
the actions to be taken when an uncontrolled liquid release of radioactive material occurs.
m 2.0 RESPONSIBILITIES 2.1 The (Interim) Emergency Director shall direct the steps necessary to terminate the liquid release and evaluate the consequences of the release performed.
2.2 The Site Emergency Coordinator, if activated, or (Interim) Emergency Director shall direct the follow-up actions of notification of downstream water users and river sampling, if they are required.
- 3.0 APPENDICES None 4
4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT None
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EP-312 Rev. O Page 2 of 4 VAW/ MPG /rgs 2 6.0 SYMPTOMS 6.1 An actual or suspected liquid release of radioactive material with a concentration greater than 1.5N5 uCi/cc (500 times the maximum MPC for any unidentified isotope in water). ,
6.2 Radwaste discharge radiation monitor exceeds alarm setpoint of 1.4N4 uCi/cc.
t 7.0 ACTION LEVEL
~
7.1 This procedure shall be implemented when a liquid release occurs exceeding the criteria in section 6.0.
8.0 PRECAUTIONS None 9.0 PROCEDURE 9.1 Immediate Actions
-i 9.1.1 The (Interim) Emergency Director shall:
9.1.1.1 Direct the immediate steps necessary to terminate the discharge to the river.
9.1.1.2 Direct the Chemistry Sampling and Analysis
. Team Leader to initiate sampling of the blowdown line in accordance with EP-236, Obtaining Blowdown Line Water Samples Following Radioactive Liquid Release After Accident Conditions, or to sample the river just downstream of the liquid diccharge.
9.1.1.3 Direct the Dose Assessment Team Leader to estimate dose projections from the ingestion of drinking water and fish in accordance with EP-318, Liquid Release Dose Calculation 2 . Method for Drinking Water and EP-319, Fish l Ingestion Pathway Dose Calculation.
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EP-312 Rev. O Page 3 of 4 VAW/ MPG /rgs 9.2 Follow-Up Actions 9.2.1 The Site Emergency Coordinator, if activated or (Interim) Emergency Director shall:
9.2.1.1 Based on results of estimated dose projections for downstream water users and fish ingestion, have the Department of Environmental Resources notified.
A.
B.
C. (Regional Office) 9.2.1.2 If requested by the Department of Environmental Resources, direct the notification of the downstream domestic water users in EP-287 Nearby Public and Industrial Users of Downstream Waters.
9.2.1.3 If necessary, direct the Environmental Sampling Coordinator if activated, or Chemistry Sampling And Analysis Team Leader to have the river water near the intake for the following water companies at the appropriate time based on the Transit Time for that location.
The Transit Time is the time required for the material released to reach the location of interest.
Location Transit Time (hrs)
A. Citize s Utilities Home 1.5 .
Water Company-Royersford l
\ l B. Phoenixville Water 10 l
C. Philadelphia Suburban 16 Water D. Norristown Water 27 E. Philadelphia Belmont Water 50 9.2.1.4 Direct that a log be kept for all samples taken.
_.... --...-.-..1 - - . . - . ..-- - . . . _ . . . . . .. . .. . . . - . . - . . . . .
. . 1 EP-312 Rev. 0 l
Page 4 of 4 VAW/ MPG /rgs
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 EP-236 Obtaining Blowdown Line Water Samples Following ,
I Radioactive Liquid Release Af ter Accident Conditions ,
10.3 EP-318 Liquid Release Dose Calculation Method For Drinking Water 10.4 EP-319 Fish Ingestion Pathway Dose Calculation 10.5 EP-287. Nearby Public And Industrial Users Of Downstream Waters 10.6 EROL Appendix 5.2A Radiological Dose Model-Liquid -
Effluents -
10.7 10CFR Part 20 Appendix B s
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EP-313 Rev. O Page 1 of 8 VA PG/rgs
.l, PHILADELPHIA ELECTRIC COMPANY C/ *,, /
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LIMERICK GENERATING STATION -
EMERGENCY PLAN IMPLEMENTING PROCEDURE
! EP-313 DISTRIBUTION OF THYROID BLOCKING TABLETS l.0 PURPOSE The purpose of this procedure is to provide guidelines for the administration of potassium iodide (KI) to on-site personnel performing a necessary TAS for use as a thyroid l blocking agent to provide protection against airborne radiciodine.
2.0 RESPONSIBILITIES 2.1 The Radiation Protection Team Leader shall determine if potassium iodide is required and direct the administration of the tablets by performing the necessary steps in this procedure.
2.2 The Personnel Dosimetry, Bioassay and Respiratory Protection Group Leader shall administer the potassium iodide tablets by performing the necessary steps in this procedure.
3.0 APPENDICES 3.1 EP-313-1 Potassium Iodide Work Sheet 3.2 EP-313-2 Potassium Iodide Administration Record Form 3.3 EP-313-3 Potassium Iodide Consent Form 3.4 EP-313-4 Instruction And Record Sheet For Persons Receiving KI 4.0 PREREQUISITES None
^ ^
- . - - . . . - - . - - - - . . . . - . . 1. . - . - - - _ . . .
L-..--..-
EP-313 Rev. O Page 2 of 8 VAW/ MPG /rgs 5.0 SPECIAL EQUIPMENT
. 5.1 Potassium Iodide tablets not beyond the expiration date. ,
6.0 SYMPTOMS ,
6.1 An actual or potential thyroid dose equal to or greater than 10 REM.
7.0 ACTION LEVEL ,
This procedure shall be implemented by the Radiation Protection Team Leader when an actual or potential thyroid dose is equal to or greater than 10 REM for any individual.
PRECAUTIONS 8.0 8.1 The taking of potassium iodide (KI) tablets is-J voluntary for each individual involved.
8.2 Personnel having allergic reactions to iodine should be administered potassium iodide only if absolutely necessary.
8.3 Prior to administering potassium iodide, ensure that the tablets are not beyond the expiration date.
8.4 All persons using potassium iodide should be familiar i with the following possible side eff ects and report any noticed side effects to Radiation Protection Team Leader.
8.4.1 Skin rashes 8.4.2 Swelling of parotid glands (like mumps) 8.4.3 Metallic taste in mouth 8.4.4 Burning mouth and throat i
,t 8.4.5 Sore teeth and guns '
8.4.6 Symptoms of a head cold 8.4.7 Gastric upset l
t b
_i_ -
_. ..___.i--____ _ _. __ _ . 2 ... .~. - - _ . _ - - -
EP-313 Rev. O Page 3 of 8 VAW/ MPG /rgs 8.4.8 Diarrhea 9.0 PROCEDURE 9.1 Immediate Actions 9.1.1 Radiation Protection Team Leader shall:
9.1.1.1 Determine the need for administering potassium iodide by completing Appendix EP-313-1 Potassium Iodide Worksheet for each
- individual needed to perform the task.
,, 9.1.1.2 Discuss with the (Interim) Emergency J
Director that potassium iodide is needed and obtain his concurrence prior to the administration of the tablets.
9.1.1.3 Enter the names of each individual on Appendix EP-313-2 and direct the Personnel Dosimetry, Bioassay and Respiratory Protection Group Leader to administer the tablets per scetion 9.2.1 of this procedure.
9.2 Follow-Up Actions 9.2.1 The Personnel Dosimetry, Bioassay and Respiratory Protection Group Leader shall:
i 9.2.1.1 When directed by the Radiation Protection
. Team Leader, assemble the personnel to be treated at the Technical Support Center or other area and acquire an adequate supply of tablets from the Medical Facility or Decon Area in Radwaste.
9.2.1.2 Discuss with personnel the possible side eff ects of potassium iodide and that taking the tablets is voluntary. Determine-if any personnel are aware of an allergy to iodine.
If an individual is allergic, discuss the situation with the ' Radiation Protection Team Leader.
9.2.1.3 Have each individual sign a copy of Appendix EP-313-3 Potassium Iodide Consent Form,
, unless one is already on file. l 2
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' . - . . - . .: - - - - - -- :--...-..---. . -- ...--.---.2..~.
EP-313 Rev. O Page 4 of 8 I
VAW/ MPG /rgs 9.2.1.4 Administer to personnel who already have been exposed to radiciodine first, preferably within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of exposure. The recommended dosage is 130 mg potassium iodide (100 mg iodide) per day for a minimum of three days but preferably 10 consecutive days. -
9.2.1.5 Provide each individual receiving KI with a copy of Appendix EP-313-4 Instruction And Record Sheet For Persons Receiving KI and instruct them to report back each day for follow-up desages. This form is for the
- individuals information only and is not needed to receive additional dosages.
9.2.1.6 Complete the information required for each person on Appendix EP-313-2 Potassium Iodide Administration Record Form. Use this information to administer follow-up dosages.
9.2.1.7 Inform the Radiation Protection Team Leader when completed.
9.2.2 Radiation Protection Team Leader shall:
9.2.2.1 Notify the Medical Director and Emergency Director of all persons who received potassium iodide.
'9.2.2.2 Ensure that the potassium iodide is administered in the proper dosage and for
, the proper number of doses.
J
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan - Section 6.4.2.3 10.2 NUREG 0654 Criteria for Preparation and Evaluation Rev. 1 ~ of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants
, 10.3 Reg. Guide 1.109 Calculation of Annual Doses to Man Rev. 1 from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part~50, Appendix I l
l ii
. s .
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) ,
EP-313 Rev. O Page 5 of 8 VAW/ MPG /rgs APPENDIX EP-313-1 POTASSIUM IODIDE WORK SHEET Date: Time:
Name:
Badge Number Area To Be Entered:
I-131 Concentration (uci/cc) in Effected Area:
Respiratory Equipment (Check one)
TYPE PROTECTION FACTOR (PF)
Air P.urifying 50 Atmosphere Supplying 2000 SCBA 10,000 None 1 Time Needed To Complete Task: Hours Previous Thyroid Dose Accumulation During Emergency: REM
. Perform Calculation:
Total Thyroid Dose = 1.361P6 x Concentration I-131 x Task Time x 1 (REM) uCi (Hours) PF cc
+ Previous Thyroid Dose (REM)
Total Thyroid Dose = Rem If Dose equals or is greater than 10 Rem, recommend administration of potassium iodide.
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EP-313 Rev. O Page 7 of 8 VAW/ MPG /rgs
?
APPENDIX EP-313-3 i
POTASSIUM IODIDE CONSENT FORM i I volunteer to receive 130 l
~
milligrams per day for the next 10 days of the thyroid blocking agent potassium iodide. I have been informed by a representative of PEco that this drug will block the absorption of radio-iodine by my thyroid and thereby reduce the exposure to radiation of the thyroid; that potassium does not reduce the uptake of other radioactive materials by the bodyr nor, does it provide j protection against exposure from external radiation. I also understand that there may be some side effects upon taking this drug.
Signature i
Date d
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EP-313 Rev. O Page 8 of 9 VAW/ MPG /rgs APPENDIX EP-313-4 INSTRUCTION AND RECORD SHEET FOR PERSONS RECEIVING KI Name i Badge No.
j' CAUTION IF YOU FEEL SICK, REPORT IMMEDIATELY TO THE PERSONNEL DOSIMETRY, BIOASSAY AND RESPIRATORY
- PROTECTION GROUP LEADER.
You have just received 13'O mgs. of the thyroid blocking agent KI.
In order to be most effective you should receive an additional nine (9) doses over the next 9 days. Each day for the next 9 days, take this form and report to the for a thyroid count and another KI pill.
130 mg KI Tablet Th/roid Count Results Administered Date ( D.st e , Time, Initials) (Date, Time, Initials) s e
1.
2.
3.
4.
5.
6.
7.
8.
9.
i 10.
i e
4
. I I: EP-318 Rev. O I Page 1 of 8 VA MPG /rgs )
plio/O PHILADELPHIA ELECTRIC COMPANY
- ? LIMERICK GENERATING STATION j EMERGENCY PLAN IMPLEMENTING PROCEDURE i EP-318 LIQUID RELEASE DOSE CALCULATIONS METHOD FOR DRINKING WATER 1.0 PURPOSE The purpose of this procedure is to provide the calculation method for estimates of population exposure due to the ingestion of drinking water at various locations downstream of the plant.
2.0 RESPONSIBILITIES None 3.0 AFPENDICES 3.1 EP-318-1 Citizen Utilities Home Water Company Intake
. 3.2 EP-318-2 Phoenixville Water Intake 3.3 EP-318-3 Philadelphia Suburban Water Company Intake 3.4 EP-318-4 Norristown Water Intake 3.5 EP-318-5 Philadelphia Belmont Water Intake 4.0 PREREQUISITES None -
5.0 SPECIAL EQUIPMENT l
None l
l l
-,- - ~ - - - - e e
EP-318 Rev. O Page 2 of 8 VAW/ MPG /rgs 6.0 SYMPTOMS 6.1 An actual or potential licuid release of radioactive material into the Schuylkill River.
7.0 ACTION LEVEL 7.1 This procedure shall be implemented when the criterion of section 6.0 is met.
~
8.0 PRECAUTIONS None 9.0 PROCEDURE 9.1 The following assumptions were utilized in this -
calculation:
, 9.1.1 The Dose Conversion Factor is based on the most limiting group (adult, teen, child, infant) using dose factors and consumption rates in Reg. Guide 1.109.
Adult 730 1/yr Teen 510 1/yr Child 510 1/yr Infant 330 1/yr 9.1.2 The Decay Factor is based on the decay of the isotope.over the transit time plus 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (time to reach the population via water system per Reg. Guide 1.109).
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I EP-318 Rev. 0 l Page 3 of 9 VAW/ MPG /rgs ,
. l 9.1.3 The total dose commitment is the dose which
. an individual would receive af ter drinking l water with the radionuclides present at the l concentrations calculated to exist at the entrance to the water plant for a period equal to the duration of the release. Fo r example, if the release 1.asted 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the -
individual is postulated to consume 1/2 of his average daily water intake at the
. diluted concentrations. l 9.2 Obtain grab sample results on the concentration of Co-p 60, I-131, Cs-134 and Cs-137 released, from the Chemistry Sampling and Analysis Team Leader.
9.3 For each location of interest, enter the concentration of Co-60, I-131, Cs-134 and Cs-137 in uCi/cc released and the release duration in hours on the appropriate appendix.
If the sample was taken prior to entering the Cooling Tower Blowdown Line, a diluted concentration must be determined by the following calculation:
Concentration [uCij " concentration
- Release rate to Blowdown Line Released \ci / Ci Blowdown line flow rate cc 9.4 Perform the calculation in each appendix for each location of interest to estimate the dose in millirem l for the liver, whole body and thyroid. I 9.5 Report results to the Dose Assessment Team Leader.
10.0 REFERENCES
10.1 EROL 2.1.3.6 Surf ace Water Use 10.2 EROL.5.2.4.1 Liquid Pathways 10.3 EROL Appendix 5.2A Radiological Dose Model-Liquid Effluents 4
10.4 Reg. Guide 1.109 Calculation Of Annual Doses To Rev. 1 Man From Routine Releases Of Reactor
, Effluents For The Purpose Of Evaluating i Compliance With 10 CFR Part 50, Appendix I l
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i i EP-318 Rev. O Page 7 of 8 VAW/ MPG /rgs ,. i l
APPENDIX EP-318-4 NORRISTOWN WATER INTAME Dose mR/hr Concentration Decay
, Conversion uCi/cc X uCi/cc X Factor =
Pactor .
$ Liver- 406 1.0 i Whole 959 Body l Liver 1591 -
N Whole 700 .87 7
H Body Thyroid 5.23P5 i
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c) Liver 2.64P4 1.0 a .
$ Whole 1.01P4 Body a n-
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0 Liver. 2.30P4 1.0 }
O Whole 5942 l Body !
+ !
Schuylkill River Release Mixing 1 Usage Factor X Duration (hrs) -X Fac tor X = Dose (mR) i i
Liver i l
1 Whole Body 1.0 .0091 Thyroid l
Date: :
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' t EP-319 Rev. 0 Fage 1 of 4 l VAW PG/rgs
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PHILADELPHIA TECTRIC COMPANY "h/U ,
l LIMERICK GEN 'ATING STATION EMERGENCY PLAN IMPLt:MENTING PROCEDURE l EP-319 FISH INGESTION PATHWAY DOSE CALCULATION 1.0 PURPOSE The purpose of this procedure is to provide the calculation method for estimates of the maximum population exposure due to the ingestion of fish from the Schuylkill River.
2.0 RESPONSIBILITIES None 3.0 APPENDICES 3.1 EP-319-1 Maximum Dose From Fish Ingestion 4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT None 6.0 SYMPTOMS 6.1 An actual or potential liquid release of radioactive material into the Schuylkill River.
4 7.0 ACTION LEVEL 7.1 This procedure shall be implemented when the criterion of section 6.0 is met.
. ....r--..- - . - . - - - - - - - . - - - . - - -
4 '
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EP-319 Rev. O Page 2 of 4 VAW/ MPG /rgs 8.0 PRECAUTIONS
. e, None 9.0 PROCEDUR'E -
9.1 The following assumptions were utilized in this calculation:
9.1.1 The Dose Conversion Factor is based on the most limiting group (adult, teen, child,
. infant) using dose factors and. consumption rates in Reg. Guide 1.109.
Adult 21 kg/yr Teen 16 kg/yr Child 6.9 kg/yr
, Infant 0 kg/yr -
9.1.2 The Decay Factor is based on the decay of the isotope over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (time to reach the i population per Reg. Guide 1.109.
9.1.3 The total dose commitment is the dose which an individual would receive af ter eating fish exposed by the highest concentration of diluted effluent for the duration of the release.
9.2 Obtain grab sample results on the concentration of Co-60, I-131, Cs-134, Cs-137 and P-32 released, from the Chemistry Sampling and Analysis Team Leader.
9.3, On Appendix EP-319-1, enter the concentration of P-32, Co-60, I-131, Cs-134 and Cs-137 in uCi/cc released and the release duration in hours.
If the sample was taken prior to entering the Cooling Tower Blowdown Line, a diluted concentration must be determined by the following method Concentration [uci) . concentration
- Release rate to Blowdown Line Released \ci / [uci} Blowdown line flow rate a
\ CC) t
.- ---.. - - -....-a....---.-.--.- i s
.. P!.
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. I EP-319 Rev. O j Page 3 of 4 ;
VAW/ MPG /rgs
!. 9.4 Perform the calculation on Appendix EP-319-1 to estimate the maximum dose in millirem for the liver, whole body and thyroid for the fish ingestion pathway.
9.5 Report results to the Dose Assessment Team Leader.
10.0 REFERENCES
10.1 EROL 5.2.4.1 Liquid Pathways 10.2 EROL Appendix 5.2A Radiological Dose Model-Liquid Effluents 10.3 Reg. Guide 1.109 Calculation of Annual Doses To Rev. 1 Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance With 10CFR Part 50, Appendix I 1
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I EP-401 Rev. O i Page 1 of 5 l V , MPG /rgs
.th/U PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-401 ENTRY FOR EMERGENCY REPAIR AND OPERATIONS
~
1.0 PURPOSE The purpose of this procedure is to provide guidelines for entering areas for emergency repair and operations that have
- - become adversely affected by the emergency conditions.
2.0 RESPONSIBILITIES 2.1 A health physics technician shall advise personnel of radiological conditions when entry for emergency repair and operations is needed.
j, 3.0 APPENDICES j 3.1 EP-401-1 Emergency Exposure Guidelines
' 4.0 PREREQUISITES i; None I, )
5.0 SPECIAL EQUIPMENT Nme
.. 6.O SYMPTOMS
'l None I
l 1
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.__, _ _ _ _ . _ - . . . . . ~ _ _ . , - .---
- 7 EP-401 Rev. O Page 2 of 5 VAW/ MFG /rgs
- . 7.0 ACTION LEVEL 7.1 This procedure shall be implemented whenever personnel must enter an area of adverse or unknown conditions for reasons of emergency repairs or operation of equipment. .
8.0 PRECAUTIONS 8.1 No one person shall be left alone during the entry.
8.2 Planned radiation exposures should be limited to the administrative guide levels in Appendix EP-401-1 Emergency Exposure Guidelines. Performance of a task involving exposure above 10CFR 20 limits should be voluntary and limited to once in a lifetime.
I i 8.3 Through General Employee Training (GET), personnel
( performing an entry shall be aware of the potential l biological effects associated with exceeding a whole l
body acute dose of 25 Ram or more.
8.4 Continuous coverage by a health physics technician may substitute for a radiation work permit.
8.5 If the atmosphere is known or suspected to be oxygen deficient or potentially toxic, appropriate Respiratory Protection Equipment shall be used.
8.6 Appropriate blocking procedures may be waived by the (Interim) Emergency Director in carrying out this procedure.
8.7 The man-rem for the entry should be maintained ALARA.
~9.0 PROCEDURE ,
9.1 Immediate Actions 9.1.1 Health Physics Technician shall l: 9.1.1.1 Discuss the situation with the OSC Coordinator as to the type of job to be
~
performed and location. Find out the maximum allowable dose authorized by the (Interim) Emergency Director for the task involtad.
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1 EP-401 Rev. O Page 3 of 5 VAW/ MPG /rgs
- 9.1.1.2 Determine from the Plant Survey Group Leader the present conditions in the area, if known.
9.1.1.3 Based on conditions in the area, direct personnel as to the Anti-C, respiratory protection and dosimetry to be used in accordance with health physics procedures.
Provide recommendations in work practices that will assist personnel in maintaining exposures ALARA.
9.'l.1.4 Have personnel who volunteered for the job sign in the OSC log book.
9.1.1.5 If airborne radiciodines are present in the working area, inform the Radiation Protection Team Leader so he can determine if potassium iodide tablets are needed in accordance with SP-313~ Distribution of Thyroid Blocking Tablets.
9.1.1.6 Obtain appropriate survey equipment and accompany the individual or group to the working area.
9.1.1.7 'While traveling through the plant, have survey meters on to observe changes in radiation levels.
9.1.1.8 Monitor radiological conditions in the working area. This should include airborne surveys, radiation survoys and contact dose rates on equipmant beir.g handled, if possible.
9.1.1.9 During the emergency repair or operation, estimate the dose being received and inform
-personnel who may be close to exceeding a
. dose guideline. Direct those to limit their exposure by leaving and being replaced by others, if possible. If the HP technician is close to a dose guideline, contact the OSC for additional HP support. If none is
.available, terminate the job if possible and direct the group to leave the area.
. e EP-401 Rev. O Page 4 of 5 VAW/ MPG /rgs
- . 9.2 Follow-Up Actions 9.2.1 Health Physics Technicians shall:
9.2.1.1 Return with the individual or groups when the operation is completed and estimate each individual's total exposures.
!. 9.2.1.2 Report back to the OSC or other designated
- . location.
- 9.2.1.3 Record whole body dose estimates for each person involved.
9.2.1.4 Have dosimetry processed so that the actual dose may be known. ,
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 NURCG 0654, Criteria for Preparation and Evaluation Rev. 1 of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
10.3 EP-313 Distribution of Thyroid Blocking (KI) Tablets 10.4 NCRP Report No. 39 Basic Radiation Protectiort Criteria 0
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i EP-401, Rev. O Page 5 of 5 VAW/ MPG /rgs
. APPENDIX EP 401-1 Emergency Exposure Guidelines t'
i Projected i Whole Body Thyroid' Authorized
- Function Dose Dose By
- l. 1. Life Saving and (Interim) i Reduction of Injury 75 rem
- 375 rem Emergency **
Director
- 2. Operation of Equipment l l- to Mitigate an (Interim) l Emergency 25 rem
- 125 rem Emergency **
' Director 6
- 3. Protection of Health (Interim)
I.
and Safety of the Public 5 rem 25 rem Emergency **
! Director (Interim)
- 5. Re-entry / Recovery Station Station Activities Administra- Adminis-i tive Guide- trative
! lines Guide- N/A
. lines 4
Reference:
EPA-520/1-75-001 Table 2.1
- Such exposure shall be on a voluntary basis i
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.- l EP-500 Rev. O l Page 1 of 4 VA PG/rgs PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PIAN IMPLEMENTING PROCEDURE ,
EP-500 REVIEW AND REVISION OF EMERGENCY PLAN 1.0 PURPOSE This procedure describes the method for annual review of the Emergency Plan and the incorporation of any necessary
.- revision.
2.0 RESPONSIBILITIES 2.1 The Superintendent, Nuclear Generation shall appoint an Emergency Plan reviewer.
2.2 The reviewer shall review the Emergency Plan in accordance with this procedure.
3.0 APPENDICES None 4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT None 6.0 SYMPTOMS None l
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EP-500 Rev. O Page 2 of 4
. VAW/ MPG /rgs 7.0 ACTION LEVEL 4
None 8.0 PRECAUTIONS None .
9.0 PROCEDURE 9.1 Immediate Actions 9.1.1 The Superintendent, Nuclear Generation, shall appoint one member of the Electric Production Department staff to conduct the annual review of the Emergency Plan.
9.1.2 The ste.ff member shall review the Plan and other documents indicated below and recommend revisions which are required as a result of the following considerat.iony:
9.1.2.1 Written critiques and evaluations of drills and exercises, especially recommended corrective actions.
9.1.2.2 Changes in plant organization, structures or personnel or capabilities.
9.1.2.3 Changes in function, organization of supporting organizations.
9.1.2.4 Changes in State or Federal regulations.
9.1.2.5 Interfaces in State or local emergency plans.
9.1.2.6 Modifications to the plant or site which could affect emergency planning.
9.1.2.7 Recommendations from other organizations, such as state, federal agencies and other utilities, organizations and INPO.
1 9.1.2.8 Changes in construction or operating status.
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EP-500 Rev. O Page 3 of 4 a
VAW/ MPG /rgs 9 9.1.2.9 Significant changes in areas surrounding the site, such as changes in population density or land usage.
9.1.2.10 Adequacy of emergency equipment, training and readiness testing. .
9.1.2.11 Changes in other plant operating or administrative procedures.
9.1.3 The reviewer shall confirm letters of agreement.
9.1.4 The reviewer shall document the results of his review in a letter to the Station Superintendent. The letter shall state the areas reviewed (with those listed above, as a minimum), the results for each area, and the recommended revisions.
.9.1.5 If in the opinion of the person reviewing the plan, only minor changes are needed, the reviewer shall formalize the proposed changes and submit them for review by the Plant Operations Review Committee (PORC).
I 9.1.6 If in the' opinion of the person reviewing the plan, substantial changes are needed, a three-person review committee shall be
, convened by the Superintendent, Nuclear Generation to develop the necessary changes.
The committee'shall consist of one member from the LGS staff, one member from the Electric Production Department not on the LGS staff, and one member appointed by the Euclear Review Board (NRB). The review committee shall recommend the necessary chinges to the Plant Operations Review Committee (PORC), based on the considerations of Steps 9.1.2.1 through 9.1.2.11. -
9.1.6.1 The recommended changes and any additional PORC recommendations shall be presented to
' the Nuclear Review Board (NRB) for approval.
9.1.6.2 P'roposed changes approved by the NRB shall be incorporated into the Emergency Plan by the person or persons who reviewed the Plan or their designees.
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l EP-500 Rev. O Page 4 of 4 ,
, VAW/ MPG /rgs i 9.1.7 Revised pages of the Emergency Plan shall be prepared and shall be distributed to personnel and groups on the Emergency Plan ,
Distribution List. Holders of the Emergency i Plan will be requested to acknowledge l receipt of the revised pages. The receipts ;
shall be returned to the Emergency i l
Preparedness Section, who will ensure proper filing.
9.1.8 Emergency Plan Implementing Procedures shall be revised to reflect any changes in the Emergency Plan'(the Implementing Procedures l- are also reviewed and revised, independent of the annual plan review, according to other prescribed administrative procedures).
Controlled copies of revis' ions shall be distributed in accordance with Administrative Procedures.
9.1.9 If changes to the Emergency Plan affect contract support groups, they should be i informed of these changes.
9.1.10 Discussion of changes shall be incorporated into training programs, as appropriate.
10.0 ' REFERENCES 4
10.1 LGS Emergency Plan 10.2 NUREG 0654, Criteria For Preparation E Evaluation Rev. 1 And Of Radiological Emergency Response Plans Preparedness In Support Of Nuclear Power Plants a
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UNITED STATES I
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8 n NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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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 ivision of Rules and Recor 'g' *I Office of Administration 9
Attachment:
As stated / ,
9
c, a
PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 SHIELDS L D ALTROFF stsc'im'ic"enNw"crion December 12, 1983 Re: Docket Nos. 50-352 50-353 Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Schwencer:
Enclosed are two copies of Limerick Generating Station Emergency Plan Implementing Procedures. These procedures are '
submitted per regulations in 10 CFR 50, Appendix E, Section V.
The procedures being submitted are the following:
EP-110, Rev. O EP-307, Rev. O EP-208, Rev. O EP-312, Rev. O EP-221, Rev. O EP-313, Rev. O EP-251, Rev. O EP-318, Rev. O EP-252, Rev. O EP-319, Rev. O EP-304, Rev. O FP-401, Rev. O EP-305, Rev. O EP-500, Rev. O Pursuant to Section 2.790 of the Commission's regulations, it is hereby recuested that the telephone numbers listed in procedures EP-252, EP-304, EP-305, EP-312 be withhsid from public disclosure. An affidavit setting forth the grounds in support of this request is attached hereto.
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Page 2 Mr. A. Schwencer .
Two copies have been sent under separate cover to the Document control Desk.
Very truly yours,
' Original signed by E L DAL.IROFJ Enclosure cca Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 Site Inspec, tor - Limerick Generating Station O
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EP-llO Rev. 0 Page 1 of 6 VA MP /mla
,,, I nh9 /4G7 PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION (
EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-110 PERSCNNEL ASSEMBLY AND ACCOUNTABILITY 1.0 PURPOSE The purpose of this procedure is to provide the steps necessary when personnel assembly and accountability of PECo personnel and contractors is required when an Alert >
or partial plant evacuation is declared.
This procedure does not apply to Unit 2 Bechtel and sub-contractor personnel since they will be assembled per Bechtel procedures. .
2.0 RESPONSIBILITIES 2.1 PEco personnel and contractors shall report to designated Emergency Assembly Areas for purposes of accountability.
2.2 Emergency Assembly Area Coordinators shall perform an accountability check of personnel at the designated area and report missing persons to
- Security.
2.3 Security shall assemble a list of missing persons for the Emergency Director.
2.4 The Emergency Director shall direct the Personnel Safety Team Leader to activate the Search and l Rescue Group to locate missing personnel.
3.0 APPENDICES 3.1 EP-110-1, Emergency Assembly Arcas 4.0 PREREQUISITES ,
None
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EP-llO Rev. O Page 2 of 6 VAV/ MPG /mla 5.0 SPECIAL EOUIPMENT None ,
6.0 SYMPTOMS None 7.0 ACTION LEVEL This procedure should be implemented whenever an Alert is declared and may be executed when an Unusual Event is declared at the discretion of the Emergency Director.
- After a site evacuation is declared, this procedure no.
! longer applies. ,
8.0 PRECAUTIONS 8.1 Only the following personnel may authorize support personnel without Limerick badges access to the site at an Alert, Site or General Emergency.
8.1.1 Site Emergency coordinator 8.1.2 Emergency Director 8.1.3 Security Team Leader ,
9.0 PROCEDURE
, 9.1 IMMEDIATE ACTIONS 9 .1.' l PECO PERSONNEL AND CONTRACTOR $ shall:
9.1.1.1 Report to the area designated in Appendix
! EP-llO-1, Emergency Assembly Areas, when the announcement for personnel assembly -
occurs. .
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EP-110 Rsv. O Page 3 of 6
. VAV/ MPG /mla 9.1.1.2 Check themselves for contamination if j leaving a radiologically controlled area.
If contaminated, contact Health Physics at the Operations Support Center.
9.1.1.3 Report to_the Emergency Assembly Area Coordinator for purpose of accountability.
l 9.1.1.4 Await further instructions from the Emergency Assemb*y Area Coordinator.
9.1.2 EMERGENCY AREA ASSEMBLY COORDINATORS shall:
9.1.2.1 Perform accountability of personnel. If personnel are unaccounted for, check with the Technical Support Center first for those in your group who may have reported to the Technical Support Center.for
. emergency response roles. -
9.1.2.2 Report to Security the names of those identified as missing, if any. If possible, report the last known location of the missing persons.
9.1.2.3 Await further instructions from the Emergency Director.
9.1.3 Security shall:
9.1.3.1 Contact the Emergency Assembly Areas that have not reported in within 15-30 minutes after the assembly announcement is made.
9.1.3.2 Inform Emergency Director or Interim Emergency Director of the accountability status within 30 minutes after the assembly announcement is made.
e.l.3.3 c Suspend access to the protected area except for those involved in Emergency Response Taams until accountability check is completed. ,
9.2 FOLLOW-UP ACTIONS 9.2.1 Emergency Director or Interim Emergency Director shall:
. ~1 ,
EP-llO Rev. 0 Page 4 of 6 VAV/ MPG /mla i l 1
9.2.1.1 Contact the Pe'rsonnel Safety Team Leader I to activate the Search and Rescue Group if required to locate missing personnel.
9.2.1.2 Contact the Personnel Safety Tohm Leader for status updates. l l
REFERENCES
- - 1.0 Limerick Generating Station Emergency Plan f.
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EP-110 Rev.- ..
? age 5 ot ;I VAV/ MPG /s. l APPENDIX EP-110-1 ,
L';ERGENCY ASSEMBLY AREAS ll Il 1
i r PRIMARY ASSEMBLY AREAS ALTERNATE ASSEMBLY AREAS I GROUP AND TELEPHONE NUMBERS AND TELEPilONE NUMBERS ASSEMBLY AREA COORDINATOR (S)
Technical Support Center None Emergency Director ,
Technical Support Personnel Safety Team Leader Centcr Sta f f : Display Area Ext.
Operations Ad min. Bldg. Senior HP TA/ Technician i HP Technicians Support Center 2ND Floor, IIP &C Area Ext. - Ext.
Control Room Senior Ranking l Plcnt Operators Operations Support P.O., A.P.O., or A.O.
Auxiliary Plant Center Ext.
i Operntors Ext.
Admin Guard Station None Securiti Assistant Security Guards Alt: Captain of the Guard Ex t. Supervisors i
Bechts1 or Norma 1 Working Office None Cubcontractors -
in Restricted .
Arca e
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-110 Pev. 0 ;,
/ age 6 of 6 -
VAV/ MPG* /mla ,,j APPENDIX EP-110-1 *'
Et1ERGENCY ASSEMBLY AREAS PRIMARY ASSEMBLY AREAS ALTERNATE ASSEMBLY AREAS I
_ CROUP AND TELEPHONE NUMBERS AND TELEPilONE NUsiBERS ASSEMBLY AREA COORDINATOR (S)
- trol Operators Control Room Sa fe Shutdown Panels Shift Superintendent it. Control Ext. For Units 1 and 2 Alt: Shif t Superv it;or rotors ft Supervis ton (Only i f Control Room not habitable) ;
- Lietry Cold Lab 217' E1. 2nd Floor Admin Supervisory Chemist or bnicinns B149 Chemistry Office Chemist Ext. .
- 2 ?loid Engineers Field Eng. Office None Senior PECO Supervisory
-)rtcd Plant Gate 3 None Senior Ranking PECO Escort ,
- Itern
- Inistretive Normal Working Of fice None Ad min. Engineer or f f cnd Unescorted in Main Bldg. or Alternate Senior Engineer
.It ra lividunt Supervisors in the Main Bldg. or
- )ex rzport unaccounted for personnel to
'l Main Engineer or Alternate)
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4 .e i EP-208 Rev. O i D Page 1 of 6 VW PG/rgs bEC 119s3 . ,
i
', PHILADELPHIA ELECTRIC COMPANY
?
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~
EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-208 SECURITY TEAM ACTIVATION
[ 1.0 PURPOSE
. The purpose of this procedure is to provide guidelines for
, the activation and conduct of operation for the Security
- - Team, i 2.0 RESPONSIBILITIES 2.1 The Guard Sergeant or alternate shall assume the role of the Interim Security Team Leader and perform the steps of this procedure until relieved by the Security Team Leader.
l 2.2 The Security Team 7;aader shall relieve the Interim Security Team Leader and perform the steps of this
.a procedure not completed by the Interim Security Team ,
Leader.
3.0 APPENDICES
! 3.1 Appendix EP-208-1 Access Control Group Location i
4.0 PREREQUISITES None.
5.0 SPECIAL EQUIPMENT .
None 6.0 SYMPTOMS None
EP-208 Rev. O
- Page 2 of 6 VAW/ MPG /rgs 7.0 ACTION LEVEL This procedure shall be implemented when an Alert or higher classification is declared, a site evacuation is declared or at the discretion of the (Interim) Emergency Director, l
8.0 PRECAUTIONS Nwe
~
9.0 PROCEDURE 9.1 Immediate Actions 9.1.1 The Guard Sergeant shall:
9.1.1.1 Assume the role of the Interim Security Team Leader.
9.1.1.2 Call the Security Team Leader and team members using EP-278 Security Team Phone List, if necessary.
9.1.1.3 Assign available personnel to functional ,
groups as necessary and direct them to perform the appropriate sections of this procedure.
A. Access Control Group (9.2.2)
B. Personnel Accountability Group (9.2.3)
C. Plant Security Group (9.2.4) .
l 9.2 Follow-Up Actions 9.2.L The Security Team Leader shalls 9.2.1.1 Report to the Technical Support Center.
9.2.1.2 Review the current status of the emergency and relieve the Interim Security Leader.
. 9.2.1.3 Ensure that the necessary groups are staffed and performing the appropriate sections of this procedure. Augment groups as necessary.
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EP-208 Rev. O Page 3 of 6 VAW/ MPG /rgs l
.~
9.2.1.4 Advise the (Interim) Emergency Director concerning the need for off-site security personnel, if necessary. Use EP-278 Security Team Phone List for these off-site agencies.
9.2.1.5 Coordinate the actions of off-site security l team personnel if their assistance is required.
9.2.1.6 Have a log maintained throughout the incident.
9.2.1.7 Keep the (Interim) Emergency Director updated on status of the team's activities.
9.2.2 The Access control Group shall:
9.2.2.1 Station a guard at each of the following locations to limit access to the plant when an alert or higher event is declared and a site evacuation is not needed unless the access point is locked:
A. Technical Support Center Personnel Exit Area B. Admin Guard Station Personnel Exit Area C. Main Access Gate (Gate 1)
D. Back Access Gate (Post 10) 9.2.2.2 When a site evacuation is declared, station a guard at the following locations per EP-254 Vehicle and Evacuee Control Group to limit access and to direct traffic flow.
See Appendix EP-208-1 for map locations.
A. Technical Support Center Personnel Exit Area l B. Admin Guard Station Personnel Exit Area C. North Parking Lot D. Post #3 E. Main Access Gate (Gate 1) l F. Gate #2 G. Back Access Gate (Post 10)
EP-208 Rev. O Page 4 of 6 VAW/ MPG /rgs
) ,
9.2.2.3 When a site evacuation is declared, the
!* guards posted at the Technical Support Center and Admin Guard Station Personnel Exit Area shall direct pektonnel to deposit security badges in the buckets provided but to keep dosimetry. If the security computer is not operable, compile a list of the badge numbers of those evacuating as they are leaving.
9.2.3 The Personnel Accountability Group shall:
I 9.2.3.1 In the event of a site evacuation:
~
A. Obtain the security badges or badge list if the computer is not operable of evacuated personnel from the Access Control Group.
B. If the security computer is operable,
' card out' all of the security badges and compile a list of personnel that are onsite.
- c. If the security computer is not operable, determine the personnel onsite. A suggested method is by crossing out all those badge numbers on '
the evacuee list and badges not in use -
from the master badge list and visitor's list.
D. Determine from the guards stationed at the North Parking Lot and Post #3 if any Bechtel/ Subcontractor personnel are unaccounted for.
E. Compile a list of Bechtel/ Subcontractor personnel missing and a list of all those in the protected area from steps B or C. Inform the (Interim) Emergency Director of unaccounted for personnel so that EP-252 Search and Rescue /First Aid can be implemented.
F. Forward the list of unaccounted personnel to the Personnel Safety Team Leader.
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EP-208 Rev. 0 l Page 5 of 6 VAW/ MPG /rgs
- . 9.2.3.2 When personnel are assembled in accordance with EP-llo Personnel Assembly and 4 Accountability and with Bechtel Project Evacuation procedure, check with the Emergency Area Coordinators and security at '
the North Parking Lot and Post #3 15-30 minutes after assembly was called for any unaccounted for personnel and compile a list
. for the Personnel Safety Team Leader.
9.. 5 The Plant Security Group shall:
9.2.4.1 Maintain plant security in accordance with emergency security procedures, and as directed by the (Interim) Emergency Director.
9.2.4.2 In the event of a Partial Plant Evacuation, assist personnel in the evacuation of affected areas.
10.0 REFERENCES
10.1 Limerick Generation Station Emergency Plan i
10.2 Limerick Generating Station Security Plan and Procedures 10.3 EP-278 Security Team Phone List 10.4 EP-254 Vehicle and Evacuee Control Group 10.5 EP-110 Personnel Assembly and Accountability s.
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. VAW/ MPG /rgs
. iii l.
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, MAIN -
- ' ACCESS .,-
- GATE 1
- . # * ,M,3 ..... EMEROENCY p'f.# SUPPORT CINT83 ARIA g, GATE 2 s,
. senAvroNo
- %.s's
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NORTH \.
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PARKING % :
LOT 1-. ,
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TSCHNICAL I POST 3 PARKING y .
, TVROINE $ WILDING 4 UNIT 1 UNtf 3 ,. ,
Mjii-t e6aG. L j '- L p.)l REACTOR
- '" DA'g' $5f'A .
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. 'BACK l. LONGVIEW
. ACCESS ROAD
, GATE j -
! APPENDIX EP-206-1 i
LOCATION OF ACCESS CONTROL POINTS e
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8
~ EP-221 Rev. 0 Page 1 of 4 VAW/ G/ala 7,
PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-221 PERSONNEL DOSIMETRY, BIOASSAY, AND RESPIRATORY PROTECTION GROUP 1.0 PURPOSE The purpose of this procedure is to provide guidelines for the actions of the Personnel Dosimetry, Bioassay and Respiratory Protection Group.
2.O RESPONSIBILITIES ,
2.1 The Personnel Dosimetry, Bioassay and Respiratory Protection Group Leader shall direct the issuance of emergency dosimetry, respiratory protective equipment and direct the bioassay program by performing the necessary steps in this procedure. ,
3.O APPENDICES None .
4.0 PREREQUISITES l
None -
5.0 SPECIAL EQdIPMENT None
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EP-221 Rev. O Page 2 of 4 VAW/ MPG /mla 4
6.0 SYMPTOMS None
- 7.0 ACTION LEVEL The Personnel Dosimetry, Bioassay, and Respiratory Protection Group shall be activated during an emergency whenever there is a need for issuing dosimetry, respiratory protective devices or for bioassay monitoring as determined by the Radiation Protection Team Leader.
8.0 PRECAUTIONS None .
9.0 PROCEDURE 9.1 Immediate Actions i
- 9.1.1 Personnel Dosimetry, Bioassay, and Respiratory Protection Group Leader shall:
9.1.1.1 Report to the TSC and discuss the sit'uation with the Radiation Protection Team Leader.
l WHEN LEAVING THE RESTRICTED AREA, PERSONNEL l ~
REMAINING ON SITE SHALL CARD OR SIGN OUT (IF THE SECURITY COMPUTER IS NOT AVAILABLE) BUT
. KEEP DOSIMETRY. ,
9.1.1.2 Assemb'le the necassary personnel in the Whole Body Counting Room in the TSC for a briefing of the situation.
9.1.1.3 Direct the group to perform the following tasks as necessary.
9.1.1.4 Emergency Dosimetry Issuance A. Take the emer'gency dosimetry devices from storage to the Personnel Entry Area at the TSC.
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. EP-221 Rev. O Page 3 of 4 l- -
VAW/ MPG /mla B. Coordinate with Security, issuing
, dosimetry to emergency team personnel and off-site emergency response teams (i.e., ambulance crews, fire-fighting crews, etc.). in accordance with Health Physics Procedures.
C. Maintain a list of the personnel to whom f dosimetric devices are distributed in accordance with Health Physics Procedures.
i- 9.1.1.5 Personnel Bioassay A. Verify that the Whole Body Counter is operational and calibrated. If need be, follow Health Physics Procedures to start up and calibrate the system.
B. Verify that a supply of bion.ssay specimen containers is on hand.. Obtain more containera from the storeroom if needed.
C. Perform Whole Body Counts or collect bioassay samples from these individuals who are directed to report by the Radiation Protection Leader.
MONITOR BACKGROUND RADIATION LEVELS IN THE WHOLE BODY COUNTER AREA. ' IF DOSE RATE EXCEEDS (LATER) MR/HR, THE COUNTER CANNOT BE USED.
- D. Have all personnel entering the Whole Body Counter Room perform a thorou.gh
. frisk. If contamination greater than or i eqinal to 500 eps above background is
{ found, have the person report to the Personnel Decon Area at the Radweste Enclosure 217' or at the Technical Support Center. Contamination less than 500 cpm above background will be red.uced to acceptable levels in the Whole Body Counter Room showerbefore entering the
.. Whole Body Counter.
9.1.1.6 Respiratory Protegtion A. Perform quantitative fit tests as needed.
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- , Page 4 of 4 VAW/ MPG /mla e
B. Distribute respiratory protective equipment in accordance with Health ,
Physics Procedures.
9.2 Follow-up Actions 9.2.1 Personnel Dosimetry, Bioassay, and Respiratory Protection Group shall:
9.2.1.1 Emergency Dosimetry Issuance A. Establish a dosimetric device collection station in the TSC Guard House.
B. Arrange to have dosimetric devices processed in accordance with Health Physics Procedures.
9.2.1.2 Personnel Bioassay A. Have the bioassay samples analyzed.
B. Compare the results of' the bioassay analysis with the most recent analysis performed on the person (if available) prior to the emergency. If internal contamination is identified, notify the .
Radiation Protection Team Leader of the situation.
9.2.1.3 Respiratory Protection A. Recover respiratory equipment and process for re-use in accordance with Health Physics Procedures, as the
, situation permits., ,
9.2.1.4 Report' status and results to the Radiation l
Protection Team Leader.
10.0 REFERENCES
10.1 Limerick Generating Station ' Emergency Plan 10.5 NUKEG 0654 Criteria for Pr'eparation and Evaluation of Rev. 1 Radio)ogical Emergency Response Plans in Suppo't of Nuclear Power Plants.
. N
t 4 .
' EP-251 Rev. O
' ~
. Page 1 of 4 V/ G/mla u # #
PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE-EP-251 PLANT SURVEY GROUP 1.0 PURPOSE The purpose of this procedure is to provide guidelines for the actions of the Plant Survey Group.
i .
2.O RESPONSIBILITIES 2.1 The Plant Survey Group leader shall be responsible to direct the plant survey group squads by performing the i steps in this procedure.
2.2 The Plant Survey Group Squads shall be responsible to conduct surveys as directed by the Plant Survey Group leader.
3.O APPENDICES ,
3.1 EP-251-1, Emergency Exposure Guidelines l
- 4. 0, PREREQUISITES , ,
None 5.0 SPECIAL EQUIPMENT Plant Survey Kit e
6.0 SYMPTOMS ,
None
_ _ - _ - . _. _ .- = - - . _ - _. --. _ -
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- EP-251 Rev. O Page 2 of 4 VAV/ MPG /mla l
7.0 ACTION LEVEL ,
i l 7.1 The Plant Survey Group shall be activated by the p
Personnel Safety Team leader when necessary.
8.0 PRECAUTIONS 8.1 Planned radiation exposures should be limited to the administrative guide levels in Appendix EP-251-1, Emergency Exposure Guidelines.
8.2 Continuous coverage by Health Physics Technicians may be substituted for a Radiation Work Permit.
9.0 PROCEDURE 9.1 Immediate Actions
- 9.1.1 The Plant Survey Group leader shall:
9.1.1.1 Report to the Operations Support Center (OSC) or other assembly area es directed by Personnel Safety Team Leader.
9.1.1.2 Discuss the situation with the Personnel Safety Team leader.
9.1.1.3 Form the necessary number of plant survey squads from available. personnel. A squad shall consist of two individuals at .least one of which is a Health Physics Technician.
. 9.1.1.4 Discuss the situation with each squad, and direct them to specific locations in the
, pl ant '.
t I
9.1.2 Plant Survey Squad members shall:
1 9.1.2.1 Report to the Plant Survey Group leader at the Operations support Center or other assembly area as , directed by Personnel Saf ety Team Leader. -
l 9.1.2.2 Take the necessary survey equipment 'from the l equipment located in the Operations Support Center or normal Health Physics stores.
9.1.2.3 Ensure that the survey equipment is working properly and have the equipment on when traveling through the plant to observe changes in radiation conditions.
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EP-251 Rev. O
. Page 3 of 4 1 VAv/ MPG /mla 9.1.2.4 Ensure that direct reading dosimeters are zeroed before leaving the Operations Support Center.
9.2 Follow-up Actions ,
9.2.1 The Plant Survey Group leader shall:
9.2.1.1 Report results to the Personnel Safety Team leader.
l 9.2.1.2 Provide the plant survey squads with status updates as to changes in plant conditions.
9.2.1.3 Di' rect the plant survey squa'ds to other locations as necessary.
9.2.1.4 Inform the Personnel Safety Team leader for the need of additional. personnel if.
necessary. .
9.2.2 Plant Survey Squad members shall:
i 9.2.2.1 Conduct surveys as directed by Plant Survey Group Leader, use the methods outlined in Health Physics Procedures- modified as i necessary to minimize exposure to survey squads.
9.2.2.2 Report survey results to the Plant Survey Group leader.
9.2.2.3 Post areas , as necessary, to prevent the
, spread of contamination and accumulation of l
large doses of radiation to operating' personnel.'
9.2.2.4 Report to the Operations Support Center or other assembly area for further instructions from the Personnel Safety Team leader.
10.0 REFERENCES
~
10.1 Limerick Generating Station Emergency Plan 10.2 NUREG 0654, Criteria for Preparation and Evaluation of Rev. 1 Radiological Emergency Response Plans in support of nuclear power plants.
L L...-
t EP-251, Rev. O L
Page 4 of 4 l-o VAV/ MPG /mla APPENDIX EP 251-1 Emergency Exposurc Guidelines l
Projected -
Whole Body Thyroid Authorized Function Dose Dose By
- 1. Life Saving and Reduction of Injury 75 rem
- 375 rem Emergency **
Director
- 2. Operation of Equipment to Mitigate an Emergency 25 rem
- 125 rem Emergency **
Director i .
- 3. Protection of Health
( and safety of the Public 5 rem 25 rem Emergency Director
- 5. Re-entry / Recovery Station Station -
Activities Administra- Administra- -
tive Guide- tive Guide-lines lipes N/A
Reference:
EPA-520/1-75,001 Tabl e 2.1
- Such exposure shall be on a voluntary basis D
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EP-252 Rev. 0
- Page 1 of 12 VAW G/rgs L PHILADELPHIA ELECTRIC COMPANY -
LIMERICK GENERATING STATION
- EMERGENCY PLAN IMPLEMENTING PROCEDURE e
EP-252 SEARCH AND RESCUE /FIRST AID 1.0 PURPOSE The purpose of this procedure is to define the requirements and the actions of the Search and Rescue /First Aid Group.
2.0 RESPONSIBILITIES 2.1 The Personnel Safety Team Leader 'shall control the Search and Rescue /First Aid Group exposure and provide offsite medical support by performing the necessary steps in this procedure.
2.2 The Search and Rescue /First Aid Group Leader shall
- direct operations by performing the necessary steps in l .
this procedure. -
i 2.3 The Search and Rescue /First Aid Group members shall perform rescue operations by performing the necessary steps in this procedure.
3.0 APPENDICES .
l 3.1 EP 252-1 Emergency Exposure Guidelines 3.2 EP 252-2 First Aid Equipment Locations 3.3 EP 252-3 Injured Personnel Report Form
> 3.4 EP-252-4 Medical Support Group Phone List N
e 4.0 PREREQUISITES None i
_ - - - =g - , -- - - . + - . , . _ . _ . _ . --_.m-_ __ --- -
EP-252 Rev. 0
. Page 2 of 12 VAW/ MPG /rgs 5.0 SPECIAL EQUIPMENT 5.1 First Aid Kit ,
6.0 SYMPTOMS 6.1 Missing personnel or personnel with injury requiring first aid.
q 7.0 ACTION LEVEL 7.1 The Search and Rescue /First . Aid Group is activated whenever personnel are known to be missing or in need of help.
8.0 PRECAUTIONS 8.1 Personnel shall participate in search and rescue operations on a voluntary basis.
8.2 Proper radiological controls shall be followed as much as practicable during search and rescue operations.
Continuous coverage by Health Physics tech,nician may be substituted for a Radiation Work Permit.
8.3 Planned radiation exposures should be limited to the administrative guide levels in Appendix EP-252-1 Emergency Exposure Guidelines.
8.4 Lif e-saving first ai'd treatment has priority ov'e r decontamination or treatment for radiation exposure.
8.5 Radiation exposure and groep member contamination should be minimized as much as practical.
8.6 If gross external contamination is found, internal contamination should be suspected.
- 8.7 Any material removed from a contaminated person shall' be recovered for potential *use for isotopic analysis.
8.8 The Search and Rescue /First' Aid Group Leader will t: maintain contact with the Personnel Safety Team Leader i at the designated assembly area. .
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4 EP-252 Rev. O Page 3 of 12 VAW/ MPG /rgs
- 8.9 If first aid team is unable to move an injured person )
due to the nature of the injury, assistance of local l ambulance personnel may be utilized. i 9.0 PROCEDURE
- 9.1 IMMEDIATE ACTIONS 9.1.1 Personnel Safety Team Leader shall:
9.1.1.1 Select a qualified person at the OSC to be the Search and Rescue /First Aid Group Leader and to carry out Section 9.1.2 of this procedure.
9.1.1.2 Inform the Interim Emer'gency Director or the Emergency Director that search and' rescue /first aid groups have been formed and of their intentions to enter the plant for search and rescue operations. (Attempt to
- locate missing person (s) by utilizing plant paging system just prior to actually 4
dispatching the search and rescue group (s)). +
9.1.1.3 Obtain exposure limits from the Emergency Director. If later search and rescue operations are necessary, the Emergency Director may adjust the radiation exposure limits accordingly. If waiting for Emergency Director approval could endanger personnel, the search and rescue /first aid group leader may decide to remove injured person.
e 9.1.1.4 If of fsite medical help is necessary, have the ambulance, hospital or physician contacted by using Appendix EP-252-4 Medical Support Groups Phone List. Always state the number of individuals involved, type of injury and if contamination is involved.
~
9.1.1.5 Notify . security so that the offsite medical '
response group's access to the Restricted Area can be expedited, if necessary.
I l 9.1.1.6 Recall the search and rescue groups when
! search and rescue operations are no longer necessary.
- - . - - . . -. ~- - - -
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EP-252 Rev. 0 l Page 4 of 12 VAW/ MPG /rgs 9.1.2 Search and Rescue /First Aid Group Leader ,
. shall:
9.1.2.1 Selact volunteers from available personnel to form search and rescue /first aid squads. ,
Each squad ~ shall consist of at least three l members; two must be qualified in first aid and one must, be a health physics . technician.
9 9.1.2.2 Ensure that each member has the' necessary respiratory equipment, radsurvey equipment, anti-contamination clothing, and personal 9 dosimetry. This material can be obtained from amargency survey kits at the OSC or l from normal HP stocks.
9.1.2.3 Discuss the situation with the Personnel Safety Team Leader. Th's following information should be obtained prior to performing search and rescue operations:
A. Number of missing persons.
B. Name of individuals.
C. Last' known location of individuals .
D. The job being worked. .
E. Any significant plant conditions that may affect the search and any special instructions.
9.1.2.4 Ensure the. group is equipped with a first aid kit,.or can get one enroute. See attached Appendix EP-252-2 for listing of first aid equipment location in the plant.
9.1.'2. 5 -Coordinate search and rescue /first aid squads to minimize duplication of effort and unnecessary radiation exposure.
9.1.2.6 Direct the groups' to the last known location
. .of the missing individual. If necessary, expand the search to adjacent areas. Ens ure most expeditious . routes available are taken .
to minimize team exposure.
9.1.2.7 Inform the Personnel Saftey Team Leader of the actions of the group and whenever the l
group locates any missing personnel, and the l identity of located personnel.
l
EP-252 Rev. O Page 5 of 12 VAW/ MPG /rgs l l
9.1.2.8 Determine the extent of the injury and direct administration of first aid.
9.1.2.9 Report to the Personnel Saf ety Team Leader the extent of the individual's injuries and recommend supplementary medical actions as necessary (i .e . , hospitalization) . Complete Appendix EP 252-3 (if possible) and attach to injured person prior to transporting in ambul ance .
9.1.2.10 Direct the first aid group to transport the
- I injured person to a site first aid f acility, '
if practicable.
Locations:
A. Radwaste Building," Elevation 217'. ,
B. In Administration Building elevation 217'.
9.1.2.11 Report to the Personnel Safety Team Leader when the search and rescue /first aid group has finished its task. . ,
9.1.3 Search and Rescue /First Aid Squad Members shall: .
9.1.3.1 Perform a radiation and contamination survey of the person and subsequently the area.
9.1.3.2 Transport the injured person to a site first
. aid f acility if practicable. .
9.1.3.3 Perform the following if the injured person is contaminated.
A. Weat necessary anti-contamination clothing if practicable.
IF THE INJURY.IS SEVERE, IPMEDIATE MEDICAL TREATMENT IS OF THE HIGHEST -
PRIORITY AND. RADIOLOGICAL CONTROLS ARE SECONDARY.
l B. . Adm.'nister appropriate first aid, being l' careful to limit the spread of contamination and limit personal e xposure .
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l EP-252 Rev. O Page 6 of 12 VAW/ MPG /rgs C. IF INJURY IS NOT SEVERE, DECONTAMINATION SHALL BE ATTEMPTED.
D. Prepare the person for transportation by covering the contaminated area with a protective wrap. Avoid excessive wrapping to prevent dehydration of the person.
IF THE INJURED PERSON IS GOING TO BE TRANSPORTED TO AN OFFSITE 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.
E. When transporting tIhe victim to an of f site medical f acility, a Health Physics Technician shall accompany the victim to assist the medical staff.
9.1.3.4 Recover any contaminated articles of I clothing that may have been removed from the person for isotopic analysis. >
9.2 Follow-Up Actions 9.2.1 Search and rescue group members shall:
9.2.1.1 Report results of their actions to the Personnel Safety Team Leader.
9.2.1.2 Follow M:rn si decontamination and disposal proca6ee <> . hen their tasks are complete.
l 9.2.2 Personnel Safety Team Leader shall:
l -
l 9.2.'2.1 Verify the victim's arrival at the medical facilities.
9.2.2.2 Inform the Emergency Director of results of
!- search and rescue efforts. -
9.2.2.3 Have the Health Physics t'echnician jl. accompanying victim to the hospital,-call
( the Personnel Safety Team Leader when
! informed by the hospital that his nrvices
~ are no. longer needed. With the concurrence of the Personnel Saf ety Team Leader he say prccede to another assignment.
l . . .
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EP-252 Rev. O Page 7 of 12 VAW/ MFG /rgs
, 9.2.2.4 Arrange for inventory and restocking of first aid kits, if necessary.
.9.2.3 The Emergency Director shall:
9.2.3.1 Have the Medical Director and Corporate Communications informed of the identify and condition of the victim (s).
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 NUREG 0654, criteria for Preparation and Rev.1 Evaluation of Radiological Emergency Response Plans and Preparedness In o Support of Nuclear Power Plants.
o 4
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4 e
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- . .. . . . . - . u.. . . . - ~. .u . ~a EP-252-1 Rev. 0
.. Page 8 of 12 VAW/ MPG /rgs APPENDIX EP 252-1 Emergency EKDosure Guidelines -
3, J'
Projected Whole Body Thyroid Authorized Function Dose Dose Bjr ,
- 1. Life Saving and Reduction of Injury 75 rem
- 375 rem Emergency **
Director
' t
- 2. Operation of Equipment to Mitigate an Emergency 25 rem
- 125 rem Emergency **
, Directo.r
- 5. Re-entry / Recovery Station Station Administra- Adminis-Acti viti es tive Guide- trative *
. lines Guide-lines N/A
- References EPA-520/1-75-001. Table 2.1
- Such exposure shall be on a voluntary basis O
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9 I
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EP 252-2 Rev. 0 Page 9 of 12 VAW/ MPG /rgs APPENDIX EP-214-2 FIRST-AID EQUIPMENT LOCATIONS FIRFT AID STRETCHERS KITS BLANKETS Unit 1 RX Encl. Elevator Stairwells Elev. 177' X X X Elev. 201' X X X Elev. 217' X X X Elev. 239' X X X Elev. 253' X X X Elev. 283' X X X Elev. 313' X X X Elev. 351' X X X Elev. 352' X ,
X X Unit 2 RX Encl. Elevator Stairwells -
Elev. 177' X X X Elev. 201' X X - X Elev. 217' X X X Elev. 239' X X X Elev. 253' X X X Elev. 283' X ,
X X ,
Elev.'313' X X X Elev. 331' X X X Elev, 352' .
t urbine Encl . East '& West Stairwells Elev. 200' X
^
Elev. 217' X Elev. 239' X Elev. 269.'" X ,
Turbine Encl.
Equipment Hatch Elev. 217' X X l
i L 1 L i
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EP 252-2 Rev. O Page 10 of 12 VAW/ MPG /rgs FIRST AID STRETCHERS KITS BLANKETS Control Enclosure Elevator Stairwells Elev. 190' X X X Elev. 200' X X X Elev. 217' X X X Elev. 239' X X X Elev. 254' X X X Elev. 269' X X X Elev. 289' X X X Elev. 304' X X X Elev. 332' X X X Radwaste Encl. North Stairwell +
Elev. 162' X X Elev. 191' X X Elev. 217'
- X X Elev. 237' X X Elev. 257' X X Cire. Water Pump House X 220 Switchyard Encl . X 500 Switchyard Encl . X - ,
"n-T
~
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 252-3, Rev. 0
- Page 11 of 12 VAW/ MPG /rgs APPENDIX EP 252-3 INJURED PERSONNEL REPORT FORM (PREPARE IN DUPLICATE)
Injured Person's Name Age Badge No. Or Social Security No.
Male Female
- 6 Type and Location of Injury e
Radioactive Contamination Yes No Level Location
, 1 Radiation Exposure Estimate where Did Injury Occur Prepared by First Aid Group Leader SIGNATURE
~
~ Group Members If practicable forward original, with the person, to the site first aid f acility or hospital as anpropriate. ,
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EP 252-4, Rev. 0
- Page 12 of 12 VAW/ MPG /rgs.
APPENDIX EP 252-4 i
MEDICAL SUPPORT GROUP PHONE LIST l
Local Physicians Office Home I Dr . Charles W . Dcip ,
Dr. Arthur Mann Pottstown Memorial Medical Center (Contaminated or otherwise) 1 1600 E. High St. '
Pottstown, PA 19464 ,
Radiation Management Corocration (Serious Conthminatioc/or Exposure',
i multiple contaminated personnel) .
l Dr. Roger E. Linneman Preferred Alternate l
l \
Ambulance Goodwill Ambulance Co. <
l j
- Serious Contamination / Exposure is:
l Whole, Body Exposure greater than 25 REM or skin exposure l greater than 150 REM or extremity exposure greater than 375 REM or contamination causing body contacted reading of greater than 1 MR/HR or suspected or actual inhalation or ingestion of measurable quantities of radioactive material.
l . l I
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. EP-304 Rev. O Page 1 of 4 W/ /rgs PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PIAN IMPLEMENTING PROCEDURE EP-304 PARTIAL PLANT EVACUATION ,
1.0 PURPOSE The purpose of this procedure is to define the actions to be perf 6rmed in the event that a partial plant evacuation is required due to uncontrolled hazards in two or more , operating areas.
RESPONSIBILITIES 2.0 2.1 Personnel in affected areas requiring evacuation shall evacuate the area and notify the control room.
2.2 The Interim Emergency Director or Emergency Director shall direct the partial plant evacuation by performing the appropriate steps in.this procedurn. ,
3.O APPENDICES None
- 4. 0' PREREQUISITES ,
None 5.0 SPECIAL EQUIPMENT .
None ,
. . . . _ _ _ . . . _ ..-m_m_._ . , . . _ .
'...__.__.,_mm. .
y.. .
3 EP-304 Rev. 0
- Page 2 of 4
. VAW/ MPG /rgs 6.0 SYMPTOMS 6.1 An increase in the area radiation monitors or continuous air. monitor indications to greater than j alarm' levels in two or more large operating areas . <
6.2 Radiation levels greater than 100 mR/hr within two or more large operating areas which normally experience less than 10 mR/hr.
6.3 Airborne radioactivity greater than 3NG uCi/cc for an unidentified isotope, (except for noble gas activity) or 10 MPC for identified isotopes in restricted areas
- in two or more large operating areas.
6.4 Release, laakage or spill of a toxic reagent such that the concentration of chemical vapors makes the areas uninhabitable in two or more large operating areas.
l 6.5 Other hazards such as flood or fire aff ecting two or i more large operating areas 7.0 ACTION LEVEL This procedure shall be implemented by the Interim Emergency Director or Emergency Director when the symptoms of section 6.0 of this procedure occur. Two or more large operating areas is defined as two or more elevations in a single enclosure or one elevation in two or more enclosures.
=
8.0 PRECAUTIONS
- None 9.0 PROCEDURE I
9.1 Immediate Actions 9.1.1 Personnel in the affected area not directly' involved in controlling the hazard shall l
evacuate to a saf,e area. Notify the control room of the type and location of the hazard.
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EP-304 RGv. O
- Page 3 of 4 VAW/ MPG /rgs 9.1.2 The (Interim) Emergency Dir9ctor or Shift Supervision shall:
9.1.2.1 Upon receiving information f rom personnel in the field that a hazardous condition or from control ro'om indications, evacuate the affected areas. Assemble personnel for purposes of accountability per procedure EP-110, Personnel Assembly and Accountability by making the following announcement:
"This (is) (is not) a drill. This (is) (is not) a drill. This is a Partial Plant Evacuation. Evacuate (locations of hazard ) .
All personnel report to Emergency Assembly Areas. This (is) (is not) a drill. This (is) (is not) a drill."
9.1.2.2 If the hazard has a potential to spread to Unit 2, evacuate construction notifying Bechtel Safety @ personnel by r Bechtel Security ( Direct them to call for either:
PARTIAL EVACUATION - ASSEMBLY AREA between the Main Construction Office ,
and the Change Ecuse.
TOTAL PROJECT EVACUA't'.ON - ASSEMBLY AREAS at the upper parki' , lot and Post #3.
9.2 Follow-Up Actions 9.2.1 The (Interim) Emergency Director shall:
9.2.1.1 Evaluate the situation and if conditions
, worsen call for an evacuation of the site in
( accordance with procedure EP-305 Site Evacuation.
9.2.1.2 If the hazard can be contained and when conditions ' permit , perform recovery / cleanup operations in accordance with EP-401 Entry ,
for Emergency Repair and Operations.
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EP-304 Rev. O
~
~ . Page 4 of 4 VAW/ MPG /rgs
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 NUREG 0654 Criteria for Preparation and Rev. 1 Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 10.3 EP-110 Personnel Assembly and Acccantability 10.4 EP-305 Site Evacuation 10.5 Bechtel Evacuation Procedures 10.6 EP-401 Entry for Emergency Repair and Operations l
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, . j EP-305 Rev. O Pa e 1 of 4 V / MPG /rgs PHILADELPHIA ELECTRIC COMPANY v' LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE I i
EP-305 SITE EVACUATION 1.0 PURPOSE The purpose of this procedure is to define the actions to be performed if a site evacuation is required.
2.0 RESPONSIBILITIES 2.1 The Emergency Director or Interim Emergency Director shall direct the evacuation of the site by performing the necessary steps in this procedure.
j .
2.2 Security shall perform accountability of personnel during the evacuation.
2.3 Bechtel/ Subcontractor personnel shall evacuate in accordance with Bechtel procedures. - '
2.4 Non-essential Unit 1 personnel shall exit through the secorrity areas and assemble at Post #3 prior to leaving the rita.
3.0 APPENDICES
- None 4.0 PREREQUISITES None l
5.0 SPECIAL EQUIPMENT None
- l. - __ _ _ __-_ ___ __ _ - . - . . . - -. . _ . . . , ,
9 l
)
EP-305 Rev. O !
Page 2 of 4 VAW/ MPG /rgs 6.0 SYMPTOMS 6.1 General Emergency has been declared.
6.2 An ac*.ual or potential release exceeding that specified as an Alert or Site Emergency levels in EP-101 Classifications of Emergencies.
6.3 Major toxic or hazardous gas release.
7.0 ACTION LEVEL This procedure shall be implemented when a symptom of section 6.0 occurs or at the discretion of the Emergency Director or Interim Emergency Director.
8.0 PRECAUTIONS None 9.0 PROCEDURE 9.1 Immediate Actions 9.1.1 Emergency Director or Interim Emergency Director shall:
9.1.1.1 Notify security that a site evacuation is being initiated and to carry out applicable security procedures.
9.1.1.1 Implement the evacuation of the information l center in accordance with EP-3 tion l l
l %heInformationCenter.
9.1.1.3 For an actual or potential adverse radiological c~ondition, inform the Personnel Safety Team Leader and direct him to prepare for a site evacuation in accordance with EP-
, 254 Vehicle And Evacuee Control Group.
l 9.1.1.4 Inform Bechtel Safety hat a site evacuation is being call .
l
j EP-305 Rev. O l Page 3 of 4 i VAW/ MPG /rgs 9.1.1.5 Select the Assembly Areas and Unit 1 exit points from the following:
Assembly Areas Unit 1 Exit Points Day Shift Upper Parking Lot and Post 3 TSC and Admin Bldg Afternoon Shift Upper Parking Lot and Post 3 Admin Bldg Night Shift Post 3 Admin Bldg 9.1.1.6 Direct the activation of the alarm in accordance with EP-301 Operating the Evacuation Alarm and River Warning System.
9.1.1.7 When the Personnel Safety Team leader is ready if needed per step 9.1.1.3, announce a site evacuation as follows:
" ATTENTION ALL PERSONNEL. THIS (IS)(IS NOT)
A DRILL. THIS (IS)(IS NOT) A DRILL. THIS IS A SITE EVACUATION. EMERGENCY TEAMS REPORT TO DESIGNATED AREAS. NON-ESSENTIAL UNIT 1 PERSONNEL EXIT THROUGH THE (TSC)
(AND) (ADMIN BUILDING). PERSONNEL ASSEMBLE AT THE (UPPER PARKING LOT) (AND) (POST 3).
THIS (IS)(IS NOT) A DRILL. THIS (IS)(IS NOT) A DRILL."
~
9.1.1.8 After the alarm has stopped, repeat steps 9.1.1.6 and 9.1.1.7.
9.1.1.9 Direct the workers at the RMC facility on
~
Fricks Lock Road to evacuate. '
9.2 Follow-Up Actions 9.2.1 Security shall:
9.2.1.1 Perform accountability of personnel in accordance with EP-209 Security Team l Activation.
l 9.2.1.2 Inform the Emergency Director or Interim Emergency Dire'ctor of unaccounted for personnel.
1
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EP-305 Rev. O Page 4 of 4 ,
, VAW/ MPG /rgs l 9.2.2 Emergency Director or Interim Emergency Director shall:
9.2.2.1 Direct the Personnel Safety Team Leader to initiate search and rescue operations for any unaccounted for personnel in accordance with EP-252 Search & Rescue /First Aid.
9.2.3 Bechtel/ Subcontractor Personnel shall:
9.2.3.1 Evacuate in accordance with Bechtel procedures.
4 9.2.4 Non-Essential Unit 1 personnel shall:
9.2.4.1 Exit the protected area through the Admin Guard House or Technical Support Center by carding out but retaining dosimetry unless otherwise instructed.
9.2.4.2 Report to the Post #3 area for evacuation instructions f rom Security. -
10.0 REFERENTS. ,
10.1 Linarick Generating Station Emergency Plan 10.2 NUREG 0654, Criteria for Preparation and Evaluation of Rev. 1 Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
10.3 EP-252 Search and Rescue /First Aid ,
10.4 EP-lOl Classification of Emergencies 10.5 EP-254 Vehicle And Evacuee Control Group 10.6 EP-30'l operating the Evacuation Alarm and River Warning System 10.7 EP-306 Evacuation of th"e Information Center l
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EP-307 Rev. O Page 1 of 3 VAV/M /mla r
L 4,i p'/p PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION i EMERGENCY PLAN IMPLEMENTING W DDRE l I
EP-307 RECEPTION AND ORIENTATION OF SUPPORT PERSCHNEL
, 1.0 PURPOSE This' procedure defines the actions to be taken to receive and train those support personnel who will be coming on site to respond to an emergency.
2.0 RESPONSIBILITIES
- 2.1 The Planning and Scheduling Coordinator shall direct the reception and orientation of support personnel by performing the necessary steps in this procedure.
2.2 Personnel from the Nuclear Training Section or their' contractors shall train the support personnel by
, performing the necessary steps in this procedure.
3.0 APPENDICES None 440 PREREQUISITES ,
4.1 Emergency Support Center or other reception area is -
activated .
1
- j. 4.2 Off-site personnel needed for assistance and arriving at the reception area.
5.0 SPECIAL EQUIPMENT L None k
6.0 SW.PTOMS www,- * - ---e-- C "-" -
_ _ _ _ . ,___2 -. . . . _ - . - _. _ . _ _ . . - _ _ . . _ . . - _ ._ -
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. . EP-307 Rev. O
- Page 2 of 3 VAV/ MPG /mla f
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6.0 SYMPTOMS None 7.0 ACTION LEVEL i
This procedure shall be implemented when the arrival of off-site support personnel requested by the Philadelphia Electric Company is anticipated and the Emergency Support Center or other reception area is activated.
8.s PRECAUTIONS J
None 9.0 PROCEDURE 9.1 Immediate Actions 9.1.1 Planning and Scheduling Coordinator shall:
9.1.1.1 Direct the Security Team Leader to assign a Security Team Member to report to the Emergency Support Center or othdr designated '
area to issue security badges in accordance with Security procedures. ,
9.1.1.2 Direct the Radiation Protection Team Leader
~
to assign a Personnel Dosimetry, Bioassay,
. Respiratory Protection Group Member t'o report to the Emergency support center or other designated area and issue dosimetry in accordance with Health Physics procedures.
9.1.1.3 Direct Training personnel through the h Training Coordinator to report to the Emergency Support Center.
9 . 2, Follow-up Actions , ,
9.2.1 Training personne,1 shall:
9.2.1.1 Request from the Planning and Scheduling L ( Coordinator information regarding the team p or staff to which the Support personnel are E to report.
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VAV/ MPG /mla '.'
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i l
t 9.2.1.2 Recuest from the Planning and Scheduling ',
l Coordinator information regarding the plant ,
status. }
L 9.2.1.3 Assemble personnel in the classroom and provide them with the following information: \-
A. Basic description of the plant status.
B. Work shif t hours they will be assigned to.
C. Arrangements for hotels, meals and transportation.
D. Person to whom they are to report.
9.2.1.4 With the same group conduct a General Employee Training Class. Also, if necessary, conduct a General Respiratory Training Class and Respiratory Fit' Test.
9.2.1.5 conduct training sessions on special topics as necessary such as use of potassiun iodide
. tablets , evacuation plans , etc. ,
9.2.1.6 Contact appropriate Station personnel :
assigned the responsibility for supervising the support personnel. Request authorization to release personnel to these Station personnel and have them meet the support personnel at the entrance of the Technical Support Center, if activated or the Administration Building Guard Station.
9.2.2 Planning and Scheduling Coordinator shall:
9.2.2.1 Inform the Site Emergency Coordinator and
- Emergency Director when the designated
. Support personnel have been properly indoctrinated and trained and are ready for.
work in the plant or on the sit's. ,
l' L
REFERENCES" ' "
10.1 Limerick Generating Station Emergency Plan j i
- . . . . _ . . . ~ . . . . ~ . . . . _ - . . - . - - - - - -
. t EP-312 Rev. O Page 1 of 4 VAW. PG/rgs
' 1/fh/L5 PHILADELPHIA ELECTRIC COMPANY '
LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-312 RADIOACTIVE LIQUID RELEASE 1.0 PURPOSE The purpose of this procedure is to provide guidelines for ,
the actions to be taken when an uncontrolled liquid release of radioactive material occurs.
2.0 RESPONSIBILITIES f =
2.1 The (Interim) Emergency Director shall direct the steps necessary to terminate the liquid release and evaluate the consequences of the release performed.
2.2 The Site Emergency Coordinator, if activated, or (Interim) Emergency Director shall direct the follow-up actions of notification of downstream water users and river sampling, i f they are required.
3.0 APPENDICES J None 4 . 0,. PREREQUISITES None 5.0 SPECIAL EQUIPMENT l None 4
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- EP-312 Rev. O Page 2 of 4 VAW/ MPG /rgs 6.0 SYMPTOMS 6.1 An actual or suspected liquid release of radioactive material with a concentration greater than 1.5N5 uci/cc (500 times the maximum MPC for any unidentified -
. isotope in water).
6.2 Radwaste discharge radiation monitor exceeds alarm setpoint of 1.4N4 uCi/cc.
7.0 ACTION LEVEL 7.1 This procedure shall be implemented when a liquid release occurs exceeding the criteria in section 6.0.
I i
8.0 PRECAUTIONS None
- 9.0 PROCEDURE
- t 9.1 Immediate Actions '
9.1.1 The (Inte' rim) Emergency Director shall:
9.1.1.1 Direct the immediate steps necessary to terminate the discharge to the river.
9.1.1.2 Direct the Chemistry Sampling and Analysis Team Leader to initiate sampling of the
- . blowdown line in accordance with EP-236, Obtaining Blowdown Line Water Samples Following Radioactive Liquid Release After
, Accident Conditions, or to sample the river just downstream of the liquid discharge.
9.1.1.3 Direct the Dose Assessment Team Leader to estimate dose" projections from the ingestion of drinking water and fish in accordance
, with EP-318, Liquid Release Dose Calculation
! Method for Drinking Water and EP-319, Fish Ingestion Pathway Dose Calculation.
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EP-312 Rev. O
! Page 3 of 4 l VAW/ MPG /rgs
! 9.2 Follow-Up Actions 9.2.1 The Site Emergency Coordinator, if activated or (Interim) Emergency Director shall:
9.2.1.1 Based on results of estimated dose projections for downstream water users and fish ingestion, have the Department of Environmental Resources notified.
A.
B.
C. _ .(Jtegional office) 9.2.1.2 If requested by the Department of Environmental Resources, direct the notification of the downstream domestic water users in EP-287 Nearby Public and Industrial Users o.f Downstream Waters.
9.2.1.3 If necessary, direct the Environmental Sampling Coordinator if activated, or Chemistry Sampling And Analysis Team Leader to have the river water near the intake for the following water companies'at the '
appropriate time based on the Transit Time for that 1ccation.
The Transit Time is the time required for the material released to reach the location of interest.
Location Transit Time (hrs)
A. Citizens Utilities Home 1.5 Water Company-Royersford i B. Phoenixville Water 10 l
C. Philadelphia Suburban 16 Water .
D. Norristown Water 27 E. Philadelphia Belmont Water 50 t 9.2.1.4 Direct that a log be kept for all samples taken.
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EP-312 Rev. O Page 4 of 4 )
VAW/ MPG /rgs 4
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 EP-236 Obtaining Blowdown Line Water Samples Following Radioactive Liquid Release After Accident Conditions 10.3 EP-318 Liquid Release Dose Calculation Method For Drinking Water
. 10.4 EP-319 Fish Ingestion Pathway Dose Calculation 10.5 EP-237 Nearby Public And Industrial Users Of
- Downstream Waters 10.6 EROL Appendix 5.2A Radiological Dose Model-Liquid Effluents 10.7 10CFR Part 20 Appendix B i
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s EP-313 Rev. O Page 1 of 8 PG/rgs VA PHILADELPHIA ELECTRIC COMPANY j e', / "hDh et LIMERICK GENERATING STATION -
EMERGENCY PLAN IMPLEMENTING PROCEDURE
, EP-313 DISTRIBUTION OF THYROID BLOCKING TABLETS 1.0 PURPOSE The purpose of this procedure is to provide guidelines for the administration of potassium iodide (KI) to on-site personnel performing a necessary TAS for use as a thyroid blocking agent to provide protection against airborne radioiodine.
2.0 RESPONSIBILITIES l '
! 2.1 The Radiation Protection Team Leader shall determine if potassium iodide is required and direct the t
administration of the tablets by performing the necessary steps in this procedure.
2.2 The Personnel Dosimetry, Bioassay and Respiratory '
Protection Group Leader shall administer. the potassium _ -
iodide tablets by perfcraing the necessary steps in this procedure.
j 3.0 APPENDICES 3.1 EP-313-1 Potassium Iodide Work Sheet'
- l 3.2 EP-313-2 Potassium Iodide Administration Record Form 3.3 EP-313-3 Potassium Iodide Consent Form 3.4 EP-313-4 Instruction And Record Sheet For Persons Receiving KI ,
4.0 PREREQUISITES
) None 1
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. . VAW/ MPG /rgs 5.0 SPECIAL EQUIPMENT 5.1 Potassium Iodide tablets not beyond the expiration date.
3 6.0 SYMPTOMS 6.1 An actual or potential thyroid dose equal to or griater than 10 REM.
7.0 ACTIONk2 VEL
. This procedure shall be implemented by the Radiation Protection Team Leader when an actual or potential thyroid dose is equal to or greater than 10 REM for any individual.
8.0 PRECAUTIONS 8.1 The taking of potassium iodide (KI) tablets is voluntary for each individual involved.
8.2 Personnel having allergic reactions to iodine should be administered potassium iodide only if absolutely necessary.
8.3 Prior to administering potascium iodide, ensure that the tablets are not beyond the expiration date.
8.4 All persons using potassium iodide should be familiar l with the following possible side effects and report any noticed side effects to Radiation Protection Team Leader.
8.4.1 Skin rashes 8.4.2 Swelling of parotid glands (like mumps) 8.4.3 Metallic taste in mouth 1
8.4.4 Burning mouth and throat 8.4.5 Sore teeth and guns 8.4.6 Symptoms of a head cold 8.4.7 Gastric upset.
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.7 EP-313 Rev. O Page 3 of 8 VAW/ MPG /rgs 8.4.8 Diarrhea 9.0 PROCEDURE
, 9.1 Immediate Actions .
9.1.1 Radiation Protection Team Leader shall:
9.1.1.1 Determine the need for administering potassium iodide by completing Appendix EP-313-1 Potassium Iodide Worksheet for each individual needed to perform the task.
9.1.1.2 Discuss with the (Interim) Emergency Director that potassium iodide is needed and obtain his concurrence prior to the
, administration of the tablets.
9.1.1.3 Enter the names of each individual on Appendix EP-313-2 and direct the Personnel l
Dosimetry, Bioassay and Respiratory Protection Group Leader to administer the tablets per section 9.2.1 of this procedure.
9.2 Follow-Up Actions 9.2.1 The Personnel Dosimetry, Bioas'say and Respiratory Protection Group Leader shall:
9.2.1.1 When directed by the Radiation Protection Team Leader, assemble the personnel to be treated at the Technical Support Center or other area and acquire an adequa$e supply of tablets from the Medical Facility or Decon Area in Radwaste.
9.2.1.2 Discuss with personnel the possible side effects of potassium iodide and that taking
, the tablets is voluntary. Determine if any 1
' personnel are aware of an allergy ~ to iodine.
If an individual is allergie, discuss the situation with the Radiation Protection Team Leader. .
9.2.1.3 Have each individual sign a copy of Appendix EP-313-3 Potassium Iodide Consent Form,
- - unless one is already on file.
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, VAW/ MPG /rgs 7
9.2.1.4 Administer to personnel who already have been exposed to radioiodine first, preferably within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of exposure. The recommended dosage is 130 mg potassium I iodide (100 mg iodide) per day for a minimum )
of three days but preferably 10 consecutive days.
9.2.1.5 Provide each individual receiving KI with a copy of Appendix EP-313-4 Instruction And Record Sheet For Persons Receiving KI and instruct them to report back each day for follow-up dosages. This form is for the individuals information only and is not needed to receive additional dosages.
9.2.1.6 Comple'te the information required for each person on Appendix EP-313-2 Potassium Iodida Administration Record Form. Use this information to administer follow-up dosages.
! 9.2.1.7 Inform the Radiation ?rotection Team Leader l when completed.
l 9.2.2 Radiation Protection Team Leade'r shall:
9.2.2.1 Notify the Medical Director and Emergency Director of all persons who received ~
9.2.2.2 Ensure that the potassium iodide is i administered in the proper dosage and for the proper number of doses.
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan - Section 6.4.2.3 10.2 NUREG 0654 criteria for Preparation and Evaluation Rev. 1 of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 10.3 Reg. Guide 1.109 Calculation of Annual Doses to Man Rev. 1 from Routine Releases of Reactor i Effluents for the Purpose of Evaluating Compliance with 10 CPR Part 50, Appendix I
l EP-313 Rev. O Page 5 of 8 VAW/ MPG /rgs APPENDIX EP-313 l POTASSIUM IODIDE WORK SHEET Date: Time:
Name:
Badge Number Area To Be Entered:
I-131 Concentration (uCi/cc) in Affected Area:
Respiratory Equipment (Check one)
TYPE PROTECTION FACTOR (PF)
Air Purifying 50 Atmosphere Supplying 2000 SCBA 10,000 None 1 Time Needed To Complete Task: Hours Previous Thyroid Dose Accumulation During Emergency: REM Perform Calculation: . ,
Total Thyroid Dose = 1.361P6 x Concentration I-131 x Task Time x 1 (REM) / uCi (Hours) PF--
Q cc
+ Previous Thyroid Dose (REM)
Total Thyroid Dose = Rem If Dose equals or is greater than 10 Rem, recommend administration of potassium iodide.
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EP-313 Rev. O
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. APPENDIX EP-313-3 POTASSIUM IODIDE CONSENT FORM I volunteer to receive 130 milligrams per day for the next 10 days of the thyroid blocking agent potassium lodide. I have been informed by a representative of PECo that this drug will block the absorption of radio-iodine by my thyroid and thereby reduce the exposure to radiation of the thyroid; that potassium does not reduce the uptake of other
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radioactive materials by the bodyr nor, does it provide protection against exposure from external radiation. I also understand that there may be some side effects upon taking this drug.
Signature Date 4
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APPENDIX EP-313-4 INSTRUCTION AND RECORD SHEET FOR PERSONS RECEIVING KI 1,
Name Badge No.
CAUTION IF YOU FZEL SICK, REPORT IMMEDIATELY TO THE
[ PERSONNEL DOSIMETRY, BIOASSAY AND RESPIRATORY f PROTECTION GROUP LEADER.
You have just received 130 mgs. of the thyroid blocking agent KI. !
In order to be most effective you should receive an additional nine (9) doses over the next 9 days. Each day for the next 9
. days, take this form and report to the for a thyroid count and another KI pill.
1 130 mg KI Tablet Thyroid Count Results Administered Date (Date, Time, Initials) (Date, Time, Initials) 1.
2.
. 3.
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EP-318 Rev. O Page 1 of 8 VA , PG/rgs sl.4/05 l PHILADELPHIA ELECTRIC COMPANY l LIMERICK CENERATING STATION EMERGENCY PLAN IMFLEMENTING PROCEDURE
. EP-318 LIQUID RELEASE DOSE CALCULATIONS METHOD FOR DRINKING WATER 1.0 PURPOSE The purpose of this procedure is to provide the calculation method for estimates of population exposure due to the
. ingestion of drinking water at various locations downstream of the plant.
2.0 RESPONSIBILITIES None 3.0 APPENDICES 3.1 EP-318-1 Citizen Utilities Home Water Company Intake 3.2 EP-318-2 Phoenixville Water Intake 3.3 EP-318-3 Philadelphia Suburban Water Company Intake ,
3.4 EP-318-4 Norristown Water Intake 3.5 EP-318-5 Philadelphia Belmont Water Intake 4.0 PREREQUISITES i
None .
- l 5.0 SPECIAL EQUIPMENT -
None p.
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EP-318 Rev. 0 F69e ?. of 8 VAW/ MPG /rgs g 6.0 SYMPTOMS 6.1 An actual or potential licuid release of radioactive material into the Schuylkill River.
7.0 ACTION LEVEL i 7.1 This procedure shall be implemented when the criterion of section 6.0 is met.
8.0 PRECAUTIONS
, None l 9.0 PROCEDURE i
l 9.1 The following assumptions were utilized in this j calculation:
9.1.1 The Dose Conversion Factor is based on the most limiting group (adult, teen, child, infant) using dose factors and consumption rates in Reg. Guide 1.109.
Adult 730 1/yr Teen 510 1/yr Child 510 1/yr Infant 330 1/yr 9.1.2 The Decay Factor is based on the decay of the isotope over the transit time plus 12
. hours (time to reach the population.via water system per Reg. Guide 1.109).
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EP-318 R3v. O Page 3 of 8 VAW/ MPG /rgs
(
9.1.3 The total dose commitment is the dese which an individual weuld receive af ter drinking water with the radionuclides present at the concentrations calcuiuted to exist at the entrance to the wa?:r plant for a period equal to the duration of the release. Fo r example, if the release lasted 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the
! individual is postulated to consume 1/2 of his average daily water intake at the 4
diluted concentrations.
l 9.2 Obtain grab sample results on the concentration of Co-60, I-131, Cs-134 and Cs-137 released, from the Chemistry Sampling and Analysis Team Leader.
i 9.3 For each location of interest, enter the concentration of co-60, I-131, Cs-134 and Cs-137 in uCi/cc released and the release duration in hours on the appropriate I appendix.
If the sample was taken prior to entering the Cooling Tower Blowdown Line, a diluted concentration must be
! determined by the following calculation:
I Concentration [uci) " concentration Release rate to Blowdown Line Released *
(ci/ [uci) Blowdown line flow rate
\ ccf 9.4 Perform the calculation in each appendix for each location of interest to estimate the dose in millirem for the liver, whole body and thyroid.
9.5 Report results to the Dose Assessment Team Leader.
. i
10.0 REFERENCES
10.1 EROL 2.1.3.6 Surface Water Use 10.2 EROL.5.2.4.1 Liquid Pathways 10.3 EROL Appendix 5.2A Radiological Dose Model-Liquid Effluents
, 10.4 Reg. Guide 1.109 Calculation of Annual Doses To l, Rev. 1 Man From Routine Releases of Reactor i Effluents For The Purpose Of-Evaluating ;
Compliance With 10 CFR-Part 50, Appendix I
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EP-318 R3v. O Page 5 of 9
- VAW/ MPG /rgs .
APPENDIX EP-318-2 PHOENIXVILLE WATER INTAKE I Dose mR/hr Concentration Decay f Conversion uCi/cc X uCi/cc X Fac tor =
i Factor
$I Liver 406 1.0 O Whole 959 Body .
Liver 1591 ,
p Whole 700 .92
.* Body A
%yroid 5.23P5 1
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[ Liver 2.64P4 1.0 e ,
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e4 Liver 2.30P4 1.0 a whole 5942 U Body ,
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Liver ;
Whole Body 1.0 .0118 t
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EP-318 Rav. 0 . I I Paqo 6 of 8 VAW/ MPG /rgs . .,
I APPRNDIX EP-318-3 PHILADELPHIA SUBURBAN WATER COMPANY INTAKE '
Dose mR/hr Concentration Decay s!
Conversion uCi/cc X uCl/cc X Factor = i ~I Factor o Liver 406 -
1.0 }'
- Whole 959 '
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1591 - '
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l Usage Factor X Duration (hrs) X Factor X = Dose (mR) [,
Liver Whole Body .22 .0149 {
i Myroid - I Date [
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EP-318 R v. O ,
Page 7 of 8 VAW/ MPG /rqa ,
.t APPEMDIX EP '318-4 NORRISTOWN WATER INTAKE Dose mR/hr Concentration Decay Conversion uCt/cc X uCi/cc X Factor = 1 Factor .
O Liver 406 1.0 0 mole 959 Body ,
Liver 1591 -
N Whole 700 .87 7
Body -
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. EP-319 Rev. O Page 1 of 4 VAW PG/rgs l
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PHILADELPHIA ELECTRIC COMPANY oflf} l LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-319 FISH INGESTION PATHWAY DOSE CALCULATION 1.0 PURPOSE ,
The purpose of this procedure is to provide the calculation method for estimates of the maximum population exposure due to the ingestion of fish from the Schuylkill River.
2.0 RESPONSIBILITIES None 3.0 APPENDICES 3.1 EP-319-1 Maximum Dose From Fish Ingestion 4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT None 1
6.0 SYMPTDMS
. 6.1 An actual or potential liquid release.of radioactive L material into the Schuylkill River.
7.0 ACTION LEVEL 7.1 This procedure shall be implemented when the criterion of section 6.0 is met.
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. EP-319 Rev. O Page 2 of 4 l VAW/ MPG /rgs B.O PRECAUTIONS None 9.0 PROCEDURIE j 9.1 The following assumptions were utilized in this calculation:
9.1.1 The Dose Conversion Factor is based on the most limiting group (adult, teen, child,
. infant) using dose factors and consumption rates in Reg. Guide 1.109. ,
Adult 21 kg/yr Teen 16 kg/yr Child 6.9 kg/yr Infant 0 kg/yr 9.1.2 The Decay Factor is based on the decay of the isotope over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (time to reach the population per Reg. Guide 1.109.
9.1.3 The total dose commitment is the dose which an individual would receive after eating fish exposed by the highest concentration of diluted effluent for the duration of the release.
9.2 Obtain grab sample results on the concentration of Co-60, I-131, Cs-134, Cs-137 and P-32 released, from the Chemistry Sampling and Analysis Team Leader.
9.3, On Appendix EP-319-1, enter the concentration of P-32, Co-60, I-131, Cs-134 and Cs-137 in uCi/cc released and the release duration in hours.
If the sample was taken prior to entering the Cooling Tower Blowdown Line, a diluted concentration must be determined by the following method:
Concentration [ucil . concentration Release rate to Blowdown Line
[
Released \ci / [uci) Blowdown line flow rate u ,
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,1 EP-319 Rev. O Page 3 of 4 VAW/ MPG /rgs 9.4 Perform the calculation on Appendix EP-319-1 to estimate the maximum dose in millirem for the liver, whole body and thyroid for the fish ingestion pathway.
9.5 Report results to the Dose Assassment Team Leader.
10.0 REFERENCES
10.1 EROL 5.2.4.1 Liquid Pathways 10.2 EROL Appendix 5.2A Radiological Dose Model-Liquid Effluents 10.3 Reg. Guide 1.109 Calculation of Annual Doses To Rev. 1 Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance With 10CFR Part 50, Appendix I O
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l EP-319 Rev. .!
l Page 4 of 4 i VAW/ MPG /rgs APPENDIX EP-319-1 MAXIMUM DOSE FROM FISil INGESTION i
Dose Conversion Mixing Done (mR)
Factor x Concentration x Decay r. Release x Factor =
mR/hr uCl Factor Duration Liver Whole Thyroid ,
uCi /cc cc (hrs) body N Liver 3.12P6 m
I A Whole' 2.5P6 .95 .0357 /
Body l Liver 256 ,
O whole 614 1.0 .0357 ! '
Boly Liver 224 s
> m Whole . .92 .0357 7
s Body 122
%yroid 7P4 ,
~s M Liver 7.19P5 0_ Whole 1.0 .0357 Body 5.79P5 S Liver 5.44P5 a
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Body 3.42P5 i
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DATE: Total Dose (mr) i; k
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. EP-401 Rev. O Page 1 of 5 .
V MPG /rgs
, ith/U PHILADELPHIA ELECTRIC CdMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-401 ENTRY FOR EMERGENCY REPAIR AND OPERATIONS 1.0 PURPOSE The purpose of this procedure is to provide guidelines for entering areas for emergency repair and operations that have become adversely affected by the emergency conditions.
2.0 RESPONSIBILITIES 2.1 A health physics technician shall advise personnel of radiological conditions when entry for emergency
. repair and operations is needed.
3.0 APPENDICES
- 3.1 EP-401-1 3mergency Exposure Guidelines" '
4.0 PREREQUISITES y None 5.0 SPECIAL EQUIPMENT None l 6.0 SYMPTOMS Y .
None
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EP-401 Rev. O Page 2 of 5 VAW/ MPG /rgs 7.0 ACTION LEVEL 7.1 This procedure shall be implemented whenever personnel must enter an area of adverse or unknown conditions for reasons of emergency repairs or operation of l
equipment.
8.0 ~ PRECAUTIONS 8.1 No one person shall be left alone during the entry.
8.2 Planned radiation exposures should be limited to the administrative guide levels in Appendix EP-401-1 Emergency Exposure Guidelines. Performance of a task involving exposure above IOCFR 20 limits should be voluntary and limited to once in a lifetime.
~
8.3 Through General Employee Training (GET), personnel performing an entry shall be aware of the potential biological effects associated with exceeding a whole body acute dose of 25 Rem or more.
- 8.4 Continuous coverage by a health physics technician may substitute for a radiation work permit.
8.5 If the atmosphere is known or suspected "to be oxygen deficient or potentially toxic, appropriate Respiratory Protection Equipment shall be used.
8.6 Appropriate blocking procedures may be waived by the (Interim) Emergency Director in carrying out this
( procedure.
1 8.7 The man-rem for the entry chould be maintained ALARA.
9.0 PROCEDURE ,
9.1 Immediate Actions 9.1.1 Health Physics. Technician shall:
9.1.1.1 Discuss the situation with the OSC !
Coordinator as to the type of job to be
( performed and location. Find out the
! maximum allowable dose authorized by the l- (Interim) Emergency Director for the task involved.
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EP-401 Rev. O
- j. Page 3 of 5 VAW/ MPG /rgs 9.1.1.2 Determine from the Plant Survey Group Leader l the present conditions in the area, if l known. l 9.1.1.3 Based on conditions in the area, direct personnel as to the Anti-C, respiratory protection and dosimetry tc de used in accordance with health physics procedures.
Provide recommendations in work practices that will assist personnel in maintaining exposures ALARA.
9.1.1.4 Have personnel who volunteered for the job sign in the OSC log book.
9.1.1.5 If airborne radiciodines are present in the working area, inform the Radiation Protection Team Leader so he can determine if potassium iodide tablets are needed in accordance with EP-313 Distribution of Thyroid Blocking Tablets.
9.1.1.6 Obtain appropriate survey equipment and accompany the individual or group to the working area.
9.1.1.7 ' While traveling through the plant, have survey meters on to observe changes in radiation levels.
9.1.1.8 Monitor radiological conditions in the working area. This should include airborne surveys, radiation surveys and contact dose rates on eauipment being handled, if possible.
9.1.1.9 During the emergency repair or operation, estimats the dose being received and inform personnel who may be close to exceeding a
. dose guideline. Direct those to limit their exposure by leaving and being replaced by l others, if possible. If the HP technician is close to a dose guideline, contact the
! OSC for additional HP support. If none is available, terminate the job if possible and direct the group to leave the area.
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EP-401 Rev. O Page 4 of 5 VAW/ MPG /rgs 9.2 Follow-Up Actions 9.2.1 Health Physics Technicians shall:
9.2.1.1 Return with the individual or group = When the operation is completed and estimate each individual's total exposures.
9.2.1.2 Report back to the OSC or other designated location.
. 9.2.1.3 Record whole body dose estimates for each person involved.
9.2.1.4 Have dosimetry processed so that the actual dose may be known.
10.0 REFERENCES
10.1 . Limerick Generating Station Emergency Plan
, 10.2 NUREG 0654, Criteria for Preparation and Evaluation Rev. 1 of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants. ,
10.3 EP-313 Distribution of Thyroid Blocking (KI) Tablets 10.4 NCRP Report No. 39 Basic Radiation Protaction Criteria i
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O EP-401, Rev. O Page 5 of 5 VAW/ MPG /rgs ,
APPENDIX EP 401-1 Emergency Exposure Guidelines Projected Whole Body Thyroid Authorized Function Dose Dose By
- 1. Life Saving and' (Interim)
Reduction of Injury 75 rem * . 375 rem Emergency **
Director
- 2. Operation of Equipment to Mitigate an (Interim)
Emergency 25 rem
- 125 rem Emergency **
Director
Director
Activities limits limits Emergency Director
- 5. Re-entry / Recovery Station Station Activities Administra- Adminis- '
tive Guide- trative lines Guide- N/A lines
Reference:
EPA-520/1-75-001 Table 2.1
- Such exposure shall be on a voluntary basis s
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EP-500 Rev. 0 Page 1 of 4 VA , PG/rgs PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION l EMERGENCY PLW IMPLEMENTING PROCEDURE ,
EP-500 REVIEW AND REVISION OF EMERGENCY PLtd 1.0 PURPOSE T *; procedure describes the method for annual review of the Emergency Plan and the incorporation of any racessary revision.
2.0 RESPONSIBILITIES 2.1 The Superintendent, Nuclear Generation shall appoint an Emergency Plan reviewer.
2.2 The reviewer shall review the Emergency Plan in accordance with this procedure.
3.0 APPENDICES None 4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT None 6.0 SYMPTOMS
. None L:
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EP-SOO Rev. O Pago 2 of 4 VAW/ MPG /rgs 7.0 ACTION LEVEL .
None 8.0 PRECAUTIONS None 9.0 PROCEDURE 9.1 Immediate Actions 9.1.1 The Superintendent, Nuclear Generation, shall appoint one member of the Electric Production Department staff to conduct the annual review of the Es.orgency Plan.
9.1.2 The staff member shall review the Plan ar.d other documents indicated below and recommend revisions which are required as a result of the following considerations:
9.1.2.1 Written critiques and evaluations of drills '
and exercises, especially recommended corrective actions.
9.1.2.2 Changes in plant organization, structures or personnel or capabilities.
9.1.2.3 Changes in function, organization'of supporting organizations.
9.1.2.4 Changes in State or Federal regulations.
9.1.2.5 Interfaces in State or local emergency plans.
9.1.2.6 Modifications to the plant or site which could affect emergency p1anning.
9.1.2.7 Recommendations from other organizations, such as state, federal agencies and other utilities, organizations and INPO.
9.1.2.8 Changes in construction or operating status.
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EP-500 Rev. O Page 3 of 4 VAW/ MPG /rgs i
L 9.1.2.9 Significant changes in areas surrounding the site, such as changes in population density or land usage.
9.1.2.10 Adequacy of emergency equipment, training
! and readiness testing.
9.1.2.11 Changes in other plant operating or administrative procedures.
t 9.1.3 The reviewer shall confirm letters of agreement.
! 9.1.4 The reviewer shall document the results of his review in a letter to the Station Superintendent. The letter shall state the areas reviewed (with those listed above, as a minimum), the results for each area, and the recommended revisions.
9.1.5 If in the opinion of the person reviewing the plan, only minor changes are needed, the reviewer shall formalize the proposed -
changes and submit them for review by the Plant Operations Review Committee (PORC).
9.1.6 If in the' opinion of the person reviewing :
the plan, substantial changes are needed, a three-person review comnittee shall be convened by the Superintendent, Nuclear Generation to develop the necessary changes.
The committee shall consist of one member i from the LGS staff, one member from the
! Electric Production Department not on the LGS staff, and one member appointed by the Nuclear Review Board (NRB). The review committee shall recommend the necessary changes to the Plant Operations Review Committee (PORC), based on the
. considerations of Steps 9.1.2.1 through 9.1.2.11.
9.1.6.1 The recommended changes and any additional .
PORC recossendations shall be presented to the Nuclear Review Bcard (NRB) for approval.
9.1.6.2 Proposed changes approved by the NRB shall be incorporated into the Emergency Plan by '
the person or persons who reviewed the Plan or their designees.
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EP-500 Rev. O ,
Page 4 of 4 VAW/ MPG /rgs 9.1.7 Revised pages of the Emergency Plan shall be prepared and shall be distributed to personnel and groups on the Emergency Plan Distribution List.' Holders of the Emergency Plan will be requested to acknowledge receipt of the revised pages. The receipts shall be returned to the Emergency Preparedness Section, who will ensure proper filing.
9.1.8 Emergency Plan Implementing Procedures shall be revised to reflect any changes in the Emergency Plan'(the Implementing Procedures are also reviewed and revised, independent of the annual plan review, according to other prescribed administrative procedures).
Controlled copies of revisions shall be
, distributed in accordance with Administrative Procedures.
9.1.9 If changes to the Emergency Plan affect I contract support groups, they should be informed of these changes.
9.1.10 Discussion of changes shall be incorporated into training programs, as appropriate.
i 10.0 'EFERENCES R
10.1 LGS Emergency Plan 10.2 NUREG 0654, Criteria For Preparation & Evaluation Rev. 1 And Of Radiological Emergency Response Plans Preparedness In Support Of Nuclear Power Plants 9
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