ML16253A318
| ML16253A318 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 09/09/2016 |
| From: | Simmons P Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML16253A318 (51) | |
Text
{{#Wiki_filter:Watts Bar Nuclear Plant, Post Office Box 2000 Spring City, Tennessee 37381 September 9, 2016 10 cFR 50.4 10 CFR 50, Appendix E, Section V 10 CFR 50.54(qX5) 10 cFR 72.4 10 cFR 72.44(f) ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 & Unit 2 Facility Operating License No. NPF-90 NRC Docket No. 50-390, 50-391
Subject:
Emergency PIan lmplementing Procedure Revision ln accordance with the requirements of 10 CFR Part 50, Appendix E, Section V, 10 CFR 50.54(qX5), and 10 CFR72.44(f), the enclosures provide the Emergency Plan lmplementing Procedure (EPIP) associated Screening Evaluation Forms of the 10 CFR 50.54(q) analysis. EPIP Revision Title Effective Date 14 0026 Radiological Control Response 8t19t2016 15 0018 Emergency Exposure Guidelines 8119t2016 There are no regulatory commitments in this letter. Please direct all questions concerning this matter to Thomas Detchemendy, Emergency Preparedness Manager, at $23) 365-3232. Respectfully Paul Simmons Site Vice President Watts Bar Nuclear Plant
U.S. Nuclear Regulatory Commission September 9, 2016 Page2
Enclosures:
- 1. Emergency Plan lmplementing Procedure Revision - Screening Evaluation Form, EPIP-14, Revision 0026
- 2. Emergency Plan lmplementing Procedure Revision - Screening Evaluation Form, EPIP-15, Revision 0018 cc:
NRC Regional Administrator - Region ll NRC Senior Resident lnspector - Watts Bar Nuclear Plant NRC Project Manager - Watts Bar Nuclear Plant EDMS bcc (w/o Enclosure): G. Arent T. F. Detchemendy W. H. Lee J. W. Shea NSRB Support
ENCLOSURE 1 WATTS BAR NUGLEAR PLANT, UNIT O EPIP Screening Evaluation Form EPIP-14, Radiological Control Response, Revision 0026
EPDP -17, Attachment 2 Screening Evaluation Form Evaluation No.: WBN -2016-012 Activity Description and
References:
BLOCK 1 Activity is Revision 26 to EPIP-14, which replaced cancelled reference RCI-120 with correct reference title NPG-SPP-OS.2.5 TEDE ALARA Evaluations (CRs 1 189908, 1 '190967) and added Appendix H back into procedure since it was mistakenly removed in last revision (CR 1 I 90967) These revisions provide update of references and reinstate material previously contained in this procedure which was inadvertently removed. This change is therefore editorial and administrative in nature. Activity Scope: I BLOCK 2 A The activity is a change to the radiological emergency plan (includes EPIPs or any other document describing the programmatic methods for maintaining preparedness or responding to an emergency). fr)t, i,' i-:it ,:i' -;i tr The activity is not a change to the radiological emergency plan. 1,-, r ir) lji,), /1 .1)/ ChangeType: I BLOCK3 E The change is editorial or typographical. ,rr irr rr / 1, r, ,', ',,i I The change is not editorial or typographical . {t,,, t,t rr rr', r /,r -J,i Gonformance: I BLOCK 4 n The change conforms to an activity that has prior approval. Record the prior approved activity: I,-jl irl Eio,'.i., ,'l tr The change does not conform to an activity that has prior approval. [()tt ii, t)lt,r;i. !)j Planning Standard lmpact Determination (Gheck All Applicable): BLOCK 5 tl 50.47(bX1) - Assignment of Responsibility (Organization Control) tr 50.47(bX2) - Onsite Emergency Organization tr 50.47(bX3) - Emergency Response Support and Resources tr 50.47(bX4) - Emergency Classification System ' tr 50.47(bX5) - Notification Methods and Procedures
- n 50.47(bXO) - Emergency Communications n 50.47(bX7) - Public Education and lnformation Page 1 of 2
EPDP-17, Attachment 2 Screening Evaluation Form Evaluation No.: WBN-2016-012 tr 50.47(bX8)- Emergency Facility and Equipment tr 50.47(bxg) - Accident Assessment
- tr 50.47(bXl 0) - Protective Response
- tr 50.47(bX11) - Radiological Exposure Control f 50.47(b)(12) - Medical and Public Health Support T 50.47(bX13)- Recovery and Reentry Planning and Post-Accident Operations r 50.47(bX14) - Drills and Exercises n 50.47(bX15) - Emergency Responder Training n 50.47(bX16) - Emergency Plan Maintenance n 72.44(f) - lndependent Spent Fuel Storage lnstallation (lSFSl)
Il itny Plartning Slandarc/s tntpacted, go lo Block 7 lf rtorrc are inrpactecl. g1o to Block 61. t Denotes Risk Significant Planning Standard Gomm itment lmpact Determ ination : tr The activity involves a site specific EP commitment. Record the Commitment or Commitment reference: [Go to Block 7] tr The activity does not involve a site specific EP commitment. [Go to Block 7] Screening Evaluation Results: A The activity can be implemented without performing a 50.5a(q) reduction in effectiveness evaluation. tr The activity cannot be implemented without performing a 50.54(q) reduction in effectiveness evaluation. Approvals: Preparer Name: Preparer Signature: Michael R. White Reviewer Name: RFt{s} Thomas F. Detchemendy J? Page 2 of 2
![/atts Bar Nuclear Plant Unit 0 Emergency Plan lmplementing Procedure EPIP.14 Radiological Gontrol Response Revision 0026 Quality Related Level of Use: Reference Use Effective Date: 08-19-201 6 Responsible Org anization: REP, Radiological Emer. Prep.
Prepared By: Michael R White Approved By: Thomas F. Detchemendy
WBN Radiological Control Response EPIP-14 Unit 0 Rev. 0026 Paqe 2 of 28 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of Revision/Ghange Rev 19 08/1 3t2004 2, 5, 25 Revised response time and minimum staffing in accordance with NRC SER Accession Number ML041810056. Rev 20 1 1/30/06 2, 5, 18, 25 Plan effectiveness determinations on these changes indicate the following revisions do not reduce the level of effectiveness of the procedure or REP. Annual Review. Revised Appendix G to clarify Radiation Protection staffing requirements consistent with the statement in Section 9.2.1 of NP-REP for the deployment of additional sampling teams in accordance with PER 107664. Added Developmental References 10 and 11. Added Quality Related designation to cover page & Quality Related subsection to Records section (PER 1203). Rev 21 10112124A7 2-27 PIan effectiveness determinations on these changes indicate the following revisions do not reduce the level of effectiveness of the procedure or REP. Changed "Rad Con" to Radiation Protection Group - (RP) Rev 22 06/23 12010 All This procedure has been converted from Word 95 to new template format using Rev 21 . Section 3.7.F- Removed Chemistry Count Room Supervisor as this position is no longer active. (PER 226531) Appendix B - revised alternate OSC location to elevation 729' Outage Control Center. Appendix E- updated the Kl instructions. (PER 22412e)
WBN Radiological Gontro! Response EPIP.I4 Unit 0 Rev. 0026 Paqe 3 of 28 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of Revision/Change Rev 23 09t23t13 17 Section 4.1 , added applicable appendices to QA records section. PER724038 Rev 24 01123114 21 Revised Appendix C to include Unit 2 Radiation Monitor information from WBNTSR115 Rev 007 (PER 728A1 9-003). Rev 25 09121 115 22 Revised Appendix C to include Unit-2 Radiation Monitors for upper and lower containmenl2-RE-90-112 and 2-RE-90-1 06 (CR 973512). Rev 26 08/1 9/1 6 6,28 Replaced cancelled reference RCI-120 with correct reference title NPG-SPP-OS.2.5 TEDE ALARA Evaluations (CRs 1 189908, 1 190967) Added Appendix H back into procedure since it 28 was mistakenly removed in last revision (CR 1 1 e0e67)
WBN Radiological Control Response EPIP-14 Unit 0 Rev. 0026 Paqe 4 of 28 Iable of Contents {.0 PURPOSE ....................5
2.0 REFERENCES
........ ..................... 5 3.0 lNSTRUCTIONS....... ....................7 4,0 RECORDS ..................18 Appendix A: RP Shift Supervisor Ghecklist.............. ................... {9 Appendix B: Alternate RP LABTOSC Location........... ..................20 Appendix C; Radiological Conditions Tracking. ........,.21 Appendix D: Occupational Dose from lnhalation of lodine-l3l .......... .......23 Appendix E: Potassium lodide (Kl) Administration Instructions........... ....24 Appendix F: Potassium lodide (Kl) lssue Report ........26 Appendix G: RP Emergency Staffing Functions/Times..... ..........27 Appendix H: Emergency Respirator lssue Guidelines ................28
WBN Radiological Gontrol Response EPIP-14 Unit 0 Rev. 0026 Paoe 5 of 28 1.0 PURPOSK This Procedure describes the actions and responsibilities of the Watts Bar Radiation Protection Group (RP) Section in the event of a radiological emergency. 2,0 REFERENCES 2.1 lnterfacing Documents o CECC-EPIP-9, "Emergency Radiological Monitoring Procedures" o EPIP-6, "Activation and Operation of the Technical Support Center (TSC)' o EPIP-7,'hctivation and Operation of the Operations Support Center (OSC)' o EPIP-8, " PersonnelAccountability and Evacuation" o EPIP-10, "Medical Emergency Response" o EPIP-11 "Security and Access Control"
. EPIP-12, "Emergency Equipment and Supplies" o EPIP-13, " lnitial Dose Assessment for Radiological Emergencies "
o EPIP-15, "Emergency Exposure Guidelines" r EPIP-16, "Termination of the Emergency and Recovery " o NRC lnformation Notice 90-08, Kr-85 Hazards from Decayed Fuel
WBN Radiological Control Response EPIP.14 Unit 0 Rev. 0026 Paqe 6 of 28 2.2 Developmental Documents
. CFR 50.72lmmediate Notification Requirements for Operating Nuclear Power Reactors
. NUREG 0654, FEMA-REP-1, Rev. 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants o RCI-101, Radiation Contamination, and Airborne Surveys o NPG-SPP-05.2.5 TEDE ALARA Evaluations r RCI-130, Personnel Monitor Alarm Response and Personnel Decontamination o ANSI-NI8.7-1976 o 10-CFR 20 Standards for Protection Against Radiation o EPA 400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear lncidents o TVA letter to NRC dated May 1 3,z}O/,,Wafts Bar Nuclear Plant WBN)
Unit 1 - Radiological Emergency Plan (REP) Proposed change - Response to NRC Request for lnformation CIAC No. MB 9130) (T04 040513 808)
. NRC Ietter to TVA dated June 24,2Ao4. Safety Evaluation of the Tennessee Valley Authority Proposed Radiological Emergency Plan Changes for the Watts Bar Nuclear Plant, Unit I (TAC No. MB9130)
WBN Radiological Control Response EPIP.14 Unit 0 Rev. 0026 Pase 7 of 28 3.0 INSTRUCTIONS 3.1 General lnstructions A. The response to radiological emergencies by Radiation Protection Group (RP) personnelwill depend upon the type and magnitude of the existing emergency condition. This can range from a minimal response requiring one or two people to a total manpower mobilization. ln addition, it should be noted radiological problems may not be associated with a given emergency [as defined in the Radiological Emergency Plan (REP)I. Natural phenomena, security threats, or other events not involving radiological problems could be the cause for the emergency status. B. lF an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY is classified, RP is required to assemble a specific number of personnel as described below.
- 1. During normal and off shifts, an ALERT will be announced over the public address system and the emergency pagers will be activated. (ln the event of a SITE AREA EMERGENCY or GENERAL EMERGENCY, the offsite sirens will be activated by the state.)
- 2. The RP Lab will be contacted by the SM/SED, or designee. The Radiation Protection Shift Supervisor (RPSS) willdetermine the number of RP personnel currently onsite and will ensure at least a total of seven (7) additional are available onsite within approximately 90 minutes.
WBN Radiological Control Response EPIP.14 Unit 0 Rev. 0026 Paoe 8 of 28 3.2 Precautions and Limitations During a radiological emergency, Radiation Protection procedures will normally be utilized to cover most situations. Since the magnitude of the problem(s) may be more severe, it is imperative that all requirements for entry into affected plant areas be met. This section summarizes items that will need to be addressed prior to entry into the affected areas and during recovery operations. A. Plant accidents involving core damage may produce excessive dose rates and airborne activity concentrations within plant areas. Radiological precautions must be followed under these conditions until available data indicates othenrtrise. B. These precautions could include the following:
- 1. The use of respiratory equipment.
- 2. lssuance of Kl.
- 3. Multiple layers of protective clothing.
- 4. The use of electronic dosimeters, multiple dosimetry and extremi$
dosimetry as appropriate.
- 5. The use of RWP (911) for drills and (3911) for actual emergencies should be utilized to cover the entry team(s).
- 6. Personnelwill be instructed to monitor their dosimetry frequently to prevent overexposure.
C. If core damage is suspected or if for any other reason elevated airborne activity concentrations are present, then appropriate respiratory protection will be required. lnitialentry will probably require the use of respiratory equipment, since iodine's may be present in significant quantities. GAUTION lF spent fuel damage is involved, be aware of the potential for significant skin doses from KrS. After spent fuel has decayed greater than {90 days, Kr-85 is the predominant gaseous nuclide. Consequently, the dose to the skin could be approximately 150 times the whole body dose.
WBN Radiological Control Response EPIP-14 Unit 0 Rev.0026 Paoe 9 of 28 ?.2 Precautions and Limitations (continued) D. The respiratory guidelines in Appendix H will be considered during emergency incidents. E. Special precautions must be taken when obtaining samples. Smears may have significant dose rates (in the REM/hr range). High airbome activity could result in significant activity concentrations being collected onto the filter media. FOLLOW standard RP procedures, should samples be considered radiological hazards. F. ENSURE allelectronic dosimeters are properly processed for each worker. irAKE arrangements to have primary dosimetry read as soon as possible. lF possible, RESTRICT repetitive entries of workers. SUBSTITUTE other qualified personnel for team members, on reentry's, to distribute exposures. Employee's remaining allowable dose shall be verified by RP prior to entry into plant areas. G. lF plant conditions are such that radiological conditions are changing rapidly, it may not be possible to use previous data in order to determine protective requirements. This factor must be considered prior to allowing survey teams into affected plant areas. H. The "Buddy System" shall be utilized for initialentries into any area where radiological conditions are not known or any area where radiological conditions could be changing due to plant conditions. At least one penson of the buddy system must be qualified in Radiation Protection procedures. Monitoring teams should maintain communication capabilities with the OSC or RP Lab.
- l. Habitability surveys of OSC, TSC, and assembly areas shall be performed as neGessary.
J. Advanced Radiation Worker (ARW) trained REP responders will respond (upon request) to the Radiation Protection Shift Supervisor during a radiological emergency and provide support and surveillance as needed during the initial phase.
WBN Radiological Control Response EPIP.14 Unit 0 Rev. 0026 Paqe 10 of 28 3.3 Response Glassification Guidelines 3.3.{ NOTIFICATION OF UNUSUAL EVENT A. No offsite radiological problems are postulated during a NOTIFICATION OF UNUSUAL EVENT. B. This emergency classification requires a notification to the state of Tennessee Emergency Management Agency (TEMA).This classification has minor on no impact on RP.
- c. RP willfollow standard practices and procedures during response work.
3.3.2 ALERT A. A limited radiological release is possible during an ALERT situation. Onsite emergency facilities will be activated and ofhite agencies contacted. B. lF the assembly alarm is activated, RP personnel shall secure work in a safe manner and report to the 713' RP Lab for assembly and accountability. C. RP Technicians will be dispatched to survey assembly and accountabili$ areas as necessary. D. lt should be noted that an ALERT classification may require the evacuation of a certain plant area and/or building. RP shallensure these areas are properly posted and arrangements made with Nuclear Site Security to restrict all unauthorized access to the affected area(s). E. RP personnelwill assist in the development of all recovery plans as necessary. Recommendations will be made to keep exposures As Low As Reasonably Achievable (ALARA) and to approve recovery activities. F. An offsite survey team may be dispatched from SQN, if coverage is necessary. Site RPSS will contact SQN RP Lab as soon as possible for assistance (Refer to CECC EPIP-9). G. Veriff that Security has distributed emergency dosimetry packages to all offsite responders (EMS, Fire, or LLEA) and to any TVA Security personnel in the OCA and Protected Area whose duties do not allow dosimetry issue at the RCA. Dosimetry packs are maintained at the site access portal.
WBN Radiological Control Response EPIP.l4 Unit 0 ReY. 0026 Paoe {1 of 28 3.3.3 SITE AREA EMERGENCY A. During a SITE AREA EMERGENCY, there may be releases to the environment requiring RP response. B. A SITE AREA EMERGENCY may require the evacuation of a plant building or buildings. C. Personnelwill be notified to assemble for accountability. RP shal! secure work in a safe manner and proceed to the 713' RP Lab for assembly and accountability. D. Accountability will be made in accordance with EPIP-8. Information shall be gathered describing the emergency situation; RP representatives shall be sent to the assembly areas to determine if any workers were in the affected plant areas at the time of the event. These people shall be separated from other plant workers and perconnel contamination surveys initiated for affected personnel. E. As reports become available regarding the details of the emergency, RP personnelshall prepare all necessary equipment needed and ready a survey team(s) for entry into the affected area(s). F. Upon notification from the Technical Support Center OSC), survey team(s) may be dispatched from the OSC to various areas of the plant. lt should be noted that depending on the type of accident, initial survey(s) may not be performed until hours or days after an event. ln this oase, procedures may be developed describing the reentry steps to be followed. G. A site boundary survey may be required. The details of the survey shall be coordinated with the TSC. The environmental monitoring van (REP van) should be utilized while performing these surveys. H. An additionalenvironmental monitoring van may be dispatched from SQN, if coverage is necessary. Site RPSS will contact the SQN RP Lab as soon as possible for assistance. (REFER TO CECC EPIP-9.)
- l. Precautions may be required to prevent personnel overexposures. These exposures could result directly from radiation emitted from the plume and/or due to submersion in the plume. IREFER TO Section 3.6, lssuance of Potassium lodide (Kl)I
WBN Radiological Control Response EPIP.14 Unit 0 Rev. 0026 Paoe 12 of 28 3.3.3 SITE AREA EUERGENGY (continued) J. RECORD all survey results. Allfindings shall be reported to the TSC or Central Emergency Contro! Center (CECC) (if activated). lf results indicate offsite contamination, the survey areas may need to be extended. OBTAIN further instructions and PERFORU requ i red su rveillan ce(s). K. Additional manpower support and equipment may be obtained from other TVA nuclear facilities. L. Veriff that Security has distributed emergency dosimetry packages to all offsite responders (EMS, Fire, or LLEA) and to any WA Security personnel in the Owner controlled area (OCA) and Protected Area whose duties do not allow dosimetry issue at the RCA. 3.3.4 GENERAL EII,IERGENCY A. During a GENERAL EMERGENCY, there may be radiation releases to the environment requiring RP response. These releases may require the implementation of evacuation procedures. B. The actions described under SITE AREA EMERGENCY will be applicable to a GENERAL EMERGENCY condition as well. C. During a GENERAL EMERGENCY, conditions in the RP Lab may be such that evacuation is warranted. lf this situation develops, REFER TO Appendix B. D. All subsequent offsite activities will be coordinated with offsite support agency survey teams to make the best use of available manpower. REPORT all survey results to the TSC or CECC (if activated) so recommendations to the proper agencies can be made to initiate any required protective actions. E. Veriff that Security has distributed emergency dosimetry packages to all offtite responders (EMS, Fire, or LLEA) and to any TVA Security personnel in the OCA and Protected Area whose duties do not allow dosimetry issue at the RCA.
WBN Radiological Control Response EPIP.14 Unit 0 Rev. 0026 Paoe 13 of 28 3.4 Duties of RP Perconnel Assigned to the TSC A. The TSC is activated during an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY, and may be activated during a NOTIFICATION OF UNUSUAL EVENT. B. The RP Manager is the designated RP TSC Manager. Approved alternates rotate this Emergency Response Organization (ERO) duty. Additional, suitably trained and qualified personnelare listed on the ERO call list. The duty RPSS may serve as the TSC representative during the initial stages of an emergency until relieved by a duly qualified individual C. The responsibilities and duties of the TSC RP Manager are summarized in EPIP.6.
WBN Radiological Control Response EPIP.14 Unit 0 Rev. 0026 Paqe 14 of 28 3.5 Duties of RP Personnel Assigned to the RP Lab. A. The RP Shifr Supervisor (RPSS) or qualified designee is responsible for managing the activities of the 713' Lab. Appendix A of this procedure can be used as a guide by the RPSS during REP activities. B. Survey teams are dispatched from the OSC staging areas. The RPSS is responsible for ensuring survey teams are properly equipped, protected and are aware of any special precautions, plant conditions, or requirements. C. The RPSS willensure all entries are properly coordinated and approved by the OSC manager. D. The RPSS is responsible for ensuring adequate numbers of RP personnel are available to support emergency activities. When an AIert or higher emergency has been declared, ensure seven (7) additional RP personnel have responded to the OSC. For a summary of minimal assignments during emergency see Appendix G of this Procedure. E. The RPSS is responsible for preparing and designating an onsite RP monitoring team. Team members will prepare the REP van(s) in accordance with CECC-EPIP-9. For additional ofbite monitoring, the RPSS may request assistance from SQN. F. The RPSS willdispatch survey teams to assembly areas, the OSC, and TSC to evaluate radiological conditions and monitor radiation levels as conditions change. These survey teams will be responsible for monitoring contamination levels (both on personnel and floor/equipment areas) and implementing corrective actions (e.9., decontamination or zoning) as necessary. G. The RPSS will monitor the 713' Lab for habitability and wil! coordinate evacuation activities to the alternate lab location (Appendix B) if required. H. The RPSS may use PEDS to track radiologicalconditions in the plant (Appendix C)
WBN Radiological Control Response EPIP.14 Unit 0 Rev.0026 Paqe 15 of 28 3.6 lssuance of Potassium lodide (Kl) A. lF the TSC RP Manager has reason to believe a person's projected cumulative dose to the thyroid from inhalation of radioactive iodine could exceed 10 Rem, the exposed person should be administered potassium iodide (Kl) as a prophylactic. Anyone authorized by the TSC RP manager to administer Kl shall be familiar with the Food and Drug Administration's approved Kl package insert and ensure each recipient is similarly informed. Kl recipients will acknowledge their understanding of the consequences of taking or refusing KI by signing Appendix F, Potassium lodide (Kl) Issue Report. The initial dose of KI should not be delayed and those who begin therapy should continue the 1O-day course of Kl unless their thyroid dose is determined not to have exceeded 10 rem. An adequate supply of Kl tablets are stored in the OSC staging area cabinets. FOLLOW dosage schedules as outlined on the package insert (Appendix E). B. Projected cumulative doses to the thyroid from inhalation of radioactive iodine can be determined using Appendix D, "Occupational Dose from lnhalation of lodine-131."
- c. Kl is stored in the Emergency Supply cabinet (OSC staging area).
Kl has an approved shelf life with the expiration date listed on each tablet package. Expiration date verification and necessary inventories are performed using EPIP-12. D. A copy of the Food and Drug Administration approved package insert shall accompany the issuance of Kl. Dosage schedules and other pertinent information are outlined on the package insert and should be followed closely (Appendix E). E. The issuing agent shall complete Appendix F, Potassium lodide (Kl) lssue Report, when Kl is issued. A copy of this report will be sent to the TSC RP Manager in a timely manner.
WBN Radiological Gontrol Response EPIP.14 Unit 0 Rev.0026 Pase 16 of 28 3.7 Radioiodine Sampling CAUTIONS {) RCI-101 should be referenced for hazards associated with Silver Zeolite cartridge use. 2l Sample cartridges may exhibit high dose rates after sampling during accident conditions. Exercise good ALARA practices when handling, storing, and disposing of these cartridges. A. During accident conditions, noble gas concentrations may be present in significant quantities. The collection of these noble gases on charcoal cartridges during iodine sampling will interfere with subsequent iodine analysis. Silver zeolite (ASZ) cartridges are provided for use during periods of high noble gas concentrations. B. Radioiodine samples should be collected at 30 liters per minute (LPM) for daily or weekly samples. Grab samples may be collected at 30 or 60 LPM based upon the type of air sampler used and the conditions in the sample location.
- c. Radioiodine sample volumes of less than 900 liters may be performed if it is known or suspected that dose rates on the AgZ cartridges willexceed 10 mrem/hr. During these instances, sample duration's may be reduced to 5 minutes. Sample duration's Iess than 5 minutes may be used for ALARA purposes but shall be pre-approved by the RPSS.
D. Upon completion of sampling activities, the air sample should be returned to the RP Lab for analysis as soon as possible. A radiation survey of the sample head shall be performed to determine the contact dose rate. The results of this survey shall determine any special handling or packaging requirements during analysis.
WBN Radiological Control Response EPIP-14 Unit 0 Rev.0026 Paqe 17 of 28 3.7 Radioiodine Sampling (continued) E. lF the iodine sample activity is > 1 mrem/hr., a contact dose rate should be taken by using a Ludlum 14-C or equivalent GM survey instrument with the beta window CLOSED. The radioiodine air activity can be approximated by using the following formula: [Average of the Front and Back Contact pCilml= Dose Rate (mrem/hr) X 5.'l E:-31 Volume (liters) F. Radioiodine cartridges with contact gamma dose rates greater than or equal to
't00 mrem/hr shall not be delivered to the Chemistry Lab without prior approval of the RPSS.
G. RP personnel shall inform Chemistry personnel of the contact dose rates of the samples. RP personnel should provide radiological coverage during handling, analysis and disposal if samples read greater than 100 mrem/hr. The RPSS will approve disposal methods and location for all samples reading greater than 100 mrem/hr. H. Gamma analysis results shall be reported to the RPSS as soon as possible.
- l. Accident related radioiodine samples should be documented and analyzed in accordance with RCI-101 or CECC-EPIP-9 as appropriate.
3.8 Personnel Decontamination and Facilities A. RCI-130 describes the procedures to be used for personne! decontamination. B. Contraminated personnel are normally decontaminated at the 7'13' elevation decon facility. This facility is equipped with a wash sink, shower, and all necessary supplies. These supplies normally include various decontamination agents and soaps, towels, clean clothing, and other miscellaneous supplies. C. Grossly contaminated personnelwith injuries are normally treated at the 713' elevation prior to transfer to an offsite medical facility unless the injury requires immediate transportation. (REFER TO EPIP-1 0). D. Contaminated personnel requiring offsite medicalattention are transported to Rhea County Medical Center [Dayton] or Starr Regional Medical Center ffihensl). The hospitals have personnelthat have been trained in the handling and care of contaminated patients. Watts Bar maintains a supply cabinet at each hospital's Emergency Room which contains posting materials and various other supplies. Refer to EPIP-10 for guidance on transporting contaminated and radiation injuries to REACTS in Oak Ridge or Erlanger Medical Center in Chattanooga.
WBN Radiological Control Response EPIP.14 Unit 0 Rev. 0026 Paqe {8 of 28 4.0 RECORDS 4.1 AA Records The following records are QA records when completed during actual radiological emergencies. Appendix F: Potassium lodide (Kl) lssue Report 4.2 Non- QA Records t1] Emergency Records The records generated due to declaration of an emergency classification are considered Lifetime Retention records. These records shall be forwarded to the WBN EP Manager. The records necessary to demonstrate performance are then submitted to the Corporate EP Manager for storage. 121 Drilland Exercise Records The records deemed necessary to demonstrate performance of key actions during drills are considered Non-M records. These records shall be foruvarded to the WBN EP Manager. The WBN EP Manager shall retain records necessary to demonstrate six-year plan requirements for six years. The VIBN EP Manager shall retain other records in this category for three years (eight years starting the after the next HAB Drill).
WBN Radiological Control Response EPIP-14 Unit 0 ReY.0026 Paqe 19 of 28 Appendix A (Page { of {} RP Sh:ft Superuisor Checklist Upon activation of the OSC and TSC, the RPSS can use the following checklist as a guide to complete actions. tl] INITIATE immediate requested actions (dose assessments) by the Main Control Room (MCR). tr 121 lF activation is ALERT or higher, ensure seven (7) additional ANSI Qualified RP personnel have responded to the emergency page. Follow FFD directions for call in of unscheduled work per EPIP-7. tl t3] CONTACT SQN to dispatch Offsite survey team per CECC-EPIP-9 if needed. tr t4l DISPATCH RP personnelto the REP Van to initiate radiological monitoring per CECC-EPIP-9. tr t5l INITIATE CECC-EPIP-9, as requested by the SM, TSC or cEcc. tr t6l lF the following 2 conditions are met, go to the TSC and perform TSC RP Manage/s functions until relieved. (Ref. EPIP-6) RPSS functions can be performed from the TSC. tr TSC RP Manager is not in the TSC. El Vl lF Assembly Alarm has been activated, dispatch RP personnel to assembly areas (as needed) per EPIP-8 to survey assembly areas. E] t8] DISPATCH RP personnelfor search and rescue teams into the plant (as needed) per EPIP-8. tr tgl ASSIGN RP personnelto survey for radiological habitability in the MCR, TSC and OSC throughout the REP activation. tr 110l DIRECT radiologicalfield monitoring teams until relieved by TSC RP Manager or the CECC. tr tl1] lF evacuation of the RP Lab is required, REFER TO Appendix B of this procedure for alternate locations. EI
WBN Radiological Control Response EPIP.I4 Unit 0 Rev. 0026 Pase 20 of 28 Appendix B (Page .l of 1} Alternate RP LAB/OSC Location The location of the Alternate RP Lab/OSC will depend on in-plant radiological conditions. The TSC RP Manager, after consultation with the SED, will make the decision on location transfer. Possible locations that will be considered are:
. Alternate OSC elevation 729'Outage Control Center . Relay Room 755' level next to the Control Room and the TSC . Staging Area, PSO building (by the old fossil plant).
Essential equipment will be moved to the alternate RP Lab if conditions warrant the evacuation of the 713' Lab. Reference EPIP-I2 Appendix E, for suggested equipment.
WBN Radiological Control Response EPIP-14 Unit 0 Rev. 0026 Paoe 21 of 28 Appendix C (Page 1 ot 2l Radiological Conditions Tracking RP personnelshould PEDS to assist in tracking in-plant radiologicalconditions. Key radiation monitoring information can be found in the following TSC Mimics or system group: o 4RMl ln-plant radiation monitors o 4RM2 In-plant radiation monitors
. EFFI Radiation monitors associated with the plant's release paths
. Group - System Group Menu - SYS-9O-RAD MON Should PEDS not be available, then the worksheets of this appendix can be utilized to track in-plant radiological conditions.
SELECTED KEY IN.PLANT RADIATION MONITORS UPDATED READINGS, CPM, mR/Hr., or R/Hr. DESCRIPTION IDENTIFIER BACKGROUND Date Date Date Date o-M-12 READING Time Time Time Time Spent Fuel Pit Area (El. 757) 1&2-RE-90-1 Upper Containment RB (El .757) 1&2-RE-90-2 Spent Fuel Pool Skimmer Filter Area 0-RE-90-5 Monitor (El. 737) CCW Heat Exchangers (El. 737) 1&2-RE-90 Hot Sample Room (EI. 713) 1&2-RE-90-7 AFW Pump Area (EI. 713) 1&2-RE-90-g Waste Condensate Tanks (EI. 692) 0-RE-90-g CVCS Board Area (El. 692) 1&2-RE-90-1 0 CS & RHR Pump Area (El. 676) 0-RE-90-1 1 RB Low Compt lnst Rm (El. 736) 1&2-RE-90-61
WBN Radiological Control Response EPIP.14 Unit 0 Rev. 0026 Paoe 22 of 28 Appendix C (Page 2 ot 2l Radiological Conditions Tracking SELECTED KEY IN.PLANT RADIATION MONITORS UPDATED READINGS, CPM mR/Hr., or R/Hr. DESCRIPTION IDENTIFIER BACKGROUND Date Date Date Date READING Time Time Time Time lnside RB-Upper Containment 1-RE-94412 (Located in AB, E\.737) lnside RB-Lower Containment 1-RE-90-106 (Located in AB, E .737) Condensate Demin (TB, EI. 685) 0-RE-90-230 0-RE-90-231 lnside RB-Upper Containment 2-RE-90-112 (Located in AB, E,1.737) Inside RB-Lower Containment 2-RE-90-1 06 (Located in AB, E\.737') (Space for additional monitors)
WBN Radiological Control Response EPIP.l4 Unit 0 Rev.0026 Paoe 23 of 28 Appendix D (Page I of {} Occupational Dose from lnhalation of lodine-l 31 Occupational Tltyroid Dose from lnhalation of 1.O0E-03 1.00E-o4 .,Q t, (, ira r,, (u
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WBN Radiological Control Response EPIP-14 Unit 0 Rev. 0026 Pase 24 of 28 Appendix E (Page I ot 2l Potassium lodide (Kl) Administration Instructions Consumer Package lntert Tablor cllr bo cnrhcd md rnlred in meny tiqradr.To teko lhs t&{ar wARilll{0 foi l[dd rolulbo, um dodng dlrtctiont undor It*try r Patmlum Ps@e who aro dleig[c to aodna, lraw dcrmrtitl hcrydihrmic or loddc Llquld lllrurc. hypooomplrn*ntrmh vrculltit, or hayr nodlhr th/roid d*rara loIIATTI Talrr Kl svcry dry (cvcry 2{ hotrrr} at diro$scl try pubil$c official*. Ss wilh hrort dltea* ehould not tr}t Xl. l(rp out of no rrrch of nol ta*a morc tha,n I doee in 2{ houra. tiloro $A fio( help yuo, Tco chil*en, ln car. of rn rlrqic rcection (dfiial$y bcr$*ig. rpeehinS {Poiarrlum }odldc Ttblrir UiP. lS0 m5} rnuch modkino mry irwcaro thc chancce of ride cfiosts. or rwmling rfioerlng; rhonncr ol brs4tr or rucllhg ol tho mqrth (Abbnvlrhd Kl) or [trnd], cell 0t I or gct mcdcat carc dght Ewry. ]n car6 d owrdo*, get rmdlc*l hclp or ce[ e Fohon Coril:ol Gcnter dghf euay" Teltc pot trlurn lodldr (t$I only x{rrn publla offiatrlr trhlng r ?oteulurt todldG Lhuk ltilrturu:
!.ll pu. ln a nuclorr ndleltron tlrttrs;nay. rMl*ac*vr t" Put onr l3O mg l(l tattot rnto a rmiil hm,l find grtrld it into. HOTI' FO?A3$IUM lotxDE WORKE lodlnr could bc rrlrlrd lnro th rlr. Kl Froloctl on$ tho ![rE por(r u.e sl. b.cI of I meul hrcpowr agntnrt tftp insHs of llryroad gland trom upttlr ol ndlorr"Uvn lodlnr. thr boryl. The podrr $oultl not hlvr:ny lnrgr pbcea Cc*atn irmr ol io'dlnc hctp your thyrold drrd work rfiht tfiod pofla Thrfllaru, xl rhould br urcd rlsle wilh othrr rtfiff[trnily 2. Add { toerpomfr.ill of wrlar to ttro ou$lad Kl pa*tler tn the Uurd {it *r lodim trey noed &,om ioodr likc iodlrcd rol or fsh. Th6'th}rioa{t rn rrunrr tlt*t wllt be rucommtndcd to you by pubttc arrd mix ur*t thr Kl porrderir dirmlrd ln the w.t*. ualr '*br*" or lrcld only a certcLr lmqrnt of iodlno.
olllclrlr. ll you ar told to tllrl lhb.nrdlGlil*,lrhr lt , tlma 3. T*lte thr Kl wttormututr rolulbnmrdr tr fiop 2 arrd rnk itwith lil E nuclaar radiatbn cmaryincf, radhectlvi lodlne msy be rsleatod everyt !{ trogrr. Do nol trb ll moil oft.n, tarr Kl wltl not ,l isllapodrftrh o{ lotr llt wt$tr or cilroobta mil}. ofirfigo iuioe, flct roda. hrlpyou. Too much Kl mry lnar,mm lhr chrncat ol rido il lfr! $f. Thir rnal**rt rnay br hra$rod or *nnfinrred, n m*y ents raspbeny iyrrup, or infont formr.ila. thi ttrlrdd gtdtd *nd daorage il. The dnrrrroG urouH pfi$rtty not ahow rfrcctl. IIo not l*kt lhll mcdldn* lf yolt lux]r fou rr. {. Thr Xl [qu*d mixlun urSl *ccp lor up to ? dryr tn tho rtftigcrator. tt ir ittslf lor !ffir*. Ch*tr*re* rre mort lilrrfy to haro thyroid dama6. raconrrncod.d thlt thc Kl liquid mixturo bc prcpercd waohly. Thrw iry ururod porlio*r. If ),ou tehe l(l. it udE bbc* ff na.hro6 the cfianmc thrfi mdlosctiru rodinc wtll cnteryorlr thyrddgland. DESGRIPTTOT{ Yho rrnounf of Xl (tS{t trq rsHcl} ln tho drlnlr wficn rf,rcd rri drlcfibod E*ch white. fourd, cro*s.*aoffid-tho nema IO$AT rremgcdoo otla rbo*r ir t$.ef ,n$ pc{ eaapoonfi^il. Thr nurnbcr of tcrcpoonlutr ol thc ur,lro $HouLD t{oT TAKE poT*S8ruil tonmE silE*lsbhl scnt*lns 13CI m0 of potsaeium ioddo. drink to givr yuur cfi*H depondr on yo$r cfiltd'c rgs *r dotcdbed ln thr fofioxFrg tab$e; Peogle *hould avdd Kl i, tlry rrc satsr!0ir b trdinl, hrue drmredtir tllglClTl(}tilS hrrprtilormir or trypocorplerru*rHntl{: v*t*r*llth, or havc noduhr Ghald't lnG &*u* yrrur chlld thll unounl ln irupoonfulr thyrolddSmrcn wtth hrert diaoe*e. bcc*uto Srse aordilhm may ffirT {Pot*r*ium lodtdr ttblotB, u!P} }l r thyrotd uooltltg irsatne* lhe chane: of gd+ ctla*t* tr iodlne. rncdlal*o thet lr u$rd lr r nuc$l* rrdleson .orarti.nca only, Ovsr fZ lo l&y$s* d ies*pooCIfuB will gifc yrou a 6&rrg dote nilro utrfih hrr tlmn HOW ATiID WHEI{ TO TAT(E POTRSSruU loDIDT srftEcTtotas Fon u$8, ISO ooundr l(l rhould hc tskon fis *$fifi m po**lhd* *fi*r p*bi$r officirlr tr$l yur. tl tlao wrty cr dirociid hf FuHts o$Fcirl* l{ e rr,rchar redrtion cx/er 3 to l? ya*r* { ionrpoonfuk xrt g[va you e O6rng chrl Irou are told lo nlpeet $$ doas. you *hn*rld in*e th* $sffild dota ?4 ffirsrg*ncy heppsn*. old iourr eflor tho lir*ldom. Oo no( tsk* it i{sc*r" &i+r* Ktw{[ nof heb yqu beceuri lhe 0ryrfftt cnn'h*ld* onty Aerturn *rnoufttr of iodinr. Ovor I rmrrth ttr l te*eprcnlukr*dl give you a 32.tmg doce Tekirq rnoro than 1 dore pcr d*y w;[ tnmass tht r}rancer of ridr S yerr* oltl g.tfactr. Thc pr$fic offrci*ts riilt tetlyou ho* rmny dayr Io trhc Kl. Adult* surr tl yr.rl 1 tabEt ($ho}* or cruchod) Yotr ghould lnke Kl until tho chmor* ol melor expocrrre lo radioectiw
$rry day (t3O r) Birth to 1 rnonft t le*pmnlul wdl gtve you a t6.25rrU doeo rodim hy breething or rwalhn{ng *topr.
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,ll{l lrfrowllgtr tvsy day tt36mgl Natnl Thir lr CIra snounf !o girrr ym.rcftitd for ono irrss dom in Strort-term use ol Xl rl thc ne@mm.ndod dore rg rds. you rhould r't lamt aarn*r tmrpoonfub (not LrUorpoontuB). You rhqJd givo yur drild onc dota not l,alta thie drug f;or loogu th*n yoo .rr toE, oach dry ii rcoornotcnded by the Srbfic offsirla.
Chlldtu oucr t3 y.rfir ?1 Udrt (rhdr or cruatred) fo lC y..rr who relgh ar { le.arpooffidr nvtry day Prrynrnl or breutfcrdlng w.om.n or brblcr undor t month of rgr; Poaaiffi lrds offecb lndudr: rrrclling of th. rrthrrry glurde, narsor, lorr thrn 1![ ooundr vornlti$g, ditnhea. rlryrroch ocho, fiaver, hredadrg, metrllio larte. {6$mol Telrc aa drarled obovo and call I doctor ai roon m pouih,h. naport errd allor,gia readions. Albrgb rrlcilionr can incbde doclrq lhould be auoided. ll B racrynnrerdgd thst &froid lunction be . thin raah'g strch as hhrqc Chlldron ovor S ttrrru to :,t tabild {rrtc*c or cnlsh$d} chac*sd ln baNer lor,r than 1 monfh od aee tfrat take Kt. Wamsn xilto tl yrrrr or 4 lm*pmrilul* ev*ry dny are ptagnanl or brGadrcdlng rftuld rho be dt6d(sd by a doclu ll nelling ol variour p{f. of tho body urctr lr tha J8firrrtrt repenl dodng h nsce.c.ry. Although lhcra pracaultuflr rtror.ild ba tat*n, fico. llps, toneuG. ttroal har6e orioet
.[BvGr w{thfolnl paln lhe benaliu ol chorl-tsrrn u.e of t( to blodr uFttf,e al radiractivg ildina .houbll brcething, apcahlng or rwallowing Chlldrco oyrr t month 2 taacRosthrtr*wrTd*y by fn thyrom gliind hr cxcmd ttl chenort ol ttdc aftoctt. .whaering or rlrorlngr ol broeth
{,t? i rnal P*lent. ullh thyrold dlre*ro; ll you hanr r noduhr lhymld carrdttlatl Grl mrdical pilcntion llgN awry ll pu heye rroubb brerthhrg, Beblrr rt blrtlt to rpo*h.inq tr rwrfiorring; wtrrorilrg; thormelr ol braatn;or tnr*Umre d I tempoonftd ovary d*y oucfi ag rnulttnodubt gottF. wtth hean dh6a36, yorJ *ruffi nol ints l(. I msrth P*llemr udth o0rf nyrOU condlttonr orl}y likrkl a* dtmfilsd flbov. ttia mouth- tEnSuG or throal. tlB.?S msl bul c-ll e dochr ll you need to lnkc Kl for nnro lhgn d far rley*. lwtlinurdl
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WBN Radiological Gontrol Response EPIP.14 Unit 0 Rev. 0026 Paoe 26 of 28 Appendix F (Page 1 of 1) Potassium lodide (Kl) lssue Report ISSUED TO EMPLOYEE ID KNO\A'N ALLERGY PACKAGE TIME OF DATE OF SIGNATURE NUMBER TO IODINE? INSERT INITIAL KI INITIAL KI ISSUED BY (lf yes, do not issue) PROVIDED DOSE DOSE AUTHORIZED BY: TITLE: Route to Emergency Preparedness Manager.
WBN Radiological Control Response EPIP-14 Unit 0 Rev.0026 Paqe 27 of 28 Appendix G (Page 1 of 1) RP Emergency Staffing Functions/Times Major Task On Shift 90 minutes Minimum Qualifications A. ln-Plant Surveys 1+ 1* 1 ARWA B. Rad iation Protection :" 2** + 2* 2 ARWA 1 Access Control 2 HP Coverage for Repair Corrective Action, Search and Rescue, First Aid and Fire fighting 3 Personnel Monitoring 4 Dosimetry C. Onsite (Out-of-Plant) 1** 1 ARWA D. Offsite Surveys 2*n 2@ RP Tech** E Senior Health Physics 1*** RPSS Expertise (1) See Developmental References 10 and 11 for bases.
- May be provided by Shifi personnel assigned other functions.
s May be provided by task specific trained personnel. i** Driver may be other than a RP Tech if enough RP Techs. are not available.
*** Radiation Protection Shift Supervisor (RPSS) may report to TSC if able to manage the RP Lab from there.
A Advanced Radiation Worker (ARW qubliReO O Additional teams can be dispatched from other facilities (for example, the SQN Monitoring Van.) At least one additionalteam can be deployed within approximately one hour of notification.
WBN Radiological Control Response EPIP.{4 Unit 0 Rev. 0026 Paqe 28 of 28 Appendix H (Page I of 1) Emergency Respirator lssue Guidelines NOTE THESE GUIDELINES ARE RECOMMENDATIONS ONLY, SUBJECT TO THE JUDGEMENT OF RP AND EMERGENCY MANAGEMENT PERSONNEL. THESE GUIDELINES ARE APPLICABLE ONLY TO PROTECTION FROM AIRBORNE MDIOACTIVE MATERIAL AND DO NOT APPLY TO RESPIRATORS/SCBAS ISSUED FOR PROTECTION FROM INDUSTRIAL OR CHEMICAL HAZARDS OR ATMOSPHERES IMMEDIATELY HAZARDOUS TO LIFE OR HEALTH. TASKS TO SAVE A LIFE OR Respirator/SCBA not required to enter airborne radioactivity PREVENT SIGNIFICANT areas provided resulting internal dose plus external dose will not DAnIAGE TO PLANT result in TEDE exceeding NRC dose limits or, if approved by the SED, doses up to the TVA emergency dose Iimits (i.e., up to 25 remr{ 0 rem} (this can include uptakes > I ALI} H,!.gtl PRIoRITY TASKS o Respirator/SCBA not required to enter airborne areas if the (priority { or 2l following are true: NOTE: lF INDIVIDUAL'S TOTAL . lndividual's internal dose plus external dose will not result in INTAKE FORTHE YEARTO TEDE exceeding NRC annual dose limit; and DATE EXCEEDS 2AO DAC-HRS., DOSE . Delays or hindrances caused by issuing or wearing RESULTING FROM ALL respiratons/ScBAS will jeopardize the success or timeliness of INTAKES FOR THE YEAR the task; or TO DATE MUST BE ASSESSED IN . Use of a respirator/SGBA will result in a higher TEDE to the DETERMINING THE TEDE. responding individuals. LOW or MID PRIORITY TASKS Use NPGPP-OS.2.5 for respirator issue guidallce. NOTE Protective requirements may be revised at the discretion of the TSC RP Manager as sample data becomes available.
ENCLOSURE 2 WATTS BAR NUCLEAR PLANT, UNIT O EPIP Screening Evaluation Form EPIP-I5, Emergency Exposure Guidelines, Revision 00{ 8
EPDP -17, Attachment 2 Screening Evaluation Form Evaluation No.: WBN-201 6-01 3 Activity Description and
References:
BLOCK { Activity is EPIP-15 Revislon 18, which: Replaced cancelled reference RCI-120 with new correct reference NPG-SPP-05.2.5 TEDE ALARA Evaluations (CRs 1 190968, 1 189908). This revision updates the name and procedure designator of a referenced procedure to be correct and current. The revision is editorial as it does not add or delete any steps and does not change the intent of the procedure. Activity Scope: I BLOCK 2 E The activity is a change to the radiological emergency plan (includes EPIPs or any other document describing the programmatic methods for maintaining preparedness or responding to an emergency). /',-:il lrr ijl,t' ;, ii tr The activity is not a change to the radiological emergency plan. ',.,,-, t , ,irlr;clr Ljl Ghange Type: A The change is editorial or typographical. /t )o it r Li/or-:i. 7l tr The change is not editorial or typographical. 1t-t t ii,i ljlt-,,r/,' "]i Conformance: I gLger4
..::t :' 'i .,.i1,,
tr The change conforms to an activity that has prior approval. Record the prior approved activity: [tjt, l1 Elo,:1.. 7] tr The change does not conform to an activity that has prior approvsl. f,io 1c 8/ciclr 5! Planning Standard lmpact Determination (Check All Applicable): tr 50.47(b)(1) - Assignment of Responsibility (Organization Control) tr 50.47(bX2) - Onsite Emergency Organization t] 50.47(bX3) - Emergency Response Support and Resources tr 50.47(bX4) - Emergency Classification System n 50.47(bX5) - Notification Methods and Procedures
- tr 50.47(bX6)-EmergencyCommunications n 50.47(bX7)- Public Education and lnformation n 50.47(bXB) - Emergency Facility and Equipment Page 1 of 2
EPDP-1 7, Attachment 2 Screening Evaluation Form Evaluation No.: WBN-2016-01 3 tr 50.47(bxg) - Accident Assessment
- r 50.47(bX1 0) - Protective Response
- tr 50.47(bX11) - Radiological Exposure Control T 50.47(b)(12) - Medical and Public Health Support l 50.47(bX13) - Recovery and Reentry Planning and Post-Accident Operations T 50.47(bX14) - Drills and Exercises f 50.47(bX15) - Emergency Responder Training tr 50.47(bX16) - Emergency Plan Maintenance u 72.44(f) - lndependent Spent Fuel Storage lnstallation (lSFSl) lf arty Planrrutg Slartri.urls mpactecl, go lo Llhtck 7 lf rtorte are irrrltacled. g1o to Block 61.
,t Denotes R sk Significant Planning Standard Gommitment lm pact Determi nation :
n The activity involves a site specific EP commitment. Record the Commitment or Commitment reference: IGo to Blor.:k 7] tr The activity does not involve a site specific EP commitment. [Go to Blctck 7] Screening Evaluation Results: E The activity can be implemented without performing a 50.54(q) reduction in effectiveness evaluation. tr The activity cannot be implemented without performing a 50.54(q) reduction in effec-tiveness eval uation. Approvals: Preparer Name: Preparer Signature: Date: Allen M. Phillips 08/1 6/2016 Reviewer Name: Reviewer Signature: Date: Michael R. White @,t*a 08/1 612016 Page 2 of 2
Watts Bar Nuclear Plant Unit 0 Emergency Plan lmplementing Procedure EPIP.{5 Emergency Exposure Guidelines Revision 0018 Quality Related Level of Use: Reference Use Effective Date: 08-19-2016 Responsible Org anization: REP, Radiological Emer. Prep. Prepared By: Michael R White Approved By: Thomas F. Detchemendy
WBN Emergency Exposure Guidelines EPIP-I 5 Unit 0 Rev. 0018 Paqe 2 of 15 Revision Log Revision Affected or Change Effective Page Number Date Numbers Descri ption of Revis ion/Ghange Rev 12 05106i20a4 2,4,5 Plan effectiveness determinations on these changes indicate the following revisions do not reduce the level of effectiveness of the procedure or REP. Non-intent changes. Corrected reference. Ed itorial corrections. Rev 13 1011212007 2,5, g, 10, PIan effectiveness determinations on these 11,13, 14 changes indicate the following revisions do not reduce the level of effectiveness of the procedure or REP. Non-intent changes. Changed "RadCon" to Radiation Protection Group- (RP) Rev 14 81241201 0 Ail This procedure has been converted from Word 95 to new template format using Rev 13. Changed Rad to Rem throughout the procedure to conform to the guidance found in EPA*400-R-92-001 . This is a corrective action of PER 214744 Rev 15 05t25112 Cover Changed the cover sheet to indicate the sheet procedure is Quality Related. (PER 542890) Rev 16 09/23 113 2,8 Section 4.1 , added applicable appendices to QA records section. PER724038 Rev 17 09121 115 15 Removed the respirator evaluation chart as this evaluation is performed in accordance with RCI-120 TEDE ALARA Evaluation, using a 15o/o inefficiency factor. CR 1077091 Rev 18 08/1 9/1 6 4,14 Replaced cancelled reference RCI-120 with new correct reference NPG-SPP-OS .2.5 TEDE ALARA Evaluations (CRs 1 190968, 1 189908)
WBN Emergency Exposure Guidelines EPIP.{ 5 Unit 0 Rev. 00{ I Paqe 3 of 15 Table of Contents 1.0 PURPOSE .................... 4
2.0 REFERENCES
........ .....................4 3.0 !NSTRUCTlONS....... ....................5 4.O RECORDS ....................8 Appendix A: Watts Bar Emergency Exposure Reference .............9 Appendix B: General lnstructions For Emergency Exposures........... ........10 Appendix C: Emergency Respirator lssue Guidelines ..........,.,...14 Appendix D: Definitions.............. ................... {5
WBN Emergency Exposure Guidelines EPIP.l 5 Unit 0 Rev. 0018 Paqe 4 of 15 1.0 PURPOSE This Procedure provides guidance for planning occupational exposures under emergency conditions consistent with EPA-400-R-92-001, "Manual of Protective Action Guides and Protective Actions for Nuclear lncidents." These limits apply only to emergency exposure authorizations and not to spontaneous reactions by individuals attempting to mitigate an emergency situation.
2.0 REFERENCES
2.1 Performance References
. NPG- SPP-05.1, Radiological Controls o EPIP-10, Medical Emergency Response o NPG-SPP-05.2.5, TEDE ALARA Evaluation 2.2 Developmental References o ICRP Publication 26, "Recommendation of the lnternationalCommission on Radiological Protection" o ICRP Publication 28, "The Principles and General Procedures for Handling Emergency and Accidental Exposures of Workers" o TVA NP Radiological Emergency Plan
. EPA 400-R-92-001, and subsequent revisions, "Manual of Protective Action Guides and Protective Actions for Nuclear lncidents"
. NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" o Title 10, Code of Federal Regulations, Parts 20 and 50 o ANSI Standard N.18.7-1976 o ANSI Standard N.13.11
WBN Emergency Exposure Guidelines EPIP.I 5 Unit 0 Rev. 0018 Paoe 5 of {5 3.0 INSTRUCTIONS NOTE Specific definitions as used in this procedure are contained in Appendix D. A. The Site Emergency Director (SED) is the gly individual responsible for authorizing Emergency dose limits in excess of TVA Administrative dose limits and 10 CFR 20.1201. Appendix A and B shall be used to provide written authorization. NOTE As defined by the emergency situation, this approval may be relayed verballv and documented later. B. The Radiation Protection (RP) Group is responsible for completing Appendix B page 4 of 4, "Authorization to Exceed Occupational Dose Limits," obtaining the Site Emergency Directo/s approval and willperform radiologicalsurveys or other assessments to estimate the radiation doses. C. ln all cases, the site RP Manager shall be informed of any emergency exposure immediately so that a determination of the total quarterly exposure can be made. Based on the results of the determination, the worker may be restricted from further dose.
WBN Emergency Exposure Guidelines EPIP-I 5 Unit 0 Rev. 0018 Paqe 6 of 15 EXPOSURE LIMITATIONS ACTIONS FOR LIFE SAVING OR PROTECTION OF THE PUBLIC A. For immediate activities up to 25 Rem which are necessary to:
- 1. Save Human Life.
For lifesaving operations situations may occur in which a dose in excess of 25 Rem would be required. It is not possible to prejudge the risk that one person should be allowed to take to save the life of another. However, persons undertaking an emergency mission in which the dose would exceed 25 Rem to the whole body should do so only on a voluntarv basis and with fullawareness of the risks involved.
- 2. Restore equipment necessary to maintain criticalsafety functions or to establish and maintain a safe shutdown,
- 3. Prevent or Mitigate a release of radioactivity to the environment for which off-site protective measures may be required. For these activities, the TEDE of personneldirectly involved shall not exceed 25 Rem. This limit is applicable only if actions establishing adequate or equivalent protection, with less dose, are not readily available.
B. Limit for lens of eye is Zlfiegq, or three (3) times the TEDE value. C. Limit for any other organ (including skin and body extremities) is !![@, or ten (10) times the TEDE value. ACTIONS FOR IiIiIEDIATE REPAIR OR TO PREVENT THE FAILURE OF EQUIPI.IENT A. For activities performed on an immediate basis to @the failure of equipment necessary to protect the public health and safety, the TEDE of personnel directly involved shall not exceed 10 Rem. This limit is applicable only if actions establishing adequate or equivalent protection, with a less dose consequence, are not readily available. B. Limit for Iens of eye of ![@, three (3) times the TEDE limit.
- c. Limit for any other organ (including skin and body extremities) of 1!939!0, or ten (10) times the TEDE limit.
TNTERNAL EXPOSU RE (EMERGENCY WORKERS) A. Guidelines for internal exposure controls of \A/BN emergency workers are provided in Appendix C.
WBN Emergency Exposure Guidelines EPIP.I 5 Unit 0 Rev. 00,l I Paoe 7 of 15 3.1 ,4 POST.EXPOSURE EVALUATIONS A. Personnel receiving emergency or accident exposures should be restricted from further occupational exposure pending the outcome of exposure evaluations and, if necessary, medical surveillance. B. An exposure evaluation shall be performed to determine the individualdose. RP shallconduct post exposure dose assessments for exposed individuals, with particular attention to determining the adequacy of administrative dosimeter correction factors for TEDE doses resulting from internal and external exposures. This evaluation should be based on observed area dose rates, airborne activity measurements, and dosimetry results. The evaluation shall be documented in an appropriate format and filed with the individual's exposure records. Appropriate reports shall be submitted to RP and the US NRC. C. Any exposures above 5 Rem TEDE shall be reported to a TVA physician or designee. lt is the responsibility of the physician to determine appropriate medicalevaluations and required care. Cross reference guidance is in EPIP-10. 3.{.5 EMERGENCY DOSE EXTENSIONS A. ln REP emergency situations, planned doses to radiologicalworkers can be extended beyond the TVA administrative limits to the 10 CFR 20 regulatory limits. 3.1.6 ADDITIONALINSTRUCTIONS A. Refer to Appendix A and B of this procedure.
WBN Emergency Exposure Guidelines EPIP-{ 5 Unit 0 Rev. 00{ I Paoe 8 of 15 4.0 RECORDS 4.1 AA Records The following records are QA records when completed during actual radiological emergencies. Appendix B: General lnstructions for Emergency Exposures 4.2 Non-CIA Records A. Emergency Records The records generated due to declaration of an emergency classification are considered Lifetime Retention records. These records shall be forwarded to the
\ rBN EP Manager. The records necessary to demonstrate performance are then submitted to the Corporate EP Manager for storage.
B. Drilland Exercise Records The records deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be foruarded to the l /BN EP Manager. The \l/BN EP Manager shall retain records necessary to demonstrate six-year plan requirements for six years. The VUBN EP Manager shall retain other records in this category for three years (eight years starting the after the next HAB Drill).
WBN Emergency Exposure Guidelines EPIP.{ 5 Unit 0 Rev. 0018 Paqe 9 of {5 Appendix A (Page { of 1} Watts Bar Emergency Exposure Reference hergency r*.rpo*dcrs
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WBN Emergency Exposure Guidelines EPIP.I 5 Unit 0 Rev. 00{ 8 Paqe 10 of 15 Appendix B (Page I of 4) General lnstructions For Emergency Exposures A. These (emergency) limits are in excess of 10 CFR 20 limits. These limits apply only to olanned exposures and not to spontaneous reactions by individuals attempting to mitigate the accident. B. Emergency exposure limits apply only to TVA personnel, who are qualified as radiation workers at the plant and have been issued dosimetry. C. Personnelwho have received previous accident or emergency exposure in excess of 25 Rem TEDE shall not participate in further emergency exposure situations. D. Personnelwho have declared pregnancy in accordance with other site procedures, shall not participate in emergency exposure situations. E. Receipt of emergency dose limits shall be on a voluntary basis. Other factors being equal, older volunteers should be selected first. F. Personnel receiving emergency exposures, in excess of 25 Rem, shall be informed 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. EPA tables are provided following these general instructions for this purpose. G. Personnel shall not enter any area where dose rates are unknown or unmeasurable with instruments and dosimetry immediately available. H. lnternal exposure should be minimized by the use of respiratory protection equipment. Respirator lssue Guidelines are given in Appendix C. Protective clothing should be used to minimize personal contramination.
- l. The dose of personnel authorized to receive emergency exposures shall be monitored and recorded as provided for in the Site RP procedures.
J. The exposure of personnel during emergency operations shall be maintained as low as reasonably achievable (ALARA).
WBN Emergency Exposure Guidelines EPIP.I 5 Unit 0 Rev. 00,I I Paqell of{5 Appendix B (Page 2 ol 4l K. The dose limits specified in this procedure are intended as upper limits for guidance during emergency situations, and planned doses for rescue and emergency repairs. Recovery operations shallgg! exceed these limits. L. lf a projected dose to the thyroid is expected to exceed 10 Rem during a radiologicalemergency, Potassium lodide (Kl) should be issued in accordance with EPIP-14 to on-site personnel as a protective measure. The SED shall be informed prior to issuance. M. The RP Group will prepare Appendix B page 4 of 4, Authorization to Exceed Occupational Dose Limits and obtain the Site Emergency Director's approval. N. Following the exposure, these individuals must be removed from areas where they can receive additional dose. NOTES
- 1) Until isotopic assessments of airborne radioactivity are available, an administrative correction factor of 2 should be used to estimate TEDE exposures in airborne activity areas:
Estimated TEDE = dosimeter reading x 2
- 2) The above value corresponds to the ratio of external (measured) dose to estimated TEDE dose, in accordance with default values in the TVAs Dose Assessment model.
When accident specific nuclide assessments are available, more definitive dose assessments should be performed to adjust the conection factors.
WBN Emergency Exposure Guidelines EPIP-I 5 Unit 0 Rev. 0018 Paqe 12 of 15 Appendix B (Page 3 of 4) EPA Emergency Exposure Risk Information (for personnel briefing on emergency exposures of 25 Rem TEDE)
. Approximate Cancer Risk to Average lndividuals from 25 Rem Effective Dose Equivalent Delivered Promptly.
Age at Exposure (years) Risk of Premature Death Average years of life lost (deaths per 1,000 persons if premature death occurs exposed) (years) 20 to 30 9.1 24 30 to 40 7.2 19 40 to 50 5.3 15 50 to 60 3.5 11 NOTE Tables referenced from the Environmental Protection Agency's "Manual of Protective Action Guides and Protective Actions for Nuclear lncidents,' (EPA-400), May 1992, page 2-12. o Health Effects Associated with \tVhole Body Absorbed Doses Received \Mthin a Few Hours. ffiole Body Absorbed Early Fatalities2 Wrole Body Absorbed Prodromal Effects3 Dose (percent) Dose (percent) (rad) (rad) 140 5 50 2 200 15 100 15 300 50 150 50 400 85 200 85 460 95 2sa 98 1 Risks will be lower for protracted exposure periods. 2 Supportive medical treatment may increase the dose at which these frequencies occur by approximately 50 percent. t Forewaming symptoms of more serious health effects associated with large doses of radiation.
WBN Emergency Exposure Guidelines EPIP.{ 5 Unit 0 Rev. 0018 Pase {3 of {5 Appendix B (Page 4 ot 4l Authorization To Exceed Occupational Dose Limits Form The persons listed below are authorized to exceed the TVA dose limits for the whole body and extremities during the evaluation or mitigation of an emergency situation. Emergency limits are in excess of 10 CFR 20.1201 Iimits. The persons listed below acknowledge they have volunteered for this assignment, and have been briefed on the emergency situation, and have been made aware of possible consequences of the estimated radiation dose(s). Hand carry or FAX to the TSC for SED Signature NAME EMPLOYEE ID# SIGNATURE DOSE LrMrT (REM) 1 2 3 4 5 6 7 8 I 10 RP Survey No. (lf Applicable): Emergency Location(s) Estimated Doses Remarks: Prepared by: sign and date Authorized by: sign and date Site Emergency Director Hand carry or FAX to the OSC after SED signs.
WBN Emergency Exposure Guidelines EPIP.I 5 Unit 0 Rev. 0018 Paqe 14 of 15 Appendix G (Page { of {) Emergency Respirator lssue Guidelines NOTE THESE GUIDELINES ARE RECOMMENDATIONS ONLY, SUBJECT TO THE JUDGEMENT OF RP AND EMERGENCY MANAGEMENT PERSONNEL, THESE GUIDELINES ARE APPLICABLE ONLY TO PROTECTION FROM AIRBORNE RADIOACTIVE MATERIAL AND DO NOT APPLY TO RESPIRATORS/SCBA'S ISSUED FOR PROTECTION FROM INDUSTRIAL OR CHEMICAL HAZARDS OR ATMOSPHERES IMMEDIATELY HAZARDOUS TO LIFE OR HEALTH. TASKS TO SAVE A LIFE OR Respirator/SGBA not reguired to enter airborne radioactivity PREVENT SIGNIFICANT areas provided resulting internal dose plus external dose will DAMAGE TO PLANT not result in TEDE exceeding NRG dose limits or, if approved by the SED, doses up to the TVA emergency dose limits (i.e., up to 25 Remll0 Rem) (this can include uptakes > { ALI} HIGH PRIORITY TASKS o Respirator/SCBA not required to enter airborne areas if the (priority I or 2) following are true: NOTE: IF INDIVIDUAL'S TOTAL . lndividual's internal dose plus external dose will not result INTAKE FORTHE YEAR in TEDE exceeding NRC annual dose limit; and TO DATE EXCEEDS 2OO DAG-HRS., DOSE . Delays or hindrances caused by issuing or urearing RESULTING FROM ALL respirators/SCBAS will ieopardize the success or timeliness INTAKES FOR THE YEAR of the task; or TO DATE MUST BE ASSESSED IN . Use of a respirator/SCBA will result in a higher TEDE to the DETERNilINING THE TEDE, responding individuals. LOllll or illD PRIORITY TASKS Use NPGPP{5.2.5 for respirator issue guidance. NOTE Protective requirements may be revised at the discretion of the TSC RP Manager as sample data becomes available.
WBN Emergency Exposure Guidelines EPIP.I 5 Unit 0 Rev. 00{ 8 Paqe 15 of 15 Appendix D (Page I of 1) Definitions Accident Exposure - Exposure to radiation or radioactive materials that results from an unexpected event. Accident exposure refers to the immediate consequences of the unexpected event and the immediate corrective/mitigative actions of personnel present at the scene where the event occurred. Accident exposures are not controlled by the Radiological Emergency Plan (REP), and may be reportable to the NRC under 10 CFR 2G andlot'10 CFR 50.72. CDE - Commifted Dose Equivalent CEDE - Committed Effective Dose Equivalent DAC - Derived Air Concentration DDE - Deep Dose Equivalent Emeroencv Exposure - Exposure to radiation or radioactive materials that is the result of actions taken in response to an emergency condition classified and declared pursuant to the Wafts Bar Radiological Emergency Plan (REP). Emergency exposure refers to radiation exposure caused by those assessments, corrective, and mitigative actions that are required on an immediate basis to protect human lives, or to prevent or minimize the collective exposure of large populations. Such activities are directed by the Control Room or by the TSC. LDE - Eye Dose Equivalent Life Savinq Action - Those actions related to the search and rescue of injured persons. Planned Special Exposure (PSEI - As defined in 10 CFR 20, an infrequent exposure to radiation, separate from and in addition to the annual dose limits. PSEs might be warranted in the recovery phase. However, it is unlikely that the PSE requirements could be met during the initial phases of the emergency. RADTREM - For purposes of this implementing procedure, radiation exposure as expressed in units of R/hr and subunits, thereof, is equivalent to dose (Rad) and dose equivalent (Rem) based on ANSI-N 13.11 development and terminology. Any acute dose greater than 10 Rem is generally denoted in units of Rad, since that Ievel is considered as the accident range of personnel exposure. Any dose less than that level is considered the protective range of personnel exposure. For purposes of this procedure the assumption of 1 Rad = 1 Rem is assumed for all levels of exposure. SDE - Shallow Dose Equivalent TEDE - Total Effective Dose Equivalent}}