ML021910033
| ML021910033 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/02/2002 |
| From: | Casey Smith Pennsylvania Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| EP-PS-106, Rev 9 | |
| Download: ML021910033 (29) | |
Text
Jul. 02, 2002 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2002-3185 USER INFORMATION:
TLAI÷LAUPLEL P EMPL#:23244 CA#: 0386 Phone#: 254-3658 TRANSMITTAL INFORMATION:
TZO: FLAIM*LAUREL B 07/02/2002 LOCATION: DOCUMENT CONTROL DESK FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER NUCSA-2)
.HE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:
106 - 106 - HEALTH PHYSICS SPECIALIST (DUTY FOREMAN): EMERGENCY PLAN-POSITION SPECIFIC PROCEDURE REMOVE MANUAL TABLE OF CONTENTS DATE: 05/24/2002 ADD MANUAL TABLE OF CONTENTS DATE: 07/01/2002 CATEGORY: PROCEDURES TYPE: EP ID: EP-PS-106 ADD: PCAF 2002-1440 REV: N/A UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON RECEIPT OF HARD COPY. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
PROCEDURE CHANGE PROCESS FORM
- 1. PCAF NO. 2002-1440 I2. PAGE 1 OF 6 3. PROC. NO. EP-PS-106 REV. 9
- 4. FORMSREVISED - C R 6 - R , R , R -, R , R
- 5. PROCEDURE TITLE Health Physics Specialist: Emergency Plan Specific Instruction
- 6. REQUESTED CHANGE PERIODIC REVIEW NO [-] YES INCORPORATE PCAFS [ NO E-1 YES # #_# #
REVISION PCAF Z DELETION '- (CH gdl<NE ONLY)
- 7.
SUMMARY
OF! REASON FOR CHANGE 'AA This PCAF replaces the term "'assembly"with "accountability" to be con,,.,,, nt with changes made in Revision 39 of the Emergency Plan.
Sections impacted are major tasks list; supporting information list;,,"d TAB .,
Continued
- 8. DETERMINE COMMITTEE REVIEW REQUIR§M 111p,, !=,, , i R'AUIR ""*,**T6 (Refer to Section 6.1.4)
PORC REVIEW REQ'D? Z'%N6 C YES 9. PORC MTG# na
<.,',,:,,' ,. iK*;l, ' Jf ;'
BLOCKS 11 THRU 16 ARE ON PA F61oRM
- 17. Cynthia Smith I[ 1 0=6/1412002 18. COMMUNICATION OF CHANGE REQUIRED?
PREPARER ........" T,Ni~ DATE [NO F-1 YES (TYPE)
(Print or Type) i:
- 19. ........ SIGNATURE ATTESTS THAT RESPONSIBLE SUPERVISOR HAS 19.~ j "-CONDUCTED QADR AND TECHNICAL REVIEW UNLESS OTHERWISE
__________DOCUMENTED IN BLOCK 16 OR ATTACHED REVIEW FORMS.
CROSS DISCIPLINE REVIEW (IFREQUIRED) HAS BEEN COMPLETED RESPONSIBLE' RVISOR - BY SIGNATURE IN BLOCK 16 OR ATTACHED REVIEW FORMS.
- 20. U, h/ /,0oZ IL-7LFUM APPROVAL DATE
- 21. RESPONSIBLE APPROVER ENTER N/A IF FUM HAS APPROVAL AUTHORITY NAL, INITIALS DATE FORM NDAP-QA-0002-8, Rev. 8, Page 1 of 2 (Electronic Form)
PROCEDURE CHANGE PROCESS FORM
- 1. PCAF NO. 2002-1440 12. PAGE 2 OF 6 13. PROC. NO. EP-PS-106 REV. 9
- 11. This question documents the outcome of the 50.59 and 72.48 Review required by NDAP-QA-0726. Either 1 a, b, c or d must be checked "YES" and the appropriate form attached or referenced.
- a. This change is an Administrative Correction for which 50.59 and 72.48 are not -' YES I N/A applicable.
- b. This change is a change to any surveillance, maintenance or administrative Z YES - N/A procedure for which 50.59 and 72.48 are not applicable. j \
- c. This change is bounded by a 50.59/72.48 Screen/Evaluation, therefore, no new ' YES [ N/A 50.59/72.48 Evaluation is required.
Screen/Evaluation No.
- d. 50.59 and/or 72.48 are applicable to this change and a 50.59/72.48 D YES Z N/A Screen/Evaluation is attached.
- 12. This change is consistent with the FSAR or an FSAR change is required. I YES Change Request No. na
- 13. Should this change be reviewed for potential effects on Training Needs or Material? "- YES [ NO If YES, enter an Action Item @ NIMS/Action/Gen Work Mech/PICN
- 14. Is a Surveillance Procedure Review Checklist required per NDAP-QA-0722? -" YES Z NO
- 15. Is a Special, Infrequent or Complex Test/Evolution Analysis Form required per - YES I NO NDAP-OA-0320? (SICT/E form does not need to be attached.)
- 16. Reviews may be documented below or by attaching Document Review Forms NDAP-QA-01 01-1.
REVIEWED BY WITH DATE REVIEW NO COMMENTS QADR TECHNICAL REVIEW REACTOR ENGINEERING/NUCLEAR FUELS
- IST *-_
OPERATIONS NUCLEAR SYSTEMS ENGINEERING NUCLEAR MODIFICATIONS MAINTENANCE HEALTH PHYSICS NUCLEAR TECHNOLOGY CHEMISTRY OTHER 10CFR50.540 . I I Required for changes that affect, or have potential for affecting core reactivity, nuclear fuel, core power level indication or impact the thermal power heat balance. (0)
, Required for changes to Section XI Inservice Test Acceptance Criteria.
FORM NDAP-QA-0002-8, Rev. 8, Page 2 of 2 (Electronic Form)
04A EP-IPS-106 Revision 9 Page 2 of 3 HEALTH PHYSICS SPECIALIST Emergency Plan-Position Specific Procedure (DUTY FOREMAN):
WHEN: Technical Support Center (TSc) is activated HOW NOTIFIED: Paged, on- and off-hours
- REPORT TO: Radiation Protection Coordinator (RPC) then Damage Control Team Coordinator (DCTC)
WHERE TO REPORT: TSC OVERALL DUTY:
Assess rad conditions within the restricted area and provide radiological and ALARA guidance to in-plant (India) teams.
MAJOR TASKS: TAB: REVISION:
Obtain briefing from the RPC and DCTC. TABA 4 Determine radiological conditions within the TAB B 5 plant and restricted area.
Assess onsite habitability - TSC, * ;/"l TAB C T areas, evacuation routes, and gatehouses.
Brief the RPC and DCTC when there are TAB D0 2 significant changes in radiological conditions onsite.
Prepare for team dispatch. TAB E 3 Provide guidance and brief teams on TAB F 2 radiological and ALARA considerations.
Monitor in-plant (India) team activities, TAB G 3 exposures, and reported survey measurements.
Coordinate the packaging and transportation TAB H of accident samples for onsite and/or offsite analysis.
Debrief team on radiological conditions TAB I encountered.
Coordinate vehicle decontamination. TAB J I
EFP-PS-106 Revision 9 Page 3 of 3 SUPPORTING INFORMATION: TAB:
Emergency Telephone Instructions TABI Emergency Organization TAB2 Logkeeping TAB3 SSES Contamination Plan TAB4 Emergency Facility Form Flow TAB5 Habitability o"Assembly Areas and Evacuation Routes-.
TAB 6 I
PPL Emergency Personnel Dose Assessment and TAB 7 Protective Action Recommendation Guide PersonnelIAsemblyea Accountability TAB 8 Preparation for India Team Dispatch TAB9 Emergency Forms TAB 10
"* Emergency Exposure Extension Request
"* Potassium Iodide (KI) Tracking Form
"* Emergency Plan Radiation Work Permit Accident Sample Packaging and Transportation TAB 11
REFERENCES:
SSES Emergency Pil an IE Notice 88-15 Approved Potassium Iodide for use in Emergency Involving Radioactive Iodine NUREG-0654, Planning Standards and Evaluation Criteria NURIEG-0731, Guidelines for Utility Management Structure and Technical Resources, September 1980 HP-TP-801, General Shipment of Radioactive Material
PA&F.,.~OLFi# TAB C EP-PS-1 06-C RevisionOr" Page 1 of 2 MAJOR TASK:
Assess onsite habitability - TSC, assembly areasjevacuation routes, and gatehouses. IQ SPECIFIC TASKS: HOW:
- 1. Establish contamination controls and 1a. Direct the performance of routine smears surveys of the TSC. and air samples.
lb. Direct the placement of step off pads and friskers at doorways during releases or if plant status warrants.
NOTE:
Frisking pads should be set up at the stairwell door, north end of the TSC, with the frisker located appropriately. Access to the TSC from the elevator should be prevented by placing signs in the elevator.
Hang "FRISKING REQUIREMENTS" signs at each end of the TSC. Update the signs as radiological conditions warrant I c. Direct HP personnel located on elevation 676' of the control structure to ensure personnel reporting to the TSC from the tunnel access use the contamination monitors if release conditions warrant 1d. Direct the decontamination of the TSC or arriving personnel as necessary.
- 2. Assess habitability of accountability HELP areas and evacuation routes. Personnel -Asembly-a,,
Accountability See TAB 8 jI4~ba-+b;IsDy4?
Aras 1 ssem-6/y A beds4" A/4L4'4 Rouvs 5-ie e. rAB 6
M2 AAO TAB C EP-PS-106-C RevisionA f, Page 2 of 2 SPECIFIC TASKS: HOW:
- 3. Assess habitability of gatehouse or 3a. If the gatehouses or Security Control other facilities on site. Center is in the plume pathway, instruct the Security Coordinator to place the ventilation systems in recirculation, isolating the intake.
3b. If dose rates warrant, contact the Security Coordinator to evacuate structure(s).
TAB 4 EP-PS-1 06-4 SSES CONTAMINATION RESPONSE PLAN TABLE OF CONTENTS PAGE 1.0 OVERVIEW 2 2.0 DEFINITIONS 2 3.0 CONTAMINATION ASSESSMENT 3 4.0 DECONTAMINATION 5 4.1 Building, Structure, Removable Equipment 5 4.2 Water 5 5.0 RELEASE CRITERIA IN RESTRICTED AREA 6 5.1 Structures and Equipment 6 5.2 Personal Property 7 EP-AD-000-133, Revision 2, Page 1 of 7
TAB 4 EP-PS-106-4 SSES CONTAMINATION RESPONSE PLAN 1.0 OVERVIEW This plan describes actions to be taken in response to emergency conditions which result in deposition of radioactive contamination as a result of a release from the Susquehanna Steam Electric Station. Deposition may be within the restricted area, within the site boundary, offsite or a combination of these.
This plan considers only actions to be taken which are PPL's responsibility and does not describe emergency response agency actions outside the PPL site boundary or public protective action implementation.
This plan is applicable when an emergency condition has been declared at SSES, an accidental release of radioactive material has occurred and the release has been terminated.
Ground contamination occurs as a result of the deposition of radioactive particulate material released into the atmosphere. It may be in the form of particulates at the time of release or it may result from the decay of gaseous radionuclides. Since these materials, and the resultant dose rates, may persist for an extended period of time following termination of a release, qualitative and quantitative analysis is necessary to assess long-term exposures. In addition, variability of levels within the affected area is expected to be high, due to meteorological and terrain conditions, and ultimately may require days or weeks of sampling to ensure adequate characterization.
2.0 DEFINITIONS 2.1 LEGAL SITE BOUNDARY - 'That line beyond which the land is not leased, owned, or otherwise controlled by the licensee."
2.2 RESTRICTED AREA - The area encompassed by the inner security fence.
2.3 EMERGENCY PLAN BOUNDARY - Same as the Exclusion Area, i.e. that area around Susquehanna SES within a radius of 1800 feet determined in accordance with 10CFR100.16.
The EPB is used to calculate offsite dose rates, project dose to the public, and to determine necessary Protective Action Recommendations for the public.
2.4 EMERGENCY PLANNING ZONE - An area approximately ten miles in radius around SSES for which emergency planning consideration of the plume exposure pathway has been given in order to ensure prompt and EP-AD-000-133, Revision 2, Page 2 of 7
TAB 4 EP-PS-1 06-4 effective actions can be taken to protect the public in the event of an accident at SSES.
2.5 INGESTION PATHWAY ZONE - An area approximately fifty miles in radius around SSES for which emergency planning consideration for the ingestion exposure pathway has been given.
3.0 CONTAMINATION ASSESSMENT 3.1 Upon termination of a release, the following actions should be done:
3.1.1 Perform smear samples and direct frisk of ground, building and temporary structure surfaces inside the restricted area which are believed to be in the plume pathway in order to determine the extent of the affected area.
Results which exceed 1000 dpm/1 00 cm 2 removable (smear survey) contamination or exceed 100 cpm above background on a frisker shall be designated contaminated.
Affected areas and/or equipment shall be roped/taped off as appropriate and posted as contaminated.
3.1.2 Perform isotopic analysis of a representative sample of onsite smears if not previously performed. Use of portable gamma spectroscopy equipment may be considered to assist in
- characterization of the depositions.
3.1.3 Perform smear samples and direct frisk survey of ground surfaces and all vehicles, equipment, and facilities outside the restricted area and within the site boundary believed to be in the plume pathway to determine the extent of affected areas.
NOTE: Results which exceed 1000 dpm/1 00 cm 2 removable contamination or exceed 100 cpm above background on a frisker shall be designated contaminated.
Use of the portable gamma spectroscopy system may be considered to assist in the characterization of the deposition.
3.1.4 Initiate surveys of building ventilation intakes to determine if airborne radioactive material was drawn into air supply systems.- Surveys of noncontrolled zone areas such as the S&A Building, South Building, trailers, etc. should be performed prior to allowing personnel to re enter these areas. Air conditioners running at the time of the release should also be surveyed.
EP-AD-000-1 33, Revision 2, Page 3 of 7
TAB 4 EP-PS-1 06-4
- a. Initiate surveys of building areas in unrestricted areas (such as APF, SLC, etc.) believed to be in the plume pathway prior to allowing personnel to re-enter these areas.
- b. Perform surveys of the service air and instrument air intakes and components to determine if these systems are contaminated. Air samples from the service air system should also be considered.
Use of supplied air respiratory protection should be prevented until the evaluation is complete.
3.1.5 Direct Chemistry personnel to:
- a. Sample standing water in the storm drainage system, roofs, equipment, pools, etc.
- b. Sample the site drinking water supply. Prevent the use of drinking water until water evaluation is complete.
- c. Initiate sampling of the Sewage Treatment Facility. If influent conditions permit, discharge should be prevented until analysis is complete. Liquid release dose calculations may be required if the discharge cannot be diverted.
3.1.6 Perform contamination surveys of areas outside the site boundary as directed by the Emergency Director or Recovery Manager. The State has primary responsibility for survey of these areas; however, it is expected that PPL assistance will be requested to assist in delineation of affected areas. Survey locations outside the site boundary should be as accurately described as possible by the monitoring teams. Isotopic analysis of a representative sample of smears should be performed as soon as practical.
3.1.7 Perform environmental sampling in accordance with EP-PS-248, Field Team Director.
3.1.8 Consider covering contaminated surfaces (building roofs, grounds and/or equipment) with reinforced plastic covering to minimize the spread of contamination until decontamination can take place.
3.1.9 Plug applicable building roof drains to prevent runoff of contaminated water.
3.1.10 Consider use of bladders to isolate storm drains and/or drainage channels in the event of precipitation. The Spill Response Team and PPC plan maybe used to assist in these actions.
EP-AD-000-133, Revision 2, Page 4 of 7
TAB 4 EP-PS-1 06-4 3.1.11 Request that engineering personnel identify any other normally clean plant systems which may have become contaminated during the release and survey, as necessary.
3.1.12 Coordinate with the Field Team Director to have Ecology-Ill personnel perform soil sampling of affected areas within the site boundary in accordance with the EREMP procedure for soil sampling.
4.0 DECONTAMINATION 4.1 Building(s), Structure(s), Removable Equipment Decontamination 4.1.1 Should be performed as soon as practical following termination of the release.
NOTE: Methods used for decontamination should generate limited quantities of waste water. Run off into the plant drainage system should be avoided if possible. Water generated should be collected, sampled, analyzed and treated as necessary.
4.1.2 Decontamination methods include, but are not limited to:
- a. Wipe down with approved decontamination chemicals
- b. Strippable paint
- c. Washing (water must be collected, sampled and treated, if contaminated, prior to disposal)
- d. Transport of movable equipment into radiologically controlled areas for decon
- e. Fix contamination using paint, plastic sealants, concrete, etc.
- f. Control areas until activity decays to acceptable levels, if release into environment is unlikely 4.2 Water Decontamination 4.2.1 Treatment of contaminated water from the following sources may be required:
- a. Roof drains previously plugged or routed to temporary tanks EP-AD-000-1 33, Revision 2, Page 5 of 7
TAB 4 EP-PS-1 06-4
- b. Water collected in the storm drainage system
- c. Decontamination of buildings, equipment and vehicles
- d. Collected water on site such as in the CST berm or Spray Pond
- e. Hydrolasing and/or flushing of roof drains, drainage systems, etc.
4.2.2 Contractor assistance and a portable demineralizer may be required.
5.0 RELEASE CRITERIA IN RESTRICTED AREA 5.1 Structures and Equipment 5.1.1 Release criteria for structures and equipment inside the Restricted Area are:
- a. Surfaces should be decontaminated to levels below the following:
2 (1) Removable contamination: <1000 dpm/1 00 cm (2) Fixed contamination: <100 cpm above background on a frisker or equivalent instrumentation
- b. If decontamination below these levels is not possible, alternatives include:
(1) Disposal of the material as waste (2) Fix contamination using paint, plastic sealants, etc.
resulting dose rate shall be less than 10 mrem per year (see NOTE on next page).
- c. Ground contamination of soils, rocks, paved surfaces, etc. inside the restricted area should be removed if the area is small. For larger areas, levels which would not result in dose to an individual in excess of 10 mrem/year are acceptable.
NOTE: This guidance is in accordance with NUREG/CR-289, PNL-5429, "Residual Radionuclide Contamination Within and Around Commercial Nuclear Power Plants,"
February 1986.
This level is considered sufficiently low so as not to endanger the health and safety of either SSES site EP-AD-000-133, Revision 2, Page 6 of 7
TAB 4 EP-PS-1 06-4 workers or members of the general public. Records of these areas and final levels of radioactivity must be maintained for the life of the Plant and should be included in the decommissioning plan.
5.2 Personal Property 5.2.1 Contamination levels on personal property being removed from the restricted area, including vehicles, must be reduced to less than the following:
2
- a. Removable - <1000 dpmr/100 cm
- b. Fixed - <100 cpm above background on a frisker (or equivalent instrumentation)
EP-AD-000-133, Revision 2, Page 7 of 7
TAB 6 EP-PS-1 06-6 HABITABILITY OF ACCOUNTABILITY AREAS, ASSEMBLY AREAS, AND EVACUATION ROUTES
- 1. Upon notification of Accountability the Health Physics Specialist will:
- a. Confirm initial habitability of all accountability areas based upon plant radiological conditions, as indicated by local CAMs and ARMs.
- b. Consider the necessity of an alternate (the Control Structure Access Corridor) or remote holding area if readings from radiological instrumentation > 5.OmR/hr and are confirmed by an independent rad survey.
(1) If a remote holding area is required, select an area which is upwind of any actual or potential radiological release.
(a) Susquehanna Energy Information Center - NE Sector.
(b) West Building - WSW Sector.
(2) Inform the Radiological Protection Coordinator.
- c. Establish a habitability monitoring program for those assembly areas that will be used as essential personnel work areas or holding areas to support OSC and TSC operations.
- 2. For site evacuation of non-essential personnel, the Health Physics Specialist shall:
- a. Ensure that evacuation routes are not in the plume pathway.
- b. Recommend alternate evacuation routes to the RPC.
EP-AD-000-192, Revision 1, Page 1 of 1
TAB 7 EP-PS-106-7 PP&L EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE TABLE OF CONTENTS Section Page 1.0 EMERGENCY DOSE LIMITS 2 2.0 EMERGENCY EXPOSURE/ACCIDENTAL OVEREXPOSURE 3 3.0 PROTECTIVE ACTIONS 3 4.0 EMERGENCY EXPOSURE NOTIFICATION AND HEALTH CONSEQUENCE INVESTIGATION 4 EMERGENCY EXPOSURE EXTENSIONS 5 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING AN EMERGENCY 8 EMERGENCY EXPOSURE EXTENSION REQUEST FORM and POTASSIUM IODIDE TRACKING FORM can be found immediately following EP-AD-000-125.
EP-AD-000-125, Revision 7, Page 1 of 10
TAB 7 EP-PS-1 06-7 PP&L EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE (continued)
CHECK 0 1.0 Limits for EMERGENCY doses.
0 1.1 An EMERGENCY DOSE AUTHORIZATION (see EMERGENCY EXPOSURE EXTENSIONS) may be granted in order to protect facilities, and or equipment to substantially limit the escape of radioactive effluents or control fires. The maximum planned doses are:
1.1.1 Whole body (TEDE)(') dose shall not exceed 10 Rem.
1.1.2 Dose to any organ (CDE)(2), including the skin and extremity (SDE)(3),
shall not exceed 100 Rem.
1.1.3 Dose to the lens of the eye shall not exceed 30 Rem (LDE)(4).
0 1.2 An EMERGENCY dose authorization may be granted for life-saving actions or protection of large populations. The maximum doses are:
1.2.1 Planned whole body (TEDE)(') doses shall not exceed 25 Rem.
1.2.2 Planned dose to any organ (CDE)<2), including skin and extremity doses, shall not exceed 250 Rem.
1.2.3 Dose to the lens of the eye shall not exceed 75 Rem (LDE)(4).
1.3 RARE situations may occur in which a dose GREATER THAN those specified in SECTION 1.2 above for emergency dose would be unavoidable to carry out a lifesaving operation or to avoid extensive exposure of large populations. It is not possible to prejudge the risk that one should be allowed to take to save lives of others, therefore no upper limit has been established.
(1) The sum of the Effective Dose Equivalent resulting from the exposure to external sources and the committed effective Dose Equivalent incurred from all significant inhalation pathways during the early phase.
(2) The Committed Dose Equivalent to the thyroid from radioiodine.
(3) Shallow Dose Equivalent.
(4) Lens Dose Equivalent.
EP-AD-000-125, Revision 7, Page 2 of 10
TAB 7 EP-PS-106-7 PP&L EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE (continued)
CHECK 0 2.0 For any EMERGENCY EXPOSURE OR ACCIDENTAL OVEREXPOSURE, the assessment actions in step 2 of the EMERGENCY EXPOSURE EXTENSIONS must be performed.
3.0 PROTECTIVE ACTIONS 0 3.1 Potassium Iodide 3.1.1 For emergency workers entering areas where a committed dose equivalent, (CDE)(2), to the thyroid from radioiodine could be 25 Rem or greater, the Consulting Radiological Physician should provide input concerning the administration and cessation of KI intake. (See Emergency Telephone Directory for telephone number.)
3.1.2 For thyroid exposures that are strongly expected to exceed 25 Rem, (CDE)(2), KI doses of 130 mg (100 mg - iodine) per day should be administered.
Unless the EMERGENCY DIRECTOR or RECOVERY MANAGER instructs personnel to do otherwise, the KI tablets should generally be taken as soon as possible after thyroid exposure exceeding 25 Rem (CDE)(2) is projected.
NOTE: Stable Iodine (KI) is most effective when administered immediately prior to exposure to radioiodine. Significant blockage of the thyroid dose can be provided by administration within one or two hours after uptake of radioiodine.
(1) The sum of the Effective Dose Equivalent resulting from the exposure to external sources and the committed effective Dose Equivalent incurred from all significant inhalation pathways during the early phase.
(2) The Committed Dose Equivalent to the thyroid from radioiodine.
(3) Shallow Dose Equivalent.
(4) Lens Dose Equivalent.
EP-AD-000-125, Revision 7, Page 3 of 10
TAB 7 EP-PS-1 06-7 PP&L EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE (continued)
CHECK 0l 3.1.3 Onsite issuance of KI for iodine prophylaxis requires the approval of the EMERGENCY DIRECTOR. Issuance to EOF and FIELD EMERGENCY MONITORING/SAMPLING TEAM personnel requires the approval of the RECOVERY MANAGER when the EOF has relieved the TSC of emergency management activities. The EMERGENCY DIRECTOR will approve issuance prior to that time.
These approvals must be documented on the POTASSIUM IODIDE (KI) TRACKING FORM.
3.1.4 For an injured and/or contaminated worker sent to a hospital for treatment, the patient will be under the care of the attending physician.
As such, plant procedures no longer apply and KI issuance will be at the discretion of the attending physician. The physician can rely on a senior Health Physics Technician Level II or Health Physics Management to provide the in-plant radiological data on which to base their decision.
0l 3.2 Protective measures should be implemented for EOF personnel at the direction of the DOSE ASSESSMENT SUPERVISOR.
El 3.3. Exposures to members of local offsite support groups, (ambulance workers, fire fighters) shall not exceed 500 mrem (TEDE)(1 )for the performance of support duties on the site of the Susquehanna SES.
4.0 EMERGENCY EXPOSURE NOTIFICATIONS AND A HEALTH CONSEQUENCE INVESTIGATION must be conducted for any emergency exposure as outlined in step 6 of the Emergency Exposure Extensions.
(1) The sum of the Effective Dose Equivalent resulting from the exposure to external sources and the committed effective Dose Equivalent incurred from all significant inhalation pathways during the early phase.
(2) The Committed Dose Equivalent to the thyroid from radioiodine.
(3) Shallow Dose Equivalent.
(4) Lens Dose Equivalent.
EP-AD-000-125, Revision 7, Page 4 of 10
TAB 7 EP-PS-106-7 EMERGENCY EXPOSURE EXTENSIONS CHECK 0l
- 1. 'Fill out the attached EMERGENCY EXPOSURE EXTENSION REQUEST Form.
- 2. Review the following factors:
"El Rescue personnel should be volunteers or professional rescuers.
"El Other considerations being equal (e.g., skill, potential need for person on another mission) personnel above the age of 45 are preferred.
"El Rescue personnel should be familiar and briefed with the consequences of exposure.
"El Women capable of reproduction should not take part in an effort requiring EMERGENCY exposure.
"El Use of personnel with high lifetime cumulative exposure should be discouraged.
"El All reasonable measures must be taken to control contamination and internal exposure.
"El Exposure under these conditions shall be limited to once in a lifetime.
"El For exposures greater than 25 Rem whole body (TEDE), the persons undertaking any emergency operation in which the dose will exceed 25 Rem to the whole body (TEDE) should do so only on a voluntary basis and with full awareness of the risks involved, including the numerical levels of dose at which acute effects of radiation will be incurred and numerical estimates of the risk of delayed effects. See the following two tables for general information concerning Health Effects & Cancer Risks.
EP-AD-000-125, Revision 7, Page 5 of 10
TAB 7 EP-PS-1 06-7 EMERGENCY EXPOSURE EXTENSIONS (continued)
CHECK 0 Health Effects Associated with Whole Body Absorbed Doses Received Within a Few Hours(a)
Whole Body Absorbed Early Fatalitiesb Whole Body Absorbed Prodromal Effectsc Dose (rad) (percent) Dose (rad) (percent affected) 140 5 50 2 200 15 100 15 300 50 150 50 400 85 200 85 460 95 250 98 a Risks will be lower for protracted exposure periods.
b Supportive medical treatment may increase the dose at which these frequencies occur by approximately 50 percent.
c Symptoms (nausea, vomiting) which occur within a few hours after exposure to large doses of radiation and which usually precede more serious health effects.
Approximate Cancer Risk to Average Individuals from 25 Rem Effective Dose Equivalent Delivered Promptly Average Years of Life Lost if Age at Exposure Approximate Risk of Premature Death Premature Death Occurs (years) (deaths per 1,000 persons exposed) (years) 20 to 30 9.1 24 30to 40 7.2 19 40 to 50 5.3 15 5O to 60 1 3.5 11
- 3. Review the HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES which is attached.
- 4. Obtain appropriate approval signatures as outlined in the table below.
EXTENSION APPROVAL ACTIONS FROM TO mrem mrem (TEDE) (TEDE) 4000 <25000 ED and RPC/RM and DASU ALARA REVIEW AND APPLY EMERGENCY EXPOSURE CONSIDERATIONS ALL OF ABOVE AND
>25000 _ED and RPC/RM and DASU BRIEFING ON RISKS EP-AD-000-1 25, Revision 7, Page 6 of 10
TAB 7 EP-PS-1 06-7 EMERGENCY EXPOSURE EXTENSIONS (continued)
CHECK 0
- 5. Ifthe Emergency Dose Extension is for greater that 4 Rem (TEDE), have the volunteer sign the EMERGENCY EXPOSURE REQUEST Form acknowledging that they are a volunteer and are fully aware of the radiological risks of acute and delayed effects.
- 6. Upon completion of the activity requiring the Emergency Exposure perform the following:
"El Collect, process, and evaluate personnel dosimetry devices when technically appropriate.
"O Investigate the circumstances of all emergency exposures and confirm the dose received.
"El Notify the NRC of emergency exposure as follows:
Immediate notification of the NRC is required for:
Notification of the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is required for:
"El Assess the health consequences of all emergency exposures. Consult with a physician to determine the need for and extent of physical and biochemical examinations.
"El Whole body greater than 25 Rem (TEDE) should result in an examination of the exposed person by a physician.
"El If internal exposure is suspected, quantitative measurements should be made immediately. Bioassays are required based on the following:
"*Nasal smear or facial contamination greater than 1,000 cpm above background.
"*Greater than 4 DAC-HRS in a day or less, or 20 DAC-HRS in a week or less.
EP-AD-000-125, Revision 7, Page 7 of 10
TAB 7 EP-PS-106-7 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES CHECK 0 0 1.0 Evaluate radiological conditions.
01 1.1 Obtain detailed survey data to ascertain:
1.1.1 Beta-Gamma radiation levels 1.1.2 Need for neutron measurements 1.1.3 Contamination levels and protective clothing requirements 1.1.4 Airborne radioactive materials 1.1.5 Variability of conditions over space and time El 1.2 Evaluate personnel status.
1.2.1 Determine available dose under normal administrative dose objectives.
1.2.2 If essential, obtain approval from RADIATION PROTECTION
- COORDINATOR/EMERGENCY DIRECTOR for persons expected to exceed administrative objectives.
1.2.3 Follow criteria in PP&L Emergency Personnel Dose Assessment and Protective Action Recommendation Guide when emergency exposures are deemed appropriate by EMERGENCY DIRECTOR.
1.2.4 Assess individual's history of exposure to airborne materials.
1.2.5 Assess individual's skills in relation to proposed task.
1.2.6 Assess individual's lifetime exposure history.
EP-AD-000-125, Revision 7, Page 8 of 10
TAB 7 EP-PS-106-7 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES (continued)
CHECK 11 El 1.3 Determine proper type and placement of dosimeters.
1.3.1 Evaluate need for additional whole body dosimeters.
NOTE: For emergency exposures above 4 rem, the placement of several dosimeters on an individual is recommended to determine spatial distribution of dose to the individual.
1.3.2 Evaluate need and placement of extremity dosimeters.
1.3.3 Evaluate need for additional dosimetry devices such as high range self-reading dosimeters, electronic dosimeters, and neutron dosimeters.
1.3.4 Evaluate need for time keeping.
El 1.4 Determine proper respirator equipment required to perform task.
NOTE: For tasks expected to last more than several hours, consider need for relief of team members.
El 1.5 Review the following ALARA items:
NOTE: The detail and scope of ALARA reviews are to be commensurate with the magnitude of doses expected, numbers of people involved, and urgency of required task.
1.5.1 Consider the trend of exposures vs. the importance of the task:
- a. Important and critical task with rising exposure rates will require the dispatch of teams as quickly as possible to reduce exposures.
- b. Unimportant or less critical task could be delayed until- exposure rates begin to trend downward.
EP-AD-000-125, Revision 7, Page 9 of 10
TAB 7 EP-PS-106-7 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES (continued)
CHECK 0 1.5.2 When time permits the following should be included in the ALARA review:
- a. Consider the use of remote handling devices or other special tools.
- b. Consider the use of portable shielding.
- c. Consider the need for mock-ups or other practice exercises.
- d. Assess the number of people required to assure all have essential productive roles.
- e. Consider the magnitude of doses received by team members in transit to work location.
EP-AD-000-125, Revision 7, Page 10 of 10
TAB 9 EP-PS-106-9 PREPARATION FOR INDIA TEAM DISPATCH
- 1. Upon identification of the need to assemble and dispatch teams during an emergency condition, the Health Physics Specialist will:
- a. Assemble and evaluate existing and potential radiological conditions that will relate to the team's activities.
- b. Consider how teams will access areas where elevated dose rates exits; in addition, consider a low dose approach where possible.
- c. Consult with appropriate TSC Coordinators on the activities to be performed and the radiological conditions present to arrive at an estimated exposure for team members.
- d. Obtain current YTD dose information for team members and evaluate the need for an exposure extension for emergency exposures.
(1) INDIA team members are permitted to accumulate doses up to 4 rem once entry into the Emergency Plan occurs.
- e. Contact the Radiation Protection Coordinator when exposure extensions for emergency exposure in excess of 4 rem authorizations are required.
- f. Review (or prepare) the Emergency Plan RWP for the activity to be performed.
(1) Description of task.
(2) Protective clothing and respiratory requirements.
(3) Dosimetry requirements (specify Alarm set points for PADs).
(4) Any special precautions.
- g. -Utilize the Emergency Plan RWP (YYYY-8000) to track team members and their exposure.
(1) Use the RWP REMARKS LOG to specify and document:
PAD Settings, Dress Requirements, Dosimetry, Engineering Controls, or other requirements.
- h. Verify respirator qualifications, as necessary.
EP-AD-000-186, Revision 3, Page 1 of I
TAB 8 EP-PS-1 06-8 PERSONNEL ACCOUNTABILITY (As defined in SP-00-309, Personnel Accountability)
ACCOUNTABILITY READER LOCATIONS SITE BUILDING READER LOCATION Service &Administration Building - North S&A Cafeteria S&A Large Conference Room 2 nd Floor Effluents Management Meeting Area Facilities Management Meeting Area Warehouse Facility Large Conference Room 2 nd Floor South Building - Two Story First Floor Main Hallway - East Doorway Main Hallway - West Doorway Main Hallway - Center Second Floor Main Hallway - North Exit Main Hallway - South Exit Main Hallway - West Exit South Building - Three Story First Floor North End Near Elevator South End Near Doorway to Maintenance Center Hallway Second Floor North End Near Elevator South End Near West Stairway Third Floor North End Near Elevator South End Near West Stairway EP-AD-000-445, Revision 8, Page 1 of 3
TAB 8 EP-PS-1 06-8 PERSONNEL ACCOUNTABILITY AREAS AND LEADER ASSIGNMENTS Accountability Area Accountability Area Designator Accountability Area Work Groups Leader ACCOUNTABILITY S&A Building Cafeteria All Personnel located PRIMARY: Industrial AREA A ETN 254-1624 in S&A Building Safety Supervisor All floors except those noted in Assembly Area B ACCOUNTABILITY Effluents Management Effluents Management PRIMARY: Effluents AREA-B Meeting Area Facilities Management Mgmt. Supervisor ETN 254-1644 Chemistry Admin ISI-ISD ACCOUNTABILITY Warehouse Large Procurement PRIMARY: Mgr.-Nuc AREA C Conference Room Procurement ETN 254-3186 ACCOUNTABILITY Electrical Maintenance All Personnel located PRIMARY: Production AREA D I&C Shop in the Two Story Supervisor I&C 1 st Floor Two Story South Building South Building ETN 254-3713 ACCOUNTABILITY Cafeteria All Personnel located PRIMARY: Production AREA E Conference Room on the 1s' Floor of the Supervisor 1 st Floor Three Story Three Story Maintenance South Building South Building ETN 254-1685 ACCOUNTABILITY Conference Room 211 All Personnel located PRIMARY: Radiation AREA F 2 nd Floor of the Three on the 2 nd and 3 rd Floor Protection Manager Story South Building of the Three Story ETN 254-1211 South Building _
ACCOUNTABILITY Technical Support All Personnel PRIMARY: TSC AREA G Center Responding to Fill Administrative Control Structure Emergency Plan Coordinator Elevation 741 Positions in the TSC ETN 254-3045 1 EP-AD-000-445, Revision 8, Page 2 of 3
TAB 8 EP-PS-1 06-8 ACCOUNTABILITY ROSTER ACCOUNTABILITY AREA: DATE: __ I_
ACCOUNTABILITY AREA LEADER:
Name (Last, First) Badge # Name (Last, First) Badge #
U I U I
- 4. U I 4 U I t U I
- 4. U I
- 4. U I 4 U I INSTRUCTIONS:
- 1. The Accountability Area Leader will direct all personnel in the assembly area to complete this roster in the event the Accountability Card Reader system is inoperable.
- 2. On-site Personnel will print their name and SSES badge number in the areas provided on this form.
- 3. After completion, notify Security and follow their direction to forward the rosters.
EP-AD-000-445, Revision 8, Page 3 of 3