ML19004A302: Difference between revisions

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{{Adams
#REDIRECT [[PLA-7758, Emergency Plan Changes Revision 61 to Revision 62]]
| number = ML19004A302
| issue date = 12/19/2018
| title = Emergency Plan Changes Revision 61 to Revision 62
| author name =
| author affiliation = Susquehanna Nuclear, LLC, Talen Energy
| addressee name =
| addressee affiliation = NRC/NRR
| docket = 05000387, 05000388
| license number =
| contact person =
| case reference number = PLA-7758
| document type = Emergency Preparedness-Emergency Plan, Emergency Preparedness-Emergency Plan Implementing Procedures
| page count = 422
}}
 
=Text=
{{#Wiki_filter:Enclosure 1 to PLA-7758 List of Changes Contained in Revision 62 to SSES Emergency Plan Enclosure 1 to PLA-7758 Page 1 of2 Emergency Plan Changes Revision 61 to Revision 62 1. Revision 62 of the Emergency Plan takes credit for the 2018 annual review. (S2018-10-25-0l)
: 2. Replaced "Manager-Emergency Preparedness" with "Manager-Security/Emergency Preparedness" throughout the document per recent organizational changes at SSES (S2018-03-28-01)
: 3. Updated Figures 4.1 and 4.2. (S2018-10-25-01)
: 4. Replaced "outlines" with "outlined" in second paragraph of section 5.1.4. (S2018-10-25-01)
: 5. Added "(Alert or higher emergency declaration)" after "classification" in Section 6.0, phase II section. (S2018-10-25-01)
: 6. Removed section 6.2.7e from the Security Coordinator responsibility to section 6.2.1.p. to align with current implementing procedures (S2018-10-25-01)
: 7. Combined sections 6.2.5.a with 6.2.5.i in current step 6.2.5.a and renumbered the remaining steps. (S2018-10-25-01)
: 8. Added responsibilities for Recovery Manager and Dose Assessment Supervisor in steps 6.3 .1.1.m and 6.3.1.4.h to approve/ advise, respectively, dose extensions for field monitoring teams personnel under EOF command and control (S2018-10-02-01, changes l.a and 7.c and 7.e). 9. Corrected typo in section 6.3.1.5 (S2018-10-25-0l)
: 10. Added EOF Technical Advisor position to Figure 6.4 (S2018-10-25-01)
: 11. Reordered bullets in bulleted list in section 7.1. (S2018-10-25-0l)
: 12. Deleted reference to supplemental meteorological tower from section 7 .1.1.1 (S2018-10-29-01/E2018-10-29-03)
: 13. Replaced "wind variability" with "wind direction variability" in the first paragraph of section 7.1.1.1. (S2018-10-25-0l)
: 14. Replaced and with when in the seventh paragraph in Section 7.1.1.3. (S2018-10-25-01)
: 15. Deleted "To the extent reasonable, persons with high lifetime cumulative radiation exposure should not take part in these actions." from Table 7.2 to eliminate this criteria from dose extension decisions and thus increase ERO responsiveness. (S2018-10-24-01/E2018-10-24-01)
: 16. Replaced"-" with empty spaces in Health Effects Associated with Whole Body Absorbed Doses Received Within a Few Hours Table in Table 7 .2. (S2018-10-25-01)
: 17. Replaced TSC with CR in the second paragraph of section 8.1.2. (S2018-10-25-0l)
: 18. Updated name and address for PEMA Headquarters in section 8.3.2. (S2018-10-25-01)
: 19. Updated location of the redundant control ANS station in section 8.5.4. (E2018-04-26-01)
: 20. ' Refined description of the plant computer capabilities in the 5th bullet in Section 8.9.1. (S2018-10-25-01)
: 21. Removed the phrase "For Example: Offsite Emergency Calendars)" from section 9.4.4. (S2018-10-25-01)
Enclosure 1 to PLA-7758 Page 2 of2 22. Updated MOA for heavy equipment in Appendix A (E2018-10-29-01)
: 23. Updated Fire Department MOA in Appendix A. (E2018-I0-29-02)
: 24. Deleted "EOF Information Coordinator" from Appendix C as this position was eliminated (S2017-10-25-01
). 25. Deleted "OSC Clerk" from Appendix C as this position was eliminated (S2017-11-21-01)
: 26. Updated equipment in Appendix D Enclosures (E2018-04-13-01)
: 27. Updated Corporate Policy letter in Appendix E with current CNO signature. (S2018-10-25-01)
Enclosure 2 to PLA-7758 List of Applicable 10 CFR 50.54(q) Screens and Evaluations Enclosure 2 to PLA-7758 Page 1 of 1 List of Applicable 10 CFR 50.54(q) Screens and Evaluations
: 1. E2018-04-13-01
: 2. E2018-04-26-01
: 3. E2018-10-24-0l
: 4. E2018-10-29-01
: 5. E2018-10-29-02
: 6. E2018-10-29-03
: 7. S2017-10-25-0l
: 8. S2017-11-21-01
: 9. S2018-03-28-01 10.S2018-10-02-01
: 11. S2018-10-24-01
: 12. S2018-10-25-01
: 13. S2018-10-29-01 Enclosure 3 to PLA-7758 SSES Emergency Plan Revision 62 Emergency Plan, Rev. 62, Page 1 of 295 SUSQUEHANNA NUCLEAR, LLC SUSQUEHANNA STEAM ELECTRIC STATION EMERGENCY PLAN REVISION 62 DATE:11/28/2018 PORC MEETING: 18-11-13 Emergency Plan, Rev. 62, Page 2 of 295 SUSQUEHANNA NUCLEAR, LLC SUSQUEHANNA STEAM ELECTRIC STATION 1EAM SUSQUEHANNAŽ
: ** Generatin,g:Excellence EMERGENCY PLAN *. THIS DOCUMENT HAS BEEN UPDATED TO INCLUDE REVISIONS THROUGH §1 DATED: 11/28/2018 NOTE: Emergency Plan, Rev. 62, Page 3 of 295 AFFECTED PAGES PPL Susquehanna, LLC was reorganized to Susquehanna Nuclear, LLC. Susquehanna is now a part of parent company Talen instead of PPL. Agreements signed in the past as PPL Susquehanna, LLC will be honored and carried forward by Susquehanna Nuclear, LLC. 1. Revision 62 of the Emergency Plan takes credit for the 2018 annual review. 2. Replaced "Manager-Emergency Preparedness" with "Manager-Security/Emergency Preparedness" throughout the document per AR-2018-04646 (S2018-03-28-01)
: 3. Updated Figures 4.1 and 4.2 per AR-2018-13801. (S2018-10-25-01)
: 4. Replaced "outlines" with "outlined" in second paragraph of section 5.1.4. (S2018-10-25-01)
: 5. Added "(Alert or higher emergency declaration)" after "classification" in Section 6.0, phase II section. (S2018-10-25-01)
: 6. Removed section 6.2.7e from the Security Coordinator responsibility to section 6.2.1.p per AR-2017-09053 and AR-2017-20479. (S2018-10-25-01)
: 7. Combined sections 6.2.5.a with 6.2.5.i in current step 6.2.5.a and renumbered the remaining steps. (S2018-10-25-01)
: 8. Added steps 6.3.1.1.m and 6.3.1.4.h per AR-2018-13835 (S2018-10-02-01, changes 1.a and 7.c and 7.e). 9. Corrected typo in section 6.3.1.5 (S2018-10-25-01)
: 10. Added EOF Technical Advisor position to Figure 6.4 per AR-2018-13095. (S2018-10-25-01)
: 11. Reordered bullets in bulleted list in section 7.1. (S2018-10-25-01)
: 12. Deleted reference to supplemental meteorological tower from section 7.1.1.1 per AR-2017-17969 (S2018-10-29-01/E2018-10-29-03)
: 13. Replaced "wind variability" with "wind direction variability" in the first paragraph of section 7.1.1.1. (S2018-10-25-01)
: 14. Replaced and with when in the seventh paragraph in Section 7.1.1.3. (S2018-10-25-01)
: 15. Deleted 'To the extent reasonable, persons with high lifetime cumulative radiation exposure should not take part in these actions." from Table 7.2 per AR-2018-13465. (S2018-10-24-01/E2018-10-24-01)
: 16. Replaced "-" with empty spaces in Health Effects Associated with Whole Body Absorbed Doses Received Within a Few Hours Table in Table 7.2. (S20~8-10-25-01)
: 17. Replaced TSC with CR in the second paragraph of section 8.1.2. (S2018-10-25-01)
: 18. Updated name and address for PEMA Headquarters in section 8.3.2 per AR-2018-06092. (S2018-10-25-01)
: 19. Updated location of the redundant control ANS station in section 8.5.4 per AR-2018-06919. (E2018-04-26-01)
: 20. Refined description of the plant computer capabilities in the 5th bullet in Section 8.9.1. (S2018-10-25-01)
: 21. Removed the phrase "For Example: Offsite Emergency Calendars)" from section 9.4.4 per DPA-10-Dl-2018-06672. (S2018-10-25-01)
: 22. Updated MOA for heavy equipment in Appendix A per ACT-02-CR-2018-037 42 (E2018-10-29-01)
: 23. Updated Fire Department MOA in Appendix A per ACT-02-CR-2018-12173. (E2017-08-25-01)
: 24. Deleted "EOF Information Coordinator" from Appendix C per DPA-06-Dl-2018-06672 (S2017-10-25-01
). 25. Deleted "OSC Clerk" from Appendix C per AR-2017-20382 (S2017-11-21-01)
: 26. Changed Appendix D Enclosures per AR-2018-04987 (E2018-04-13-01)
: 27. Updated Corporate Policy letter in Appendix E with current CNO signature. (S2018-10-25-01)
Emergency Plan, Rev. 62, Page 4 of 295 ,:_, *, /.:";_*/_ .l.fE'J)'1:*cot{teJ~11s,~:,, .... , *.* '' , ... . / .' ;,., *01 ' } \ ; : ' . ' .. '' SECTION TITLE PAGE 1.0 DEFINITIONS 7 2.0 ACRONYMS 18
 
==3.0 REFERENCES==
 
20 4.0 SCOPE AND CONTENTS 22 5.0 EMERGENCY CONDITIONS 26 5.1 CLASSIFICATION SYSTEM 26 5.2 SPECTRUM OF POSTULATED ACCIDENTS 28 6.0 ORGANIZATIONAL CONTROL OF EMERGENCIES 48 6.1 NORMAL OPERATING ORGANIZATION 50 6.2 ON-SITE EMERGENCY ORGANIZATION
-(PHASE II) 51 6.3 OFF-SITE RESOURCES AND ACTIVITIES
-(PHASE Ill) 57 6.4 COORDINATION WITH PARTICIPATING GOVERNMENT AGENCIES 62 6.5 RESTORATION 65 7.0 EMERGENCY MEASURES 76 7.1 ASSESSMENT ACTIONS FOR ALL EMERGENCY CLASSIFICATIONS 76 7.2 CORRECTIVE ACTIONS 80 7.3 PROTECTIVE ACTIONS 80 7.4 AID TO AFFECTED PERSONNEL 84 8.0 EMERGENCY FACILITIES AND EQUIPMENT 93 8.1 ON-SITE EMERGENCY CENTERS 93 8.2 SUSQUEHANNA OFF-SITE EMERGENCY CENTERS 101 8.3 COUNTY AND STATE EMERGENCY CENTERS 104 8.4 ASSESSMENT CAPABILITIES 104 8.5 PROTECTIVE FACILITIES 105 8.6 ADDITIONAL COMMUNICATIONS SYSTEMS 106 8.7 ON-SITE FIRST AID AND MEDICAL FACILITIES 106 8.8 DAMAGE CONTROL EQUIPMENT 107 8.9 INFORMATION SYSTEMS 107 9.0 MAINTAINING EMERGENCY PREPAREDNESS 114 9.1 ORGANlzA TIONAL PREPAREDNESS*
114 9.2 REVIEW AND UPDATING*
119 9.3 MAINTENANCE AND INVENTORY OF EMERGENCY EQUIPMENT/
SUPPLIES 120 9.4 PUBLIC EDUCATION AND INFORMATION 120 10.0 APPENDICES A LETTERS OF AGREEMENT 124 B WIND ROSES, DOSE/DISTANCE PLOTS AND JOINT FREQUENCY 126 DISTRIBUTION C SSES EMERGENCY PLAN POSITION SPECIFIC PROCEDURES (TYPICAL) . 143 D EQUIPMENT INFORMATION LISTINGS 145 E SUSQUEHANNA NUCLEAR, LLC POLICY STATEMENT 161 F DEVIATIONS to NEI 99-01, Rev 6 163 G SSES EVACUATION TIME ESTIMATES 165 H DOWNSTREAM SUSQUEHANNA RIVER WATER USAGE 188 I POPULATION UPDATE FOR SSES EMERGENCY PLANNING ZONE 191 ' J NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS 193 REFERENCE TO SSES EMERGENCY PLAN K ON-SHIFT STAFFING ANALYSIS 203 Page 1 of 3 Emergency Plan, Rev. 62, Page 5 of 295 LISTING OF TABLES -----TABLE TITLE PAGE Section ABNORMAL RAD LEVELS/RADIOLOGICAL EFFLUENT 35 5-Table R Section FISSION PRODUCT BARRIER DEGRADATION 36 5-Table F Section SYSTEM MALFUNCTIONS 37 5-Table S Section HAZARDS 38 5-Table H Section ISFSI 39 5-Table E Section COLD SHUTDOWN/REFUELING SYSTEM MALFUNCTIONS 40 5-Table C 5.1 TABLE DELETED N/A 5.2 EMERGENCY ACTIONS BASED ON CLASSIFICATION 41 6.1 STATION EMERGENCY PLAN MINIMUM STAFFING REQUIREMENTS 67 6.2 ADDITIONAL ASSISTANCE FROM OUTSIDE SUSQUEHANNA NUCLEAR, LLC 70 7.1
 
==SUMMARY==
OF IMMEDIATE NOTIFICATION AND RESPONSE FOR ALL 85 CLASSIFICATIONS
 
===7.2 EMERGENCY===
 
EXPOSURE CRITERIA 87 7.3 PROTECTIVE ACTION RECOMMENDATIONS 90 8.1 RELATIONSHIP OF THE PRIMARY PARAMETER, SECONDARY DISPLAY, AND 109 ALGORITHMS ON SPDS 9.1 TRAINING OF SUSQUEHANNA SES EMERGENCY RESPONSE PERSONNEL 121 Page 2 of 3 Emergency Plan, Rev. 62, Page 6 of 295 I --LJSflNG OF FIGURES --.. -I FIGURE TITLE PAGE 4.1 MAP OF SSES VICINITY 24 4.2 MAP OF SSES 50 MILE INGESTION EXPOSURE ZONE 25 6.1 DELETED (NUCLEAR DEPARTMENT ORGANIZATION
-FSAR) FIGURE 13.1-3 N/A 6.2 TSC ORGANIZATION 71 6.3 OSC ORGANIZATION 72 6.4 EOF ORGANIZATION 73 6.6 LONG TERM RESTORATION ORGANIZATION 74 6.7 COMMUNICATION INTERFACES WITH OFFSITE AGENCIES 75 8.1 MAP OF THE SUSQUEHANNA SES EMERGENCY FACILITIES 110 8.2 TECHNICAL SUPPORT CENTER FLOOR PLAN 111 8.3 EMERGENCY OPERATIONS FACILITY/JOINT INFORMATION CENTER FLOOR 112 PLAN 8.4 SIREN LOCATION 113 Page 3 of 3 
: 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. Emergency Plan, Rev. 62, Page 7 of 295 ACCIDENT -an unforeseen and unintentional event which may result in an emergency.
ACTIVATE -an emergency response facility has sufficient staffing to perform required functions and fhe facility has taken over command and control of the emergency.
The positions required to activate the TSC, OSC and EOF are specified with an
* in Figures 6.2, 6.3 and 6.4. The terms "activated", "activation" "activation time" and "take over management of the emergency" have the same definition.
AFFECTING SAFE SHUTDOWN -Event in progress has adversely affected functions that are necessary to bring the plant to and maintain it in the applicable HOT or COLD SHUTDOWN condition.
Plant condition applicability is determined by Technical Specification LCOs in effect. Example 1: Event causes damage that result in entry into an LCO that requires the plant to be placed in HOT SHUTDOWN.
HOT SHUTDOWN-is achievable, but COLD SHUTDOWN is not. This event is not "AFFECTING SAFE SHUTDOWN." Example 2: Event causes damage that result in entry into an LCO that requires the plant to be placed in COLD SHUTDOWN.
HOT SHUTDOWN is achievable, but COLD SHUTDOWN is not. This event is "AFFECTING SAFE SHUTDOWN." ALERT -Events are in process or have occurred _which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels. ANNUAL -occurring within calendar year starting January 1.and ending December 31. ALERT NOTIFICATION SYSTEM -sirens with ratings of 121 dB at 100' within the ten-mile EPZ around the Susquehanna Steam Electric Station. Siren location was determined by a detailed study including field surveys, actual determination of average background noise level, and consideration of population distribution within the 10-mile EPZ. ASSESSMENT ACTIONS -those actions taken during or after an incident to obtain and process information that is necessary to make decisions to implement specific emergency measures.
BIENNIAL EXERCISE -NRC/DHS-FEMA exercise performed on alternate years, to be completed within the calendar year scheduled.
BIWEEKLY -occurring on alternate weeks, within the 7-day week. BOMB -refers to an explosive device suspected of having sufficient force to damage plant systems or structures.
Page 1 of 11 Emergency Plan, Rev. 62, Page 8 of 295 11. CAN/CANNOT BE MAINTAINED ABOVE/BELOW-The value of an identified parameter is/is not able to be held within the specified limit. The determination requires an evaluation of system performance and availability in relation to parameter values and trends. An instruction prescribing action when a parameter cannot be maintained above or below a specified limit neither requires nor prohibits anticipatory action-depending upon plant conditions, the action may be taken as soon as it is determined that the limit will ultimately be exceeded, or delayed until the limit is actually reached. Once the parameter does exceed the limit, however, the action must be performed; it may not be delayed while attempts are made to restore the parameter to within the desired control band. 12. CAN/CANNOT BE RESTORED ABOVE/BELOW
-The value of an identified parameter is/is not able to be brought within the specified limit. The determination requires an evaluation of system performance and availability in relation to parameter values and trends. Ari instruction prescribing action when a value CANNOT BE RESTORED AND MAINTAINED above or below a specified limit does not require immediate action simply because the current values is outside the range, but does not permit extended operation beyond the limit; the action must be taken as soon as it is apparent that the specified range cannot be attained.
: 13. COE -the Committed Dose Equivalent; dose to an organ due to an intake of radioactive material during the 50 year period following the intake. 14. COLUMBIA COUNTY EMERGENCY MANAGEMENT AGENCY (CCEMA)-emergency response coordinating agency for Columbia County, responsible for implementing off-site action upon direct notification from Susquehanna SES or PEMA. 15; CONFINEMENT BOUNDARY -the barrier(s) between spent fuel and the environment once the spent fuel is processed for dry storage. As related to the Susquehanna ISFSI; Confinement Boundary is defined as the Dry Shielded Canister (DSC). 16. CONTAINMENT CLOSURE -the procedurally defined conditions or actions taken to secure Primary or Secondary Containment and its associated structures*, systems, and components as a functional barrier to fission product release under shutdown conditions.
: 17. CONTROL ROOM -the location of the Control Panels from which the reactor and its auxiliary systems are controlled.
: 18. CORPORATE LEADERSHIP COUNCIL (CLC) -the Talen Management group which determines major policy commitments for the company. The CLC membership includes the President of the company and other senior executives.
: 19. CORRECTIVE ACTIONS -those emergency measures taken to ameliorate or terminate . an emergency situation.
: 20. DEPARTMENT OF ENVIRONMENTAL PROTECTION/BUREAU OF RADIATION PROTECTION
<DEP/BRP)
-the State agency responsible to provide guidance and recommendations for specific off-site protective measures.
: 21. DEPARTMENT OF HOMELAND SECURITY -Federal Emergency Management Agency (DHS-FEMA)
-within the context of this plan, serves as-the primary contact for requests for Federal assistance; lead coordinator all non-technical federal response.
Page 2 of 11 Emergency Plan, Rev. 62, Page 9 of 295 22. DOSE PROJECTION
-a calculated estimate of the potential radiation dose to individuals at a given location, normally off-site, (determined from the quantity of radioactive material released and the appropriate meteorological transport and dispersion parameters).
: 23. DOSE RATE -the amount of radiation an individual can potentially receive per unit of time. 24. EFFECTIVE DOSE EQUIVALENT (EDE) -the sum.of the products of the dose equivalent to the organ or tissue and the weighting factors applicable to each of the body organs or tissues that are irradiated.
: 25. EMERGENCY ACTION LEVELS (EAL) -A predetermined, site-specific, observable threshold for an Initiating Condition that, when met or exceeded, places the plant in a given emergency classification level. 26. EMERGENCY ACTIONS -those steps taken, as a result of exceeding an Emergency Action Level in the Emergency Plan, to ensure that the situation is assessed and that the proper corrective and/or protective actions are taken. 27. EMERGENCY ALERT SYSTEM (EAS)-radio and television broadcast system used by public emergency management officials to notify the public concerning protective actions to be taken in the event of natural disasters, radiological protective actions, and other information of immediate impact to the public. Formerly referred to as the Civil Defense Emergency Broadcast System. 28. EMERGENCY CLASSIFICATION LEVEL (ECL) -One of a set of names or titles established by the US Nuclear Regulatory Commission (NRC) for grouping off-normal events or conditions according to (1) potential or actual effects or consequences, and (2) resulting onsite and offsite response actions. The emergency classification levels, in ascending order of severity, are:
* Notification of Unusual Event (NOUE) -synonymous with Unusual Event (UE)
* Alert
* Site Area Emergency (SAE)
* General Emergency (GE) 29. EMERGENCY CONDITION
-the characterization of several classes of emergency situations consisting of exclusive groupings including the entire spectrum of possible radiological emergency situations.
The four classes of emergencies, listed in increasing severity, which Susquehanna has,incorporated into this Emergency Plan, are outlined in Section 5.0 of this plan. 30. EMERGENCY COORDINATORS
-designated Susquehanna SES staff members responsible for coordinating specific emergency organization functions
.. 31. EMERGENCY DIRECTOR (ED) -the Susquehanna individual responsible for direction of on-site activities during an emergency at the Susquehanna SES. 32. EMERGENCY OPERATIONS CENTERS -designated state and county emergency management agency headquarters facilities designed and equipped for the purpose of exercising effective coordination and control over disaster operations carried out within their jurisdiction.
Page 3 of 11 Emergency Plan, Rev. 62, Page 10 of 295 33. EMERGENCY OPERATIONS FACILITY -Emergency Response Facility co-located with the Joint Information Center in Plains Township, Pennsylvania, to provide continuous coordination and evaluation of Susquehanna activities during an emergency having or potentially having environmental consequences (Reference REFERENCES, Section 3.19). 34. 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 10 CFR 100.11. The dose criterion of 10 CFR 50.67 applies at the EXCLUSION AREA boundary.
: 35. EMERGENCY PLAN IMPLEMENTING PROCEDURES
-specific procedures defining in detail the action to be taken in the event of an emergency condition.
The Emergency Plan Implementing Procedures will be separate from, but may incorporate and refer to, normal plant operating procedures and instructions, Emergency Plan Position Specific Procedures and Emergency Plan Technical Procedures.
: 36. EMERGENCY PLAN TECHNICAL PROCEDURES
-procedures describing how to perform processes associated with the Emergency Plan. These procedures may include processes such as Emergency Classification .or Protective Action. Used together with Emergency Plan Position Specific Procedures, these procedures are designed to implement the Emergency Plan during a declared emergency.
: 37. EMERGENCY PLANNING ZONE -there are two Emergency Planning Zones. The first is an area, approximately 1 O miles in radius around the Susquehanna SES, for which emergency planning consideration of the plume exposure pathway has been given in order to ensure that prompt and effective actions can be taken to protect the public in the event of an accident.
The second is an area_approximately 50 miles in radius around the Susquehanna SES, for which emergency planning consideration of the ingestion
* exposure pathway has been given. 38. EMERGENCY PLAN POSITION SPECIFIC PROCEDURES
-procedures describing how to perform tasks assigned to emergency positions.
Each procedure includes an overview of the position's tasks, detailed instr.uctions, and relevant material.
Used together, these procedures are designed to implement the Emergency Plan during a declared emergency.
: 39. EMERGENCY PROTECTION AGENCY PROTECTIVE ACTION GUIDELINES
-Environmental Protection Agency Protective Action Guidelines.
The EPA PAGs. are expressed in ten,:is of dose commitment 1 Rem TEDE or 5 Rem COE Thyroid. Actual or projected offsite exposures in excess of the EPA PAGs require Susquehanna to recommend protective actions for the general public to offsite planning agencies.
: 40. EMERGENCY RESPONSE ORGANIZATION (ERO) -The SSES organization that is activated when an emergency classification has .been declared that meets one of the four emergency classifications.
: 41. EXCLUSION AREA -is a circle of radius 1800 feet with the center at the common release point on the Unit 1 and Unit 2 Reactor Buildings as determined in accordance with 10 CFR100.11.
The dose Criterion of 10 CFR 50.67 applies at the EXCLUSION AREA boundary.
Page 4 of 11 Emergency Plan, Rev. 62, Page 11 of 295 42. EXPLOSION -A rapid, violent and catastrophic failure of a piece of equipment due to combustion, chemical reaction or overpressurization.
A release of steam (from high energy lines or components) or an electrical component failure (caused by short circuits, grounding, arcing, etc.) should not automatically be considered an explosion.
Such events require a post-event inspection to determine if the attributes of an explosion are present. 43. FIRE -is combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute FIRES. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.
: 44. FISSION PRODUCT BARRIER THRESHOLD -A pre-determined, site-specific, observable threshold indicating the loss or potential loss of a fission product barrier. 45. FLOODING -A condition where water is entering a room or area faster than installed equipment is capable of removal, resulting in a rise of water level within the room or area. 46. 47. 48. 49. 50. 51. 52. FULLY FUNCTIONAL-all minimum required staff as defined in Table 6.1 and the positions designated by dashed lines in Figures 6.2, 6.3 and 6.4 are present. GENERAL EMERGENCY
-Events are in proces~ or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility.
Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area. HOSTAGE -is a person(s) held as leverage against the station to ensure that demands . will be met by the station. HOSTILE FORCE -one or more individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction.
HOSTILE ACTION-An act toward Susquehanna or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, projectiles, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
Hostile action should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on Susquehanna.
Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the OWNER CONTROLLED AREA). IMMINENT -The trajectory of events or conditions is such that an EAL will be met within a relatively short period of time regardless of mitigation or corrective actions. IMPEDE(D)
-Personnel access to a room or area is hindered to an extent that extraordinary measures are necessary to facilitate entry of personnel into the affected room/area (e.g., requiring use of protective measures such as temporary shielding, SCBAs or dose extensions beyond Emergency Plan RWP that are not routinely employed to access the room/area).
Page 5 of 11 
: 53. 54. 55. 56. 57. 58. Emergency Plan, Rev. 62, Page 12 of 295 INITIATING CONDITION (IC) -An event or condition that aligns with the definition of one of the four emergency classification levels by virtue of the potential or actual effects or consequences.
ISFSI -Independent Spent Fuel Storage Facility-A complex that is designed and constructed for the interim storage of spent nuclear fuel and other radioactive materials associated with spent fuel storage. JOINT INFORMATION CENTER-the designated location from which news releases, press conferences and other media interfacing can be provided.
LDE -Lens Dose Equivalent; the external exposure to the lens of the eye. LOWER FLAMMABILITY LIMIT (LFL} -The minimum concentration of a combustible substance that is capable of propagating a flame through a homogenous mixture of the combustible and a gaseous oxidizer.
LUZERNE COUNTY EMERGENCY MANAGEMENT AGENCY (LCEMA) -the h'ost county emergency response coordinating agency, responsible for implementing off-site action upon either direct notification from the Susquehanna SES or from PEMA. 59: MAINTAIN -Take appropriate action to hold the value of an identified parameter within specified limits.
* 60. MONTHLY -occurring within the calendar month. 61. NORMAL LEVELS -As applied to radiological IC/EALs, the highest reading in the past twenty-four h_purs excluding the current peak value.
* 62. NORMAL PLANT OPERATIONS
-activities at the plant site associated with routine testing, maintenance, or equipment operations, in accordance with normal operating or administrative procedures.
Entry into abnormal or emergency operating procedures, or deviation from normal security or radiological controls posture, is a departure from NORMAL PLANT OPERATIONS.
: 63. NOTIFICATION OF UNUSUAL EVENT-Events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.
No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. 64. NUCLEAR REGULATORY COMMISSION (NRC) -within the context of this plan, the Federal agency responsible for verifying that appropriate emergency plans have been implemented and for conducting investigative activities associated with a radiological emergency.
: 65. OPERATING BASIS EARTHQUAKE (OBE) -An earthquake which, considering the regional and local geology, and seismology and specific characteristics of local subsurface material, could reasonably be expected to affect the plant site during the operating life of the plant. It is that earthquake which produces the vibratory ground motion for which these features of the nuclear power plant necessary for continued operation without undue risk to the health and safety of the public are designed to remain functional.
Page 6 of 11 Emergency Plan, Rev. 62, Page 13 of 295 66. OFF-SITE -any area outside the Emergency Plan Boundary surrounding the Susquehanna SES. 67. OFF-SITE RADIOLOGICAL INCIDENT -any radiation incident affecting areas beyond the Emergency Plan boundary and posing a significant threat to public health and safety. 68. ON-SITE -the area within the PROTECTED AREA. 69. OPERATIONAL SUPPORT CENTER (OSC) -the primary on-site assembly area for operations support team personnel during the initial phase of an emergency.
The primary OSC is not in the control structure but is located in an administrative building.
In the event of a large radioactive release, the OSC may be relocated to the back-up OSC that is located in the control structure.
: 70. OWNER CONTROLLED AREA -includes the area within the expanded security perimeter, i.e. the areas that are bordered by the Vehicle Barrier System. The OWNER CONTROLLED AREA encompasses the Monitored OWNER CONTROLLED AREA (MOCA) as defined in Security-Procedures.
: 71. PENNSYLVANIA EMERGENCY MANAGEMENT AGENCY (PEMA) -within the context of this plan, the lead state-agency for radiological emergency planning, response and recovery and for providing guidance to local government for development of radiological emergency .plans and programs.
: 72. PLANT PROCEDURES
-those procedures utilized by the plant operations staff to control and manipulate the plant under both normal and abnormal circumstances.
: 73. PROTECTED AREA -An area encompassed by Physical Barriers and to which access is controlled.
: 74. PROJECTILE -A means of a fired, self-propelled object directed toward a Nuclear Power Plant that could cause concern for its continued operability, reliability, or personnel safety. 75. PROTECTIVE ACTION GUIDES (PAG) -the projected dose to reference personnel, or other defined individual, from an unplanned release of radioactive material at which a specific *protective action to reduce or avoid that dose is recommended.
: 76. PROTECTIVE ACTIONS -those emergency measures taken for the purpose of preventing or minimizing radiological exposures.
: 77. QUARTERLY
-occurring during the calendar quarter. 78. RADIATION DOSE -the quantity of radiation absorbed by the body or any portion of the body. 79. RADIATION MONITORING SYSTEM -an in-plant system consisting of ARMs, CAMs, and process monitors that contributes to personal protection, equipment monitoring, and accident assessment by measuring and recording radiation levels and concentrations at selected locations throughout the station. Reference Appendix D. 80. RADIOACTIVE MATERIAL-any solid, liquid, or gas which emits radiation spontaneously.
Page 7 of 11 Emergency Plan, Rev. 62, Page 14 of 295 81. RADIOLOGICAL EMERGENCY RESPONSE TEAM -the response team from the Department of Environmental Protection/Bureau of Radiation Protection, Department of Health, Pennsylvania Emergency Management Agency, and other State agencies, which will be dispatched to the scene of radiological emergencies.
The team provides technical guidance and other services to local governments or an affected nuclear facility.
: 82. RADIOLOGICALLY CONTROLLED AREA (RCA) -any temporary or permanent area established by Radiation Protection, which is controlled for purposes of protection from exposure to radiation or radioactive materials.
Typically, the Radiologically Controlled Area is defined by the outer perimeters of the Turbine, Reactor, and Radwaste Buildings, portions of the Control Structure, and portion$ of LLRWHF. 83. RCS INTACT -The RCS should be considered intact when the RCS pressure boundary is in its normal condition for the cold shutdown mode of operation (e.g., no freeze seals). 84. RADIOLOGICALLY CONTROLLED AREA EVACUATION
-evacuation of nonessential individuals from some or all of the Radiologically Controlled Area. 85. RECOVERY ACTIONS -those actions taken after the emergency to restore the plant as nearly as possible to its pre-emergency condition.
: 86. RECOVERY MANAGER -the individual responsible for the management of-emergency response activities in the EOF during an emergency at the Susquehanna Steam Electric Station. 87. REFUELING PATHWAY -The reactor refueling cavity, spent fuel pool and fuel transfer canal comprise the refueling pathway. 88. REM (Acronym for roentgen equivalent man) -a unit of measure of radiation dose in biological tissue. 89. REMOTE ASSEMBLY AREA -a designated area, outside the exclusion area, for the assembly of evacuated plant personnel, if necessary, during a Site Evacuation.
The Primary Remote Assembly Area is the Susquehanna Energy Information Center. The alternate assembly area is the West Building.
: 90. RESTORE -Take the appropriate action required to return the value of an identified parameter to the applicable limits. 91. ROUTE ALERTING TEAMS -a back-up to the siren system that is implemented, as necessary, in the event of siren failure or to alert persons or areas that may not be within the sound of the sirens. _Route alerting is a municipal responsibility and is accomplished by municipal route alert teams traveling in vehicles along preplanned routes delivering the following message: "There is an emergency at the Susquehanna Steam Electric Station; please tune to your Emergency Alert Station." 92. SOE -Shallow Dose Equivalent; external exposure of the skin or extremity which is measured at 0.007 cm in tissue. Page 8 of 11 Emergency Plan, Rev. 62, Page 15 of 295 93. SABOTAGE -is deliberate damage, mis-alignment, or mis-operation of plant equipment with the intent'to render the equipment inoperable.
Equipment found tampered with or damaged due to malicious mischief may NOT meet the definition of SABOTAGE until this determination is made by security supervision.
: 94. SAFE SHUTDOWN EARTHQUAKE (SSE) -An earthquake which is based upon an evaluation of the maximum earthquake potential considering the regional and local geology, and seismology and specific characteristics of local subsurface material.
It is that earthquake which produces the maximum vibratory ground motion for which Seismic Category I systems and components are designed to remain functional.
: 95. -SAFETY SYSTEM -A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related (as defined in 1 OCFR50.2):
* Those structures, systems and components that are reiied upon to remain functional during and following design basis events to assure: (1) The integrity of the reactor coolant pressure boundary;
-(2) The capability to shut down the reactor and maintain it in a safe shutdown condition; (3) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exp*osures:
: 96. SAFE SHUTDOWN SYSTEMS/EQUIPMENT
-consists of the following:
Diesel Generators, HPCI, Core Spray, Standby Gas Treatment System, RCiC, 4kV Safeguard Buses, ESW, ADS, RHR, RHRSW, Remote Shutdown Panels and DC Vital Buses'. 97. SECURITY CONDITION -Any Security Event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threat/risk to site personnel, or a potential degradation to the level of safety of the plant. A SECURITY CONDITION does not involve a HOSTILE ACTION. 98. SHIFT MANAGER -the individual who acts in the capacity of Susquehanna Steam Electric Station emergency manager immediately upon concurrence of an emergency as described in the SSES Emergency Plan. The designation Shift Manager is synonymous with the designation Shift Supervisor and may be used interchangeably iii the emergency plan. Both terms designate the same individual.
: 99. SIGNIFICANT TRANSIENT-is an UNPLANNED event involving one or more of the following:
(1) Reactor Re-circulation System runback involving a power reduction of over 25% thermal reactor power, (2) Reactor Recirc Pump Trip while >25% Reactor Power, (3) Reactor Scram, (4) ECCS Injection, or (5) thermal power oscillations
>10%. 100. SITE AREA EMERGENCY
-Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely faiiure of or; (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels that exceed EPA Protective Action Guideline exposure levels beyond the SITE BOUNDARY.
101. SITE BOUNDARY -that line, beyond which the land is not owned, leased or otherwise controlled by the licensee. (Susquehanna drawing C243786, Sh 1, "Site Facilities and Boundary Map.") Page 9 of 11 Emergency Plan, Rev. 62, Page 16 of 295 102. SITE EVACUATION
-evacuation of all non-essential personnel from the Exclusion Area. 103. STA TE -the Commonwealth of Pennsylvania.
104. STATION ACCOUNTABILITY AREAS-areas designated for the gathering of individuals for the purpose of personnel accountability.
Typically these are large areas with installed card readers to facilitate electronic accounting for personnel.
Specific locations are defined in station procedures.
105. SUSQUEHANNA NUCLEAR. LLC -subsidiary company of Talen Energy Corporation . that owns and operates Susquehanna Steam Electric Station. The Emergency Plan will refer to this company as Susquehanna.
* 106. TECHNICAL SUPPORT CENTER -a designated on-site location Where the conditions during and after an accident can be analyzed to provide technical and radiological assessments of the accident to the Emergency Director.
In the event of certain hazards preventing site access or certain security related events, personnel who normally report to the Technical Support Center may report to the Emergency Operations Facility where arrangements will be made to accommodate TSC-specific functions not assumed by the EOF. The alternate TSC will be activated as soon as possible to support the site; however, it is recognized that the *activation time for the alternate TSC may exceed 60 minutes.*
107. TEDE -Total Effective Do~e Equivalent; integrated doses consisting of the sum of external doses from plume shine, 50 year committed effective dose equivalent from
* inhalation (CEDE), and 4 day ground shine doses. 108. THYROID DOSE -radiation exposure to the thyroid resulting from an intake of radioactive materials.
109. TRANSMISSION POWER DISPATCHER-individual manning the transmission and distribution system for PPL Corporation.
110. UNISOLABLE -An open or breached system line that cannot be isolated, remotely or locally.
* The term UNISOLABLE also includes any decision by plant staff or procedure direction to not isolate a primary system.
* Normal leakage past a closed isolation valve is not considered UNISOLABLE leakage 111. UNPLANNED -A parameter change or an event that is not: 1) the result of an intended evolution, or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.
* Letter dated February 25, 2002 from Samuel J. Collins, Director, Office of Nuclear Reactor Regulations, to Robert G. Byram, Senior Vice President and Chief Nuclear Officer.
 
==Subject:==
Issuance of Order for Interim Safeguards and Security Compensatory Measures for -Susquehanna Steam Electric Station, Units 1 & 2. Page 10 of 11 Emergency Plan, Rev. 62, Page 17 of 295 112. VALID-an indication, report, or condition is considered to be VALID when it is verified by (1) an instrument channel check, or (2) indications on related redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicator's operability, the condition's existence, or the report's accuracy is removed. Implicit in this definition is the need for timely assessment.
113.
* VISIBLE DAMAGE -Damage to a component or structure that is readily observable without measurements, testing, or analysis.
The visual impact of the damage is sufficient to cause concern regarding the operability or reliability of the affected component or structure.
114. VITAL AREAS -is any area, normally within the PROTECTED AREA, which contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.
Plant VITAL AREAS include the following:
sec, Control Structure, Diesel Generator Buildings, ESSW Pump House, Spray Pond and Reactor Buildings.
115. WHOLE BODY EXPOSURE -direct radiation exposure to the body from external sources. Page 11 of 11 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 2.10 2.11 2.12 2.13 2.14 2.15 2.16 2.17 2.18 2.19 2.20 2.21 2.22 2.23 2.24 2.25 2.26 2.27 2.28 2.29 2.30 2.31 2.32 2.33 2.34 2.35 2.36 2.37 2.38 2.39 2.40 2.41 2.42 2.43 2.44 2.45 ANS-ARI-ARM-CAM-CEDE-CSAR CTN-DAC-DHS-FEMA DOE-EAL-ECCS-ED-EDE-EMA-EMC-EOC-EOF-EP-EPA-. EP-PS -EPZ-. ERO ETN-. FPC-LER-Page 1 of 2 Emergency Plan, Rev. 62, Page 18 of 295 2.0 A RONYM.S Alert Notification System Alternate Rod Insertion Area Radiation Monitors Continuous Air Monitors Central Alarm Station Columbia County Emergency Management Agency Committed Effective Dose Equivalent
* Control Room Control Room Emergency Outside Air Supply System Certified Safety Analysis Report Centrex Telephone Network Derived Air Concentration Document Control Services Department of Environmental Protection/Bureau of Radiological Protection Department of Homeland Security-Federal Emergency Management Agency U.S. Department of Energy Emergency Action Levels Emergency Alert System Emergency Core Cooling Systems Emergency Director at Susquehanna SES Effective Dose Equivalent Emergency Management Agency Emergency Management Coordinator (Municipality)
Emergency Operations Center Emergency Operations Facility Emergency Preparedness Environmental Protection Agency Emergency Plan Position Specific Procedures Emergency Planning Zone Emergency Response Data System Emergency Response Facility Emergency Response Organization for SSES Electronic Tandem Network Fuel Pool Cooling Federal Response Coordinator Federal Radiological Emergency Response Plan Federal Radiological Monitoring and Assessment Center Susquehanna SES Final Safety Analysis Report, Units 1 and 2 Federal Telecommunications System Health and Human Services High Pressure Coolant Injection System Joint Information Center Luzerne County Emergency Management Agency Limiting Condition for Operation License Event Report 2.46 2.47 2.48 2.49 2.50 2.51 2.52 .2.53 2.54 2.55 2.56 2.57 2.58 2.59 2.60 2.61 2.62 2.63 2.64 2.65 2.66 2.67 2.68 2.69 2.70 2.71 2.12* 2.73 2.74 2.75 2.76 2.77 2.78 2.79 2.80 2 . .81 2.82 2.83 2.84 2.85 2.86 2.87 2.88 2.89 2.90 LLRWHF -NSRB ODCM-.ORO . OSC-PICSY-PORC -PPL-PSP--RCA-RHR-RPS-RX-SAS-SDE-SDS-SSE-SSES Susquehanna TEDE-TR-TSC-UMC-VERMS Page 2 of 2 Emergency Plan, Rev. 62, Page 19 of 295 Low Level Radwaste Holding Facility Loss of Coolant Accident Monitored Owner Controlled Area Meteorological Information and Dose Assessment System Main Steam Isolation Valve Main Steam Line Nuclear Emergency Planning Nuclear Regulatory Commission National Response Plan Nuclear Safety Review Board Nuclear Steam Supply System Offsite Dose Calculation Manual Offsite Response Organization Operations Support Center Protective Actio*n Guides from *EPA Post Accident Sampling -System Pennsylvania Emergency Management Agency Plant Integrated Computer System, synonymous with Plant Process Computer (PPC) or R*TIME -Plant Operations Review Committee PPL Corporation Pennsylvania State Police Radiologically Controlled Area Reactor Core Isolation Cooling Remote Data Analysis System Residual Heat Removal Reactor Protection System Reactor Secondary Alarm Station Shallow Dose Equivalent Satellite Display System Susquehanna Energy Information Center Standby Gas Treatment System Standby Liquid Control Security Owner Controlled Area Safety Parameter Display System Safe Shutdown Earthquake Susquehanna Steam Electric Station Susquehanna Nuclear, LLC (subsidiary company of Talen Energy Corporation)
Total Effective Dose Equivalent Temperature Recorder Technical Support Center Unit Monitoring Console (PCS) Uninterruptible Power Supply United States Department of Agriculture Vent Effluent Radiation Monitoring System Emergency Plan, Rev. 62, Page 20 of 295 3.1 Columbia County Radiological Emergency Response Plan to Nuclear Power Plant Incidents.
3.2 DEP/BRP Emergency Plan -Bureau of Radiation Protection "Plan for Nuclear Power Generating Station Incidents".
3.3 NRC Generic Letter 91-14, "Emergency Telecommunications".
 
===3.4 Luzerne===
County Radiological Emergency Response Plan to Nuclear Power Plant Incidents.
 
===3.5 NUREG===
0654/FEMA-REP-1
-Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness In Support of Nuclear Power Plants. 3.6 NUREG 0696 -Final Report -Functional Criteria for Emergency Response Facilities.
3.7 NU REG 0737 -Clarification of TMI Action Plan Requirements.
 
===3.8 NUREG===
1392 -Emergency Response Data System Implementation.
3.9 PEMA Emergency Plan -Annex E to Commonwealth of Pennsylvania "Disaster Operations Plan", Nuclear Incidents (Fixed Facility).
3.1 O Susquehanna SES Emergency Plan Position Specific Procedures.
3.11 Susquehanna SES Letters of Agreement with off-site emergency organizations* (Appendix A). 3.12 Susquehanna Nuclear, LLC Security Plan. 3.13 Susquehanna SES Plant Procedures.
3.14 1 OCFR Part 50 -Domestic Licensing of Production and Utilization Facilities.
3.15 Design of the Siren Alerting System for the Susquehanna Steam Electric Station: Final Report. 3.16 SSES Preparedness, Prevention and Contingency Plan. 3.17 EPA 400-R-91-001
-Manual of Protective Action Guides and Protective Actions for Nuclear Incidents.
3.18 NEI 99-01 Revision 6, "Development of Emergency Action Levels for Non-Passive Reactors".
3.19 NRC Letter dated April 17, 1996, MOVING THE EOF TO THE NORTHEAST DIVISION HEADQUARTERS (TAC NOS. M91377 AND M91378), Docket Nos. 50-387/50-412.
Page 1 of 2 Emergency Plan, Rev. 62, Page 21 of 295 3.20 Letter dated February 25, ~002 from Samuel J. Collins, Director, Office of Nuclear Reactor Regulations, to Robert G. Byram, Senior Vice President and Chief Nuclear Officer.
 
==Subject:==
Issuance of Order for Interim Safeguards and Security Compensatory Measures for -Susquehanna Steam Electric Station, Units 1 & 2. 3.21 Susquehanna Nuclear, LLC Training and Qualification Plan. 3.22 Regulatory Guide 1.101 Emergency Planning and Preparedness for Nuclear Power Reactors (Revision 3, August 1992). 3.23 NRC Bulletin 2005-02 Emergency Preparedness and Response Actions for Security Based Events July 18, 2005. 3.24 Regulatory Issue Summary 2004-15, Supplement 1, Emergency Preparedness Issues: Post-9/11.
3.25 EC 690275/AR 850156, Extended Power Uprate (EPU) Impact Evaluation.
3.26 NEI 03-12, Template for Security Plan and Training and Qualification Plan, June 2004. Page 2 of 2 Emergency Plan, Rev. 62, Page 22 of 295 4~'.0 SCOPE AND C:ONTEl,ITS SSES includes two boiling water reactor electrical generating units. The station is located in Salem Township, Luzerne County, in east central Pennsylvania; about five miles northeast of Berwick, Pennsylvania (see Figure 4.1). This Emergency Plan applies to the operation of Unit 1 and Unit 2. 4.1 SCOPE This Plan provides guidance for both on-site and off-site emergency situations.
It ranges in scope from relatively minor events and occurrences involving small releases of radioactive material, up to and including a major nuclear emergency having significant off-site radiological consequences.
This Plan, together with the state, county, and municipal radiological emergency response plans, provides detailed guidance and direction for taking emergency measi.ires by the ERO to ensure the health and safety of the public living within the 10-mile EPZ of SSES. Additional guidance is provided in state and county plans for ingestion pathway preventive measures out to 50 miles (see Figure 4.2). Additional guidance on specific emergency actions for non-radiological releases of hazardous materials can be found in the SSES Preparedness, Prevention, and Contingency Plan.
* 4.2 CONTENTS 4.2.1 Classification 4.2.2 Page 1 of 2 This Plan provides for a graded response for distinct classifications of emergency conditions, action within those classifications, and criteria for escalation to another classification.
This classification system is also used by PEMA, DEP/BRP, LCEMA, and CCEMA. This system is covered in Section 5.0. Organization Control The Susquehanna organization for control of emergencies begins with the on-shift station personnel and contains provisions for augmentation and extension to include other station personnel, Talen corporate personnel, and outside emergency response organizations.
The total emergency program includes the support of state, federal and local emergency organizations.
Detailed provisions are made for implementing protective measures against direct radiation exposure for the public within a radius of at least ten miles from the SSES. Additional preventive measures may be taken beyond that distance to preclude ingestion pathway exposures.
Specific agreements are also made with local off-site support organizations to provide firefighting, medical, law enforcement, and traffic control services.
State, County, and Federal agencies have lead responsibilities specifically related to this Plan. Organizational control is covered in Section 6.0. 
 
====4.2.3 Emergency====
 
Plan, Rev. 62, Page 23 of 295 Emergency Measures The mechanisms through which this Plan provides for the proper response to emergency conditions at SSES include identification of the event, initial and ongoing assessment, and initial and ongoing emergency actions. Emergency actions include classification of event, completion of notifications, activation of onsite and offsite ERO, requests for offsite assistance, implementing onsite protective actions, recommending offsite protective actions, and activation of the restoration organization.
These mechanisms are discussed in Section 7.0. 4.2.4 Emergency Facilities 4.2.5 Page 2 of 2 Emergency facilities and equipment are provided to ensure the capabilities for prompt, efficient assessment and control of situations over the entire spectrum of probable and postulated emergency conditions.
The facilities and associated equipment and their emergency functions are described in Section 8.0. Emergency Traini~g A concept of in-depth preparedness is employed regarding the SSES emergency preparedness program. This concept is emphasized in the training program and in preparedness drills and exercises.
Personnel are trained to provide an in-depth response capability for required actions in an emergency situation.
Section 9.0 includes the means to achieve and maintain preparedness and to ensure maintenance of an effective emergency program.
Page 1 of 1 Emergency Plan, Rev. 62, Page 24 of 295 SSES' POPULATION CIRCLES pennsylvania , MER NC:Y,MANACEriEN AGEN,c:Y' Total Populatfon 1 o Miles; 52;ll12 Total f'.opulation 5 Miles'= 1_3,026 Total Population 2 Miles,= 998 .Population 5 to 10 Miles= 39;786 : .. Population 2 to*5 Miles= 12,028 :Total EPZ Population=
71,212* Population.Outside'1 OaMile * .But lnside'EPZ
= 18,400 -SUSQUEHANNA STEAM ELECTRIC STATION Units 1 and 2 EMERGENCY PLAN MAP OF SSES VICINITY Figure 4.1 Page 1 of 1 ..... POP ULAT I ONS: 1 0-Mile = 53.000 5 0-M i l e = 1 , 8 00 , 000 (a pp r o x.) PERRY CU B LAND Emergency Plan , Rev. 62 , Page 25 of 295 SSES EPZ and Ingestion Zone SULLIVAN Commooweotth of Pe n n~ylvania Pe n nsy1vonia Emerge n cy M a n:, gement Agency O eputate: P l a n n i no and Prepare d ness Bu r e au o f Stmtegtc ond Operational Planning www.pemo.stite.pa.u s SUSQUEHANNA STEAM ELECTRIC STATION Units 1 and 2 EMERGENCY PLAN MAP OF SSES 50 MILE INGESTION EXPOSURE ZONE F i gure 4.2 Emergency Plan, Rev. 62, Page 26 of 295 5.1 CLASSIFICATION SYSTEM Emergency conditions are grouped into four classifications that cover the entire spectrum of probable and postulated accidents.
These classifications are Notification of Unusual Event, Alert, Site Area Emergency, and General Emergency.
Action level criteria are specified for determining and declaring each emergency classification.
Planning is coordinated with State and county agencies to ensure that this classification system is compatible with the system used by those agencies.
The system provides for notification of appropriate emergency response organizations and for implementation of actions immediately applicable to a specific condition.
Provisions are included for upgrading the classification level and the corresponding response in the event of a change in the emergency condition.
Recognition and action level criteria are based on readily available information such as Control Room instrumentation.
Immediate actions for response to conditions involving plant operating parameters, such as Technical Specification Limiting Conditions for Operation (LCOs), are detailed in the Plant Procedures.
* The emergency classification system, initiating conditions, and EAL thresholds for each initiating condition are defined in Tables R, F, S, H, E and C. These tables demonstrates how an initiating condition leads directly to the appropriate emergency classification based on the magnitude of the event. In many cases, the proper classification is immediately apparent from in-plant instrumentation.
In other cases, more extensive assessment is necessary to determine the applicable emergency classification.
Continuing reassessment is required to ensure that the classification is consistent with the conditions.
The emergency actions that will be taken for each of the four emergency classifications are shown in Table 5.2. 5.1.1 Page 1 of 9 Notification of Unusual Event Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.
No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. Conditions that constitute a Notification of Unusual Event classification are outlined in Tables R, F, S, H, E and C. The ED declares a Notification of Unusual Event within 15 minutes of having information necessary to make a declaration.
Emergency Plan, Rev. 62, Page 27 of 295 The emergency actions that will be taken by Susquehanna and offsite agencies for an unusual event are listed in Table 5.2. In general the table states that the plant emergency management personnel and offsite agencies will be notified by plant staff if a Notification of Unusual Event is declared.
Plant staff will request assistance as necessary to disseminate information, make critical decisions and resolve the unusual event. 5.1.2 J\lert Events are in process or have occurred which involve an actual or potential substantial degradation of the level of .safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE fo.CTION:
fo.ny releases are expected to be limited to small fractions of the EPJ\ Protective fo.ction Guideline exposure levels. Conditions that constitute an J\lert classification are outlined in Tables R, F, S, Hand C. The ED or Recovery Manager declares an Alert within 15 minutes of having information necessary to make a declaration.*
The emergency actions that will be taken by Susquehanna and offsite agencies for an J\lert are listed in Table 5.2. In general the actions will be
* similar to a Notification of Unusual Event but will also include the dispatch ~f monitoring teams if a radioactive release is involved.
5.1.3 Site J\rea Emergency Page 2 of 9 Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE fo.CTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public. J\ny releases are not expected to result in exposure levels that exceed EPJ\ Protective J\ction Guideline exposure levels beyond the SITE BOUNDJ\RY.
Conditions that constitute a Site fo.rea Emergency are outlined in Tables R, F, S, H and C. The ED or Recovery Manager declares a Site fo.rea Emergency within 15 minutes of having information necessary to make a declaration.
The emergency actions taken by Susquehanna and offsite agencies for a Site fo.rea Emergency are listed in Table 5.2. In general, the actions will be similar to the actions taken for an J\lert with increased emphasis on information dissemination, more senior technical and management staff in the emergency response facilities, and additional field radiological monitoring.
Emergency Plan, Rev. 62, Page 28 of 295 5.1.4 General Emergency Events are in process or have occurred which involve actual or IMMINENT substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility.
Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area. Total activation of the onsite and offsite emergency organizations is required for such events. Actions involving offsite populations are probable.
Conditions that constitute a General Emergency are outlined in Tables R, F, S, H and C. The ED or Recovery Manager declares a General Emergency within 15 minutes of having information necessary to make a declaration.
The emergency actions taken by Susquehanna and offsite agencies for a General Emergency are listed in Table 5.2. In general the actions will be similar to the actions taken for a Site Area Emergency with additional resources dedicated to the health and safety of the general public. Additional actions include the initiation of predetermined protective actions for the public. -. 5.2 SPECTRUM OF POSTULATED ACCIDENTS The classification and corresponding protective actions relative to significant emergency conditions are based primarily on the resultant or potential radiation doses. Methods are described in this Plan and in EP Procedures for measuring, projecting and evaluating those doses. The discrete accidents addressed in this section are those which are defined in the SSES FSAR as "design basis accidents" resulting in off-site dose consequences and accidents involving the spent fuel storage facility (ISFSI). The following discussion of these postulated accidents and Tables R, F, S, H, E and C identify the instrumentation . and other mechanisms for prompt detection and continued assessment, and demonstrates how each accident is encompassed within the emergency classification system of this Plan. When an event also involves elevated off-site radiological consequences or other specific conditions, the event classification will be adjusted to reflect actual conditions.
 
====5.2.1 Control====
Rod Drop Accident Page 3 of 9 This accident is described in FSAR Section 15.4.9 and is postulated to occur with the reactor in hot startup condition, and very conservative calculations indicate failure of fuel rods. The main steam line radiation monitors dete~t the significant increase in activity and initiate an alarm to alert operations personnel.
Operations personnel would then validate the alarm condition, manually SCRAM the reactor and initiate closure of the main steam isolation valves (MSIV) and isolation of the main condenser.
During the MSIV closing time period, noble gases and radioiodines are transported with the steam to the condenser.
Release of radioactivity to the environment is by way of leakage from the turbine building. 
 
====5.2.2 Emergency====
 
Plan, Rev. 62, Page 29 of 295 Initial assessment of this accident, performed by the Control Room Personnel under the direction of the ED includes evaluation of radiation levels. Data a're direct radiation levels at the locations of various turbine building ARMs, and an indication of the airborne radioactivity concentration from the turbine building vent exhaust monitor. EP Procedures provide guidance for dose projections based on radiation readings.
Data from the Turbine Building vent exhaust monitors is supplemented by information obtained by the radiological monitoring team. The emergency actions include: a) Evaluate Emergency Action Levels per Tables R, F, S, Hand C b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation Fuel Handling This accident is described in FSAR Section 15.7.4 and is postulated to occur with the reactor in shutdown condition with the vessel head removed and results in fuel failure. The reactor building ventilation exhaust duct radiation monitoring system alarms, isolates the ventilation . system, and starts operation of the Standby Gas Treatment System (SGTS). Noble gases and radioiodines are released to the fuel pool, migrate to the secondary containment, and are released to the environment after filtration through the SGTS. Initial assessment of this accident includes the performance of dose projections in accordance with EP-PSs .. Dose projections utilize data from the reactor building vent monitor, standby gas treatment vent monitor, and meteorological instrumentation.
The emergency actions include: -a) Evaluate Emergency Action Levels per Tables R, F, S, Hand C b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation 5.2.3 Main Steam Line Break Page 4 of 9 This accident is described in FSAR Section 15.6.4 and is postulated to occur with the reactor in operating status. The steam line break occurs outside the containment ar,-id releases steam until complete closure of the MSIVs. Noble gases and radioiodines in the coolant are assumed to be released directly to the environment.
Emergency Plan, Rev. 62, Page 30 of 295 The initial assessment of this event includes the performance of dose projections.
An estimate of the resultant doses can be made and compared to those shown in Table 15.6-9 of the FSAR for worst case conditions.
Actual doses are proportional to the fission product activity in the steam, as monitored by the off-gas release rate, prior to the accident.
The doses in Table 15.6-9 of the FSAR are based on the assumption that the off-gas release rate is at the upper limiting condition for operation.
Actual dose estimates, and corresponding emergency actions, may be taken, based on the off-gas release rate prior to the accident.
Consideration may also be given to the relative benefit from taking or not taking specific protective action, based on the short-term duration of exposure associated with this accident.
The emergency actions include: a) Evaluate Emergency Action Levels per Tables R, F, S, Hand C b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation
 
====5.2.4 Instrument====
 
Line Break Page 5 of 9 This accident is described in the FSAR section 15.6.2 and is a circumferential rupture of an instrument line connected to the primary coolant system postulated to occur outside the primary containment but inside the secondary containment.
This failure results in the release of primary system coolant to the secondary containment, until the reactor is depressurized.
Operator recognition of the accident is by a combination of alarms or abnormal readings or by comparison of radiation, temperature, humidity, fluid and noise readings with several instruments monitoring the same process variable such as reactor level, jet pump flow, steam flow, and steam pressure.
Design Basis analysis shows that the event analyzed in Subsection 15.6.5 is bounding.
The following describes a realistic analysis of the event. The iodine concentration prior to the break is assumed to be 0.2 micro-curies/gram dose equivalent 1-131, which is the maximum equilibrium concentration for continued full-power operation permitted by the Technical Specifications.
All of the iodine activity in the steam from the flashed liquid and steam from the steam dome and 10 percent from the remainirm liquid released from the break are assumed to become airborne.
A plateout factor of 2 is assumed for airborne iodine inside secondary containment.
Although there will be some activation and corrosion products released the isotopes of primary importance are the iodine isotopes.
The emergency actions include: a) Evaluate Emergency Action Levels per Tables R, F, S, Hand C 5.2.5 5.2.6 Page 6 of 9 Emergency Plan, Rev. 62, Page 31 of 295 b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation Loss of Coolant Accident (LOCA) This accident is described in FSAR Section 15.6.5 and is postulated to involve a complete circumferential break of a recirculating loop pipe inside the primary containment, with the reactor operating at full power. The accident results in release of a significant quantity of fission products into the primary containment, leakage into the secondary containment, and release to the environment through the SGTS. Containment failure, although not likely, must be considered possible.
The occurrence of a design basis LOCA is uniquely identified by low-low reactor water level and high drywell pressure signals from the reactor protection system sensors and high radiation signal from the containment accident radiation monitor(s).
A reactor scram and MSIV closure occur. Operation of the emergency core cooling system is initiated.
The radiological exposures resulting from the activity released to the environment as a consequence of the LOCA have been determined for the realistic and design basis cases. The design basis and realistic LOCA doses are presented in FSAR Table 15.6-18. The radiological exposure of the-Control Room personnel for the design basis case is given in Table 15.6-21.
* The emergency actions include: a) Evaluate Emergency Action Levels per Tables R, F, S, Hand C
* b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation Off-Gas Treatment System Failure This accident is described in FSAR Section 15. 7 .1.1 and is postulated to be initiated by an occurrence such as earthquake (greater than design basis), explosion, or fire. The accident results in release of the stored . inventory of radionuclides in the system including that contained in the charcoal adsorption beds. In addition to recognition of the initiating event, the operator is provided with recognition and assessment information from alarmed instrumentation such as ARMs and vent radiation monitors.
The emergency actions i_nclude:
a) Evaluate Emergency Action Levels per Tables R, F, S, Hand C b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation Emergency Plan, Rev. 62, Page 32 of 295 5.2.7 Air Ejector Line Failure This accident is described in FSAR Section 15. 7 .1.3 and is postulated to result from a seismic event more serious than the system is designed to withstand.
The noble gas and radioiodine activity from the air ejector, which is normally processed by the off-gas treatment system, is discharged to the environment via the turbine building ventilation system. The accident is recognized by the off-gas system loss of flow indication and ARMs. Assessment of the severity includes evaluation of the off-gas activity release rate prior to the accident and results of on-site monitoring
.. The emergency actions include: a) Evaluate Emergency Action Levels per Tables R, F, S, Hand C b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation
 
====5.2.8 Liquid====
Radwaste Failure 5.2.9 Page 7 of 9 This accident is described in FSAR Section 15.7.3 and is postulated to be a rupture of the RWCU phase separator in the Radwaste enclosure.
Airborne radioactivity released during the accident passes directly to the environment via the turbine building vent. A.high water level alarm on the Radwaste building sump alarms and activates the sump pumps. Radwaste building ARMs and on-site monitoring provides data for assessing the magnitude of the radiological consequences.
The emergency actions include: a) Evaluate Emergency Action Levels per Tables R, F, S, Hand C b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation Recirculation Pump Seizure This accident is described in FSAR Section 15.3.3 and is postulated to result in the nearly instantaneous stoppage of the pump motor shaft of one of the recirculation pumps to occur with the reactor in operating status. As a result of the very rapid decrease in core flow in response to the large hydraulic resistance produced by the stopped pump impeller, a
* resulting level swell in the reactor may initiate a trip of the main and feedwater turbines, a scram due to stop valve closure, and a trip of the recirculation pumps.
5.2.10 Page 8 of 9 Emergency Plan, Rev. 62, Page 33 of 295 Fuel damage is not expected for the pump seizure accident for either two loop or single loop operation.
Any rods that experience boiling transition may be conservatively postulated to fail and potentially causing an Emergency Plan entry per th~ fuel cladding degradation Emergency Action Level. The radioactivity released from the fuel is transported into the steam line and is released to the environment via leakage from the condenser.
The occurrence of recirculation pump seizure is identified by the indication of recirculation flow loss and pump differential pressure in the control room. The emergency actions include: a) Evaluate Emergency Action Levels per Tables R, F, S, Hand C b) Declare the appropriate classification as warranted Feedwater Line Break -Outside Containment This accident is described iri FSAR Section 15.6.6 and is postulated to be an instantaneous, circumferential break of the largest feedwater line outside of containment.
The break releases coolant to the turbine
* building until the feedwater line check valves isolate the reactor from the feedwater system. The reactor will scram on low water level. At low-low water level, RCIC and HPCI initiate and maintain reactor water level above the low-low-low level trip point and eventually restore the reactor water level to its normal elevation.
There is no fuel damage as a result of this accident scenario.
Radioactivity will be released from the feedwater piping prior to isolation of the break location.
Activity concentrations are the same as those found in the main condenser hotwell. Activity release will occur through flashing and partitioning into the turbine building atmosphere, and then to the environment through the turbine building ventilation system. The estimated activity released to the environment for the worst case condition is shown in FSAR Table 15.6-25. Actual doses are proportional to the fission product activity in the coolant. Fission product activity can be determined from coolant grab samples or off-gas grab samples. Area Radiation Monitors, Main Steam Line Radiation Monitors, or Off-Gas radiation monitors may also indicate fission product activity.
The emergency actions include: a) Evaluate Emergency Action Levels per Tables R, F, S, H and C b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation.
5.2.11 NOTE: Page 9 of 9 Emergency Plan, Rev. 62, Page 34 of 295 Accidents Affecting Independent Spent Fuel Storage Installation as described in the CSAR The design basis accidents postulated to affect the Dry Fuel Storage System include:
* Reduced Horizontal Storage Module air inlet and outlet shielding
* Natural phenomena events as defined in the CSAR
* Accidental transfer cask drop with loss of neutron shield
* Lightning effects
* Debris blockage of Horizontal Storage Module air inlet and outlet opening
* Postulated Dry Cask Storage leakage
* Pressurization due to fuel cladding failure within the Dry Cask Storage The consequences of the postulated accidents are as specified in the CSAR. Impact of the postulated accidents would be detected by radiological monitoring during transport and storage of spent fuel. a) Evaluate Emergency Action Levels per Tables E, Rand H. b) Declaration of a Notification of Unusual Event as warranted.
c) Implement recovery actions. The following Emergency Action Level (EAL) Tables are excerpts from the EAL Basis Controlling Procedure and contain page number references after each EAL threshold for its corresponding basis section. Those page number references are not applicable within the Emergency Plan.
P age 1 of 1 Emergen c y Plan , Rev. 6 2 , Pa g e 35 of 2 9 5 TABLER-ABNORMAL RAD LEVELS/ RADIOLOGICAL EFFLUENT 1 ... -GloMou**->T-11-1-'GE'"IO'>lSm.
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____ w, ___ ~825.29 ~--l.*.s_ Susquehanna Nuclear, LLC CSl2.21 1.2.l.*.5..0 F<lrmEP-f!M-004-H Rev.1 , P a 901cl1 ALL CONOITIONS I I I Page 1 of 1 Emergency Pla n , Rev. 62 , Page 39 of 295 Susquehanna Nuclear , LLC ~'"*--~---... *----*----*--... -.. ____ ,._ ... __ '::::::""--
..... --.. --,-0----... ----ALL COND ITI ONS Page 1 of 1 E mergency Plan , R ev. 62, Pa ge 40 of 295 TABLE C-COLD SHUTDOWN/
REFUELING SYSTEM MALFUNCTIONS GENERAL EMERGENCY SITE AREA EMERGENCY UNUSUAL EVENT ======:J!pt..ll 1 R PV-C,t,NNOT buno:fl l<<odkr*lO-._, NO o l) CONT .... NMENTCI.OSUREo
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odo lo H GI AlLT-C-IOROo;mn'Alftlc--o lll2!ll N 01<11: Th&E~M MIOU ld dec lar&ltle....rn~upondelemuningtha t tim1lml: l 1ub&l:ne~.orlMll~ke1 V be&Yeffded Table C-1 Sumps & Tanks Table C-2 Containment Challenge lndk:allon s N obl I: WCONT IJ N M ENT ClOSURf ii -bbl>&d to e'lOffdirlg
'Ch& 30-minu!tlimtlll'lil.Clee la rationoltGer>era l Emerpancyrs NOT reqund. Nolll9: W lhtQOndtiof>lspeciliedw,thisEAllu t long&rthln1Sm,nu t H,CA1,2 *-Not. 10 In lht &bHnc.e or r&blM RCS t.rr,pe111tur&
lndiealion cal!S&d b)l lht lou. DI dta v h .. 1.--1 ca~bil'ty. ~lawlricalion .tlou ld be b H&don 1h* R:PV preu.ure increase eril&!ia 'M'Wl n 'Che RCS ii IN TACT in Mode, orbnad on ~me t g ooildat1,J,en in M.:>d&5 orlht RCS \i.NOTI N T ACTin M.:>d& , , CONTIJN M ENT Q.OSVR:E-Th& ~ty cltffl9<1 conditions or actionl tlk&n t o HCUntPrim1,Y 01 SecondlfYCo<ltlintMn l aMits1MOCll!8d WUCIU I H, *I'll...-..
~~""'n11unctio,, 1 l blllriertol......,praclic t releH&U n det""'-1tdov.fl
* Drywell equipment drain tank
* Drywell sumps
* Reactor Building sump
* LRW collection tanks
* Main condenser hotwell
* Suppression pool
* Visua l observation Table C-3 RCS Reheat Du ra tion Thresholds Table C...( Com m unication MethOds CONT,tJNI.EN T CLOSUREStalu s
* 11 1 n RCShu 1 ,-ITIO\lal,vstemisrloper>>orl\a.ithinthistjme l rame1nd RCS1&mp&r.1tur.isbei,ig relllced1h&EAL ii NOT applicable TableC-6 Max Sa k Reactor B uilding Rad iation limits .. il K II H$alO IINL ..... (II/WIii System Onsite ORO
* UHF Radio X
* Plant PA System X
* Dedicated Conference Lines X
* Commercial Telephone Systems X X
* Cellular Telephone X
* FTS-2001 (ENS) X T a ble C-7: AC 4.16 kV ESS buses Uni t 1:
* 1A201
* 1A202
* 1A203
* 1A204 Un it 2:
* 2A201
* 2A202
* 2A203
* 2A204 NRC X X X
* CONTAINMENT CLOSURE NOT established (Note6)
* PC hydrogen concentration
> 6%
* UNPLANNED rise in PC pressure
* Exceeding one or more Secondary Containment Control Max Sate Radiation Levels (EQ.0~104 Table 9)that can be read in the Control Room (Table C-6) Table C-5 Hazardous E vents
* Seism i c event (earthquake)
* I nterna l or external FLOODING event
* High 'Mnds or tornado strike
* F I RE
* EXPLOSION
* Other events 'Mth similar hazard characteristics as determ i ned by the Shift Manager I Susquehanna Nuclear , LLC F or mEP-RM.OCM.C:
Re v.~, Pa,g* 1 of 1 COL D CON DITI ONS Classification
: 1. Notification of Unusual Event Class Description Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.
No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of SAFETY SYSTEMS occurs. Purpose Purpose of offsite notification is to (1) assure that the first step in any response later found to be necessary has been carried out,. (2) bring the operating staff to a state of readiness, and (3) provide systematic handling of unusual events information and decision-making.
Emergency Plan, Rev. 62, Page 41 of 295 TABLE 5.2 EMERGENCY ACTIONS BASED ON CLASSIFICATION Licensee Actions 1. Promptly notify plant emergency management personnel of event particulars and an assessment of safety significance of the event. and 2. Notify PEMA, LCEMA, CCEMA and NRC of "Unusual Event". Under certain security-related events, such as a site-specific credible threat, the TSC and EOF will be activated at the Unusual Event level.* and 3. Closeout event with verbal summary to offsite authorities (PEMA, LCEMA, CCEMA, and NRC) followed by written summary if required by 10 CFR 50.73. or 4. Escalate to higher emergency classification if appropriate.
Page 1 of 7 Off-Site Agency Actions 1. Notify key officials and public if deemed necessary by county/state Emergency Director.
and 2. Provide assistance if requested and able.
* Letter dated February 25, 2002 from Samuel J. Collins, Director, Office of Nuclear Reactor Regulations, to Robert G. Byram, Senior Vice President and Chief Nuclear Officer:
 
==Subject:==
Issuance of Order for Interim Safeguards and Security Compensatory Measures for -Susquehanna Steam Electric Station, Units 1 & 2. Page 1 of 7 Emergency Plan, Rev. 62, Page 42 of 295 TABLE 5.2 EMERGENCY ACTIONS BASED ON CLASSIFICATION Page 2 of 7 Classification Licensee Actions Off-Site Aaencv Actions 2. Alert 1. Promptly notify state/local authorities a'nd 1. Provide assistance, if request~d and able. NRC of Alert status and reason for alert. Class Description and and Events are in process or have 2. Augment resources by activating EOC and occurred which involve an actual 2. Promptly notify Susquehanna emergency any other primary response centers. or potential substantial degradation management personnel of event particulars of the level of safety of the plant or and an assessment of the safety significance and a security event that involves of the event. probable life threatening risk to site 3. Alert to Standby status key emergency personnel or damage to site and personnel including monitoring teams and equipment because of HOSTILE associated communications.
ACTION. Any releases are 3. Activate TSC and OSC, and dispatch expected to be .limited to small monitoring team if radioactive effluent and fractions of the EPA Protective release involved.
Action Guideline exposure levels. 4. Prepare to provide confirmatory off-site and radiation monitoring and ingestion Purpose pathway dose projections if actual 4. Provide a dedicated individual for plant releases substantially exceed technical Purpose of offsite alert is to (1) status updates to offsite authorities and specification limits. assure that .emergency personnel periodic press briefings.
are readily available to respond if and situation becomes more serious or and to perform confirmatory radiation
: 5. Maintain alert status until verbal closeout.
monitoring if required; and (2) 5. Activate the Emergency Response Data provide offsite authorities current System (EROS) within one hour. or status information.
and 6. Escalate to a more severe class. Page 2 of 7 Emergency Plan, Rev. 62, Page 43 of 295 TABLE 5.2 EMERGENCY ACTIONS BASED ON CLASSIFICATION Page 3 of 7 Classification Licensee Actions Off-Site Agency Actions 2. Alert (continued)
: 6. Closeout or recommend reduction in emergency class by verbal summary to offsite authorities followed by written summary if required by 10 CFR 50.73. or 7. Escalate to a more severe emergency class. Page 3 of 7 Emergency Plan,. Rev. 62, Page 44 of 295 TABLE 5.2 EMERGENCY ACTIONS BASED ON CLASSIFICATION Page 4 of 7 Classification Licensee Actions Off-Site Agency Actions 3. Site Area Emergency
: 1. Promptly inform off-site authorities of site 1. Provide, if able, any assistance required.
emergency
*status and reason for emergency, if Class Description known. and Events are in .process or have and 2. Augment resources by activating primary occurred which involve actual or emergency response centers. likely major failures of plant 2. Augment resources by activating TSC, OSC functions needed for protection of and EOF and near-site/off-site monitoring and the public or HOSTILE ACTION that teams. results in intentional damage or 3. Assure that systems for public notification of malicious acts; (1) toward site and emergency status are in standby and initiate personnel or equipment that could preparation for subsequent public periodic lead to the likely failure of or; (2) that 3. Dispatch monitoring teams and associated updates. prevent effective access to communications for instances where radiation equipment needed for the protection releases appear imminent or have occurred.
and of the public. Any releases are not expected to result in exposure levels and 4. Alert to standby status other emergency that exceed EPA Protective Action personnel and dispatch personnel to duty Guideline exposure levels beyond 4. Provide a dedicated individual for plant status stations.
the site boundary.
updates to off-site authorities and periodic press briefings
.. and Purpose and 5. Provide off-site monitoring results to Purpose of the site area emergency licensee and others and jointly assess them. declaration is to (1) assure that 5. .Make senior technical and management staff in response centers are manned, (2) the EOF available for consultation with NRC and assure that monitoring teams are and state on a periodic basis. dispatched, (3) assure that personnel required for evacuation of and near-site areas are at duty stations if situation becomes more serious, (4) provide consultation with offsite authorities, and (5) provide updates for the public through offsite authorities.
Page 4 of 7 Emergency Plan, Rev. 62, Page 45 of 295 TABLE 5.2 EMERGENCY ACTIONS BASED ON CLASSIFICATION Page 5 of 7 Classification Licensee Actions Off-Site Agency Actions 3. Site Area Emergency (Continued)
: 6. Provide meteorological and dose estimates
: 6. Continuously assess information from to off-site authorities for actual releases via a licensee and off-site monitoring with dedicated individual or automated data regard to changes to protective actions transmission.
already initiated for public and mobilizing evacuation resources.
and and 7. Provide release and dose projections based on available plant condition information and 7. Recommend placing milk animals within foreseeable contingencies.
affected area radius on stored feed and assess need to extend distance.
and and 8. Close out or recommend reduction in emergency class by briefing of off-site 8. Provide press briefings.
authorities at EOF by phone followed by written summary if required by 10 CFR and 50.73. 9. Maintain site emergency status until close or out or reduction of emergency class. 9. Escalate to General Emergency class. or 10. Escalate to General Emergency class. Page 5 of 7 Emergency Plan, Rev. 62, Page 46 of 295 TABLE 5.2 EMERGENCY ACTIONS BASED ON CLASSIFICATION Page 6 of 7 Classification Licensee Actions Off-Site Agency Actions 4. General Emergency
: 1. Same as for "Site Area Emergency" 1. Provide requested assistance, if able. classification.
Class Description and and Events are in process or have 2. Recommend protective actions for 10-mile occurred which involve actual or 2. Make a Protective Action Recommendation EPZ population and 50 mile EPZ IMMINENT substantial core to the state based on an assessment of plant agricultural products.
degradation or melting with conditions and/or dose projections.
potential for loss of containment and integrity or HOSTILE ACTION that Note: The initial recommendations may be results in an actual loss of physical modified on the basis of subsequent plant 3. Dispatch key emergency personnel control of the facility.
Releases can status assessments or dose projections.
including monitoring teams and associated be reasonably expected to exceed communications.
EPA Protective Action Guideline exposure levels offsite for more and than the immediate site area. 4. Activate other emergency services Purpose personnel and dispatch to duty stations.
Purpose of the general emergency and declaration is to (1) initiate predetermined protective actions 5. Provide off-site monitoring results to for the public, (2) provide Susquehanna and jointly assess these. continuous assessment of information from licensee and and offsite organization measurements, (3) initiate additional measures as 6. Continuously assess information from indicated by actual or potential licensee and field-monitoring teams with releases, (4) provide consultation regard to changes to protective actions with offsite authorities and (5) already initiated for public and evacuation provide updates for the public resources.
through offsite authorities.
and Page 6 of 7 Emergency Plan, Rev. 62, Page 47 of 295 TABLE 5.2 EMERGENCY ACTIONS BASED ON CLASSIFICATION Page 7 of 7 Classification Licensee Actions Off-Site Agency Actions 4. General Emergency (Continued)
: 7. Maintain General Emergency status until closeout or reduction of emergency classification.
Page 7 of 7 Emergency Plan, Rev. 62, Page 48 of 295 IL .: II Susquehanna's Emergency Plan is based upon a four-phase approach to accident response and mitigation.
Phase I -Immediate Response (Reference Table 6.1.) Phase I consists of identification of the emergency condition, initiation of prompt corrective action and initiation of prompt notification to local, state and federal agencies as well as appropriate members of Susquehanna's ERO. This initial phase is implemented by the on-shift organization.
The-on-shift organization has been staffed and trained to be capable of both safely operating the units and quickly and effectively responding to an emergency condition.
Initially, the Shift Manager, the highest ranking management individual on-shift, will assume the role of Emergency Director and retain that role until relieved of that responsibility by the on-call Emergency Director.
The Shift Manager, as Emergency Director:
a) Classifies the condition.
b) Initiates corrective actions and coordinates emergency management activities.
c) Designates a communicator to notify off-site agencies and initiate call-in of selected personnel.
d) Ensures plant personnel are notified via the PA system or direct manual methods for accountability and/or evacuation, if required.
e) Notifies the on-call Emergency Director, informs him of the situation, and requests relief if appropriate.
For conditions under a Notification of .Unusual Event the Shift Manager may remain as ED through termination of the condition, due to probable short duration or low severity of the event. f) Ensures that on-site emergency response individuals and groups are notified, using the PA system or direct manual communications.
Depending on the nature and severity .of the condition, TSC, OSC and EOF staffing may be called out. Under certain security-related events, such as a site-specific credible threat, the TSC and EOF will be activated at the Notification of Unusual _Event level.* g) Ensures that initial dose projections are done and makes resulting recommendations regarding off-site protective actions, if required.
h) Ensures that off-duty station personnel are notified to assist as necessary with emergency activities.
These notifications are made, via the activation of ERO response pagers or by telephone backup, to individuals designated for off-duty availability status (i.e. on-call) to fill key emergency response positions.
Those key positions are identified in Sections 6.2 and 6.3. Other off-duty personnel are called in as required.
*
* Letter dated February 25, 2002 from Samuel J. Collins, Director, Office of Nuclear Reactor Regulations, to Robert G. Byram, Senior Vice President and Chief Nuclear Officer.
 
==Subject:==
Issuance of Order for Interim Safeguards and Security Compensatory Measures for -Susquehanna Steam Electric Station, Units 1 & 2. Page 1 of 19 Emergency Plan, Rev. 62, Page 49 of 295 Upon activation of Phase II, additional personnel are available, and control of the emergency and dissemination of in-plant teams shifts from the Control Room to the TSC. Ph.ase II -Activation of On-Site ERO -(Reference Table 6.1 and Figures 6.2 and 6.3.) Upon notification by the on-shift organization, the on-call Emergency Director reports to the site/Control Room to assume the role of Emergency Director.
As specified in Figures 6.2 and 6.3, the minimum number of support coordinators and staffs also report to the site. These individuals form the nucleus of the ED's Team and activate the TSC and OSC. The TSC and OSC are fully functional within 60 minutes of event classification (Alert or higher emergency declaration).
As the on-call Emergency Director and his support coordinators arrive, they are briefed and assume responsibility for their particular areas of expertise.
Emergency management activities, including communications, are under the control of the Emergency Director; dose projection and assessment activities are directed by the Radiation Protection Coordinator; technical expertise is directed by the Tech Support Coordinator; the Operations Coordinator oversees Operations activities; and the Damage Control Team Coordinator oversees in-plant damage control actions. The OSC Coordinator supports the operations and damage control team coordinators by managing personnel in the OSC (back up OSC in the event the OSC is not habitable).
The TSC takes over all emergency management and support activities from the on-shift organization, freeing them to devote their efforts towards establishing and maintaining the plant in a safe, stable condition.
The onsite ERO may be further augmented as shown .in Figures 6.2 and 6.3 by personnel filling TSC positions and OSC positions not designated as minimum requirements.
Figures 6.2 and 6.3 also designate minimum requirements for the TSC and OSC respectively.
In the event of hazards preventing site access or certain security related events, personnel who normally report to the Technical Support Center and Operations Support Center will report to the Alternate TSC and OSC at the Emergency Operations Facility.
OSC personnel can be sent to the site to mitigate site damage as soon as the site is secured. The alternate TSC will be activated as soon as possible to support the site; however, it is recognized that the activation time for the alternate TSC may exceed 60 minutes.
* Phase Ill -Activation of Off-site ERO -(Reference Table 6.1 and Figure 6.4.) This organization staffs the Emergency Operations Facility to provide management of the overall emergency response as well as technical support, off-site radiological assessment, and communications.
Staffing of the EOF occurs fallowing an Alert, a Site Area Emergency, or a General Emergency declaration.
The EOF is required to activate following a Site Area Emergency or General Emergency classification and take over management of the emergency from the TSC or Control Room within 90 minutes of the Site Area Emergency or higher classification.
Activation of the Emergency Operations Facility requires the minimum staff as identified in Figure 6.4. When the initial emergency classification is a Site Area Emergency or higher, the EOF will take over the management of the emergency within 90 minutes of the declaration of a Site Area Emergency.
Due to the site response during a daytime security event that starts at the SAE level, the EOF may not be staffed within 90 minutes. With an event in progress, station personnel may be directed to take cover and therefore be unable to respond to the EOF until cleared by plant security.
At the discretion of the Emergency Director, the EOF can be activated and take over management of the emergency earlier. * *
* Letter dated February 25, 2002 from Samuel J. Collins, Director, Office of Nuclear Reactor Regulations, to Robert G. Byram, Senior Vice President and Chief Nuclear Officer.
 
==Subject:==
Issuance of Order for Interim Safeguards and Security Compensatory Measures for-Susquehanna Steam Electric Station, Units 1 & 2. Page 2 of 19 Emergency Plan, Rev. 62, Page 50 of 295 Functional operation will include:
* Management of overall emergency response
* Coordination of radiological and environmental assessment
* Determination of recommended protective actions
* Communications
* Coordination of emergency response activities with Federal, State, local county and municipal agencies The offsite ERO may be further augmented as denoted in Figure 6.4 by personnel filling EOF positions not designated as minimum requirements.
Figure 6.4 designates minimum staffing.
Phase IV -Restoration
-This phase leads ultimately to the return to service of the unit. The organizational and philosophical concepts that are utilized during this phase are highly dependent upon the nature of the emergency.
The restoration phase does not begin until there is complete assurance that the plant is in a stable shutdown condition and that there is no inadvertent or unplanned significant release of radioactivity to the environment.
 
===6.1 NORMAL===
OPERATING ORGANIZATION FSAR Section 13.1.2 defines the normal operating organization for SSES as illustrated in FSAR Figure 13.1-3. Minimum shift response during off-hours is as follows: 1 Shift Manager (SRO) 1 Unit Supervisor (SRO) 3 Plant Control Operators (RO) 4 Non-Licensed Operators (NLO) 1 Shift Technical Advisor 2 Radiation Protection Technicians 1 Chemistry Technician 1 Emergency Plan Communicator (Proficient Licensed Operator (LO)) 1 NRC Communicator (Proficient SRO) Fire Brigade response personnel per Technical Requirements Manual Security Personnel as specified in the SSES Security Plan 15 Total Appendix K of the Emergency Plan contains a detailed on-shift staffing analysis that ensures the above on-shift staffing is adequate to take emergency actions to safely shut down the reactor, mitigate accident consequences, notify augmented ERO staff and OROs, determine PARs for site personnel and the public, perform firefighting, and provide medical assistance if needed for various emergency events and accidents until they are relieved by the augmented Emergency Response Organization (ERO). These provisions are required by 1 OCFR50 Appendix E section IV.A.9, delineated in NEI 10-05 and endorsed by NSIR/DPR-ISG-01.
* The on-shift staffing analysis shows that the prescribed set of events or accidents does not result in an emergency plan implementing duty being assigned to an on-shift position whose other mitigation duties could adversely impact performance of their emergency plan implementing duty. The minimum shift response during off-hours is also shown in the On Shift column on Table 6.1. Page 3 of 19 Emergency Plan, Rev. 62, Page 51 of 295 NOTE: On-shift staffing may be less than the minimum Emergency Plan requirement for a period of time not to exceed 2 hours in order to accommodate unexpected unavailability of on-duty shift individuals provided immediate action is taken to restore shift complement to within minimum requirements.
This note applies to personnel who are on-duty, not oncoming shift relief. 6.2 ON-SITE EMERGENCY ORGANIZATION-(PHASE II) Technical Specification 5.2, FSAR Section 13.1, and FSAR Section 17.2 define qualification requirements for Susquehanna Nuclear, LLC personnel.
Department implementing procedures define specific qualification and training requirements for Susquehanna ERO positions.
 
====6.2.1 Emergency====
 
Director (Table 6.1 60 Minute Response, Figure 6.2) The Shift Manager assumes the role of Emergency Director (ED) until he is relieved by a qualified Emergency Director or a qualified Recovery Manager (RM). Non-delegable duties (duties the ED cannot delegate except to another qualified ED or RM) are duties related to classification of emergencies, decision to notify state and local agencies, and Protective Action Recommendations.
The ED assumes full responsibility for the implementation and administration of the Emergency Plan and is responsible for assuring continuity of resources until those responsibilities are turned over to the Recovery Manager. The responsibility and authority of the ED are set* forth in Appendix E of this plari. The ED cannot relinquish any responsibilities until the arrival of and assumption of responsibilities by the Recovery Manager at the EOF. At that time, the ED may relinquish any responsibilities except those related to maintaining the Unit in a safe shutdown condition with adequate core cooling and no uncontrolled radioactive material releases.
If the Emergency Director cannot perform this function during the emergency, he will be succeeded by the Operations Coordinator until another qualified Emergency Director arrives to assume this responsibility.
Functional responsibilities of the ED include: a. Immediately upon notification of an existing or potential emergency, report to the Control Room and initiate assessment activities, including classification of the emergency and dose projections if appropriate.
: b. Manage overall implementation of the immediate on-site corrective and protective actions to bring the incident under control and mitigate its effects. Page 4 of 19 Page 5 of 19 Emergency Plan, Rev. 62, Page 52 of 295 c. Assure that appropriate notifications of emergency classification and protective action recommendations to state and local agencies are made within 15 minutes of declaration of an EAL. d. Assure that appropriate notifications and recommendations to the NRC are made immediately after notification to state and local agencies, but not later than one hour after declaration of an emergency classification.
: e. Augment the on-site ERO with duty roster personnel and other available station staff members as dictated by the emergency condition.
: f. Continue reassessment of emergency status and make appropriate recommendations including protective actions to off-site organizations.
: g. Ensure that information released is accurate and released through the proper channels.
: h. Activate Emergency Facilities described in Section 8.0, as required.
: i. Assign a technical liaison to the state EOC when requested.
: j. Communicate with and provide inform*ation to the Recovery Manager and the Public Information Manager. k. Authorize issuance of Radioprotective Drugs in accordance with -prescribed procedures.
This should include consultation with the Radiation Protection Coordinator and medical consultants.
I. Authorize Emergency dose extensions.
This should include consultation with the Radiation Protection Coordinator.
: m. Authorize taking essential corrective action that may involve the risk of emergency radiation exposure to ERO personnel.
Table 7.2 provides the basic criteria for this decision.
: n. Implement RCA and site evacuations as required.
: o. Request Federal assistance to augment ERO capabilities as necessary.
Such requests should be coordinated with PEMA and/or DEP/BRP and are normally done through the Recovery Manager and the EOF staff. p. Provide personnel and work schedules for relieving emergency per~onnel.
Emergency Plan, Rev. 62, Page 53 of 295 6.2.2 Operations Coordinator (Table 6.1 60 Minute Response, Figure 6.2) Responsibilities:
: a. Prepare the TSC for activation if the TSC ED has relieved the Control Room ED of responsibility.
: b. Advise the Shift Manager in directing the Control Room and in-plant operational activities.
: c. Direct activities of the Damage Control Team Coordinator, and TSC Communicator.
: d. Advise the ED on plant operations and conditions.
: e. Establish and set priorities for mitigation with the concurrence of the ED. f. Make recommendations to the Shift Manager for mitigation of the effects of Severe Accidents when Severe Accident Management (SAM) procedures are entered. 6.2.3 TSC NRC Communicator (Table 6.1 60 Minute Response, Figure 6.2) Responsibilities:
: a. Maintain communications with the NRC. b. Maintain records during the emergency.
I 6.2.4 TSC Emergency Plan Communicator (Table 6.1 60 Minute Response, Figure 6.2) 6.2.5 Page 6 of 19 a. Make proper notification to off-site organizations.
: b. Function as liaison for emergency-related communications between the ED and on-site and off-site emergency groups. c. Maintain records during the emergency.
Radiation Protection Coordinator (Table 6.1 60 Minute Response, Figure 6.2) Responsibilities:
: a. Ensures dose projections are performed and results are provided to the to the Dose Assessment Supervisor until relieved by the EOF. b. Provide radiological advice to the ED concerning on-site emergency activities.
: c. Provide protective action recommendations to the ED. d. Maintain communication with and provide information to the EOF Dose Assessment Supervisor.
6.2.6 Page 7 of 19 Emergency Plan, Rev. 62, Page 54 of 295 e. Maintain communication with and provide radiological information to DEP/BRP until relieved by the EOF. f. Provide on-site radiation monitoring personnel for effluent release assessment.
: g. Provide radiation monitoring personnel for emergency team efforts. h. Direct personnel and area contamination control and decontamination activities.
: i. Perform initial off-site environmental assessment until relieved by the EOF. j. Ensure radiological data is communicated to the NRC via the Health Physics Network. k. Advise the Emergency Director and organization on use of Kl and emergency dose extensions.
Technical Support Coordinator (Table 6.1 60 Minute Response, Figure 6.2) Responsibilities:
: a. Analyze mechanical, electrical, and instrument and control problems; determine alternate solutions, design and coordinate the installation of short-term modifications.
: b. Analyze thermo hydraulic and thermodynamic problems and develop solutions.
: c. Assist in the development of procedures necessary for conducting emergency operations and damage control. d. Analyze conditions and develop guidance for the ED and operations personnel.
: e. Resolve questions concerning Operating License requirements with NRC representatives.
: f. Maintain lead technical responsibility, coordinate technical information with the EOF as appropriate, and request technical support from the EOF or other engineering/technical resources.
: g. Maintain communication with and provide technical information to DEP/BRP Technical, as required, until relieved by the EOF. h. Provide core damage estimates.
: i. Until relieved, provide direction to Chemistry Technician to perform emergency plan actions. 
 
====6.2.7 Emergency====
 
Plan, Rev. 62, Page 55 of 295 Security Coordinator (Table 6.1 60 Minute Response, Figure 6.2) Responsibilities:
: a. Maintain plant security and institute appropriate contingency measures.
: b. Account for personnel as directed by EP-PS procedures.
: c. Act as liaison with outside groups in providing additional resources such as manpower, equipment, supplies, and transportation.
: d. Coordinate provisions for transportation, food, and other logistical support for emergency personnel.
6.2.8 OSC Coordinator (Table 6.1 60 Minute Response, Figures 6.2 & 6.3) Responsibilities:
6.2.9 6.2.10 Page 8 of 19 a. Report to the OSC. b. Organize, brief, dispatch, and direct, as necessary, the onsite
* damage control teams.
* c. Coordinate the availability and assignment of personnel supporting activities for the ED and other ERO managers.
: d. Organize and manage emergency response personnel in the OSC. e. Ensure communications with all in-plant teams is maintained.
Damage Control Team Coordinator (Table 6.1 60 Minute Response, Figure 6.2) Responsibilities:
: a. Participate in briefings with the TSC ED and helping to set priorities.
: b. Ensure damage control resources are allocated on the correct priorities by providing priorities to the OSC Coordinator and monitoring INDIA Team assignments.
: c. Communicate with Operations Coordinator, the Technical Support Coordinator, and the OSC Coordinator.
RP Specialist
-RAD Assessment Staff (Table 6.1 60 Minute Response, Figure 6.3) Responsibilities:
: a. Determine and maintari up-to-date status for radiological conditions in the plant. b. Assess on-site habitability.
6.2.11 6.2.12 6.2.13 6.2.14 Emergency Plan, Rev. 62, Page 56 of 295 c. Provide guidance and brief teams on radiological and ALARA considerations.
: d. Monitor in-plant team exposures. "A" Radiological Monitoring Team (Table 6.1 60 Minute Response, Figures 6.2 & 6.4) One team with two people who perform monitoring of areas around the plant as directed.
Engineering Staff (Core Thermal Hydraulic Engineer, Electrical Engineer, Mechanical Engineer) (Table 6.1 60 Minute Response, Figure 6.2) Responsibilities
: a. Provide core damage estimates. (Core Thermal Hydraulic Engineer)
: b. Analyze mechanical problems and other discipline related issues and determine solutions and provide support for implementation of required mechanical actions. (Mechanical Engineer)
: c. Analyze electrical and instrumentation and control problems and other discipline related issues. Determine alternate solutions and provide support for implementation of required electrical/l&C actions. (Electrical Engineer)
Non -Operations Support Personnel (Table 6.1 60 Minute Response, Figure 6.3) Four RP Technicians, One Chemistry Technician, One .Mechanical Maintenance worker and One (Electrical Maintenance worker or l&C Technician) provide support of accident assessment and repair/corrective actions. As designated, maintain radio communications with in-plant teams. One of the above RP Technicians may function as the RP Radio Communicator in the TSC to relieve the on-shift RP II Dose Calculator of that function if determined by the Radiation Protection Coordinator.
Non -Operations Support Personnel (Table 6.1 90 Minute Response, Figure 6.3) Four RP Technicians and One (Electrical Maintenance worker or l&C Technician) provide support of accident assessment and repair/corrective actions as directed by the OSC Coordinator.
If the position is not already filled, one of the above RP Technicians may function as the RP Radio Communicator in the TSC to relieve the on-shift RP II Dose Calculator of that function if determined by the Radiation Protection Coordinator.
All responders are notified to provide for full augmentation of resources at the TSC and OSC for the positions in Figures 6.2 and 6.3. The augmented response may be greater than 60 minutes and may occur after the TSC has activated.
Page 9 of 19 Emergency Plan, Rev. 62, Page 57 of 295 6.3 OFF-SITE RESOURCES AND ACTIVITIES (PHASE 111) Technical Specification 5.3, FSAR Section 13.1, and FSAR Section 17.2 define the qualification requirements for Susquehanna Nuclear, LLC personnel.
Department implementing procedures define specific qualification and training requirements for Susquehanna ERO positions.
Notification of the Recovery Manager is made via notification of key managers for the Notification of Unusual Event and via ERO activation for higher levels by the Communicators in the Control Room or TSC. An on-call duty roster is available in the Susquehanna Information Management System. At the discretion of the Emergency Director, the EOF can be manned or activated at a Notification of Unusual Event level. Staffing of the EOF occurs following an Alert, a Site Area Emergency, or a General Emergency declaration.
The EOF is required to activate following a Site Area Emergency or General Emergency classification for the purpose of taking over management of the emergency from the TSC or Control Room within 90 minutes of the Site Area Emergency or higher classification.
* When these responders are briefed on the emergency situation and verify that necessary equipment is functioning properly, the Recovery Manager will assume responsibility for overall management of the.emergency response.
The following functions are provided:
* Management of overall emergency re~ponse
* Coordination of radiological and environmental assessment
* Determination of recommended protective actions
* Communications
* Coordination of emergency response activities with Federal, State, local county and municipal agencies.
All responders are notified to provide for full augmentation of resources at the EOF for the positions in Figure 6.4. The augmented response may be greater than ninety minutes and may occur after th~.EOF has activated.
Page 10 of 19 6.3.1 Page 11 of 19 Emergency Plan, Rev. 62, Page 58 of 295 EOF Organization 6.3.1.1 Recovery Manager (Table 6.1 90 Minute Response, Figure 6.4) If the Recovery Manager cannot perform this function during the emergency, he will be succeeded by the Engineering Support Supervisor until another qualified Recovery Manager arrives. Non-delegable duties (duties the RM cannot delegate except to another qualified ED or RM) are duties related to classification of emergencies, decision to notify state and local agencies, and Protective Action Recommendations.
Responsibilities:
: a. Upon activation of the EOF, initiate assessment activities, including classification of the emergency and dose projections if appropriate.
: b. Provide continuous coordination and evaluation of Susquehanna activities during an emergency having or potentially having environmental consequences.
: c. Manage overall Susquehanna emergency response and assuring continuity of resources.
: d. Act as lead interface with off-site government agency officials.
: e. Assure appropriate notifications and recommendations to offsite organizations are timely.
* f. Continue reassessment of emergency status and make appropriate recommendations including protective actions to off-site organizations.
: g. Ensure that information released is accurate and made through proper channels.
: h. Direct the activities of all other EOF managers.
: i. Request Federal assistance to augment ERO capabilities as necessary.
Such requests should be coordinated with PEMA and/or DEP/BRP. j. Notify PEMA Emergency Operations Center of Protective Action Recommendations.
Page 12 of 19 Emergency Plan, Rev. 62, Page 59 of 295 k. When requested, send a representative to the State EOC. If conditions result in implementation of the Federal Radiological Emergency Response Plan, assign a representative to the Federal Response Center, to the Federal Radiological Monitoring and Assessment Center, and to the Joint Information Center (most likely the PIM). I. Authorize issuance of Radioprotective Drugs in accordance with prescribed procedures.
This should include consultation with the Dose Assessment Supervisor and medical consultants.
: m. If necessary, authorize Emergency dose extensions for monitoring field teams members under EOF command and control. This should include consultation with the Dose Assessment Supervisor.
6.3.1.2 Engineering Support Supervisor (Table 6.1 90 Minute Response, Figure 6.4) Responsibilities:
: a. Manage engineering support resources in the EOF. b. Provide technical support to aid in decision making process. c. Keep BRP informed concerning technical status of the plant and any mitigating actions being considered or in progress.
: d. Provide techniqal information concerning plant status and mitigating actions to the off-site agencies.
* 6.3.1.3 EOF Support Supervisor (Table 6.1 90 Minute Response, Figure 6.4) Responsibilities:
: a. Provide support to the Recovery Manager in review of plant data. b. Oversee formal communications leaving the EOF. c. Oversee proper facility set up. d. Provide administrative support. e. Support the Recovery Manager with off-site agency interface.
6.3.1.4 Dose Assessment Supervisor (Table 6.1 90 Minute Response, Figure 6.4) Responsibilities:
: a. Ensure dose projections are performed.
Page 13 of 19 Emergency Plan, Rev. 62, Page 60 of 295 b. Evaluate the magnitude and effects of actual or potential radioactive releases from the plant. c. Recommend appropriate off-site protective measures to the Recovery Manager. d. Recommend appropriate emergency classifications to the Recovery Manager. e. Communicate with the Radiation Protection Coordinator in the TSC and with DEP/BRP radiological personnel.
: f. Control field monitoring teams. g. Perform off-site environmental assessment.
: h. Advise the Recovery Manger and organization on use of Kl and emergency dose extensions, if necessary, for the monitoring field team members under EOF command and control. 6.3.1.5 Emergency Plan Communicator (Table 6.1 90 Minute Response, Figure 6.4) Responsibilities:
: a. Assume responsibility from the TSC for off-site notifications (except ENS communications).
: b. Transmit information about the emergency to off-site organizations.
: c. Function as liaison for questions received from other organizations.
: d. Maintain a record of emergency notifications.
*6.3.1.6 Radiological Support Staff (Dose Assessment Staffer, Field Team Director, "B" Radiological Monitoring Team) (Table 6.1 90 Minute Response, Figure 6.4) Responsibilities:
: a. Perform dose calculations, as required. (Dose Assessment Staffer) b. Monitor and control field teams. (Field Team Director)
: c. Perform monitoring of areas around the plant as directed.
(''B" Radiological Monitoring Team)
Emergency Plan, Rev. 62, Page 61 of 295 6.3.2 Joint Information Center 6.3.3 6.3.4 Page 14 of 19 The ED ensures that the JIC (Figure 6.4) is promptly notified and provided with available details of the emergency.
The JIC staff provides information regarding the emergency and items of public interest to municipal groups, initiates appropriate news releases, and responds to questions from the media officials.
After the Recovery Manager assumes control of the EOF, the Public Information Manager reports to the Recovery Manager. 6.3.2.1 Public Information Manager Responsibilities:
: a. Serve as official company spokesperson.
: b. Prepare and disseminate SSES information to the public via the news media. c. Interpret plant status information for the news media and other agencies.
: d. Arrange for_ news media conferences.
: e. Manage rumor control. f. Establish interfaces and coordinates news releases with the federal and state agencies in the JIC. Local Off-Site Support Services The Emergency Director, and the Recovery Manager as appropriate, ensures that appropriate off-site emergency support groups are contacted to provide the type and level of assistance that may be necessary to deal with the existing emergency condition.
Organizations that may be contacted for assistance during an emergency conditjon at SSES are listed in Appendix A, Letters of Agreement.
Methods available for contacting these support groups include direct telephone communications.
with individual organizations, use of the 911 telephone system for* emergency services, and message relay through LCEMA or CCEMA. Off-Site Support Services An emergency at SSES may require additional technical services and equipment.
This type of assistance may be obtained from the organizations listed in Table 6.2 and Appendix A. 
 
===6.4 Emergency===
 
Plan, Rev. 62, Page 62 of 295 COORDINATION WITH PARTICIPATING GOVERNMENT AGENCIES The ED and the RM ensure that off-site authorities are notified and apprised of emergency events at SSES when their respective facilities are managing the emergency.
Notification of a NOUE (Notification of Unusual Event) is primarily to ensure that the authorities are cognizant of the details of events that may arouse public concern and initiate inquiries by news media or members of the public. 6.4.1 County Agencies LCEMA and CCEMA provide for:
* Planning and coordination with municipal, State, and Federal authorities.
* Initial response to notification by SSES.
* Alert and warning of local populations within the 1 O mile EPZ.
* Evacuation and other protective measures for local populations within the 10 mile EPZ.
* Emergency services.
* Situation analysis.
* Operation of county EOC. LCEMA and CCEMA also provide direction for the local organizations that are assigned action or support responsibilities under_their plans. The primary method of notification to LCEMA and CCEMA is via the Centrex Telephone Network (CTN). Secondary methods are radio and regular telephone.
 
====6.4.2 State====
Agencies PEMA provides for:
* Issuance of planning guidance.
* Coordination of State response to nuclear incidents.
* Coordination of multi-county Emergency Response Planning.
* Operation of PEMA EOC.
* Provision for emergency public information.
* C.oordination of State agencies and departments.
Page 15 of 19 Emergency Plan, Rev. 62, Page 63 of 295 DEP/BRP provides for: * . Technical consultation on Radiological and Plant conditions.*
* Accident assessment.
* Recommendations for protective actions.
* Recommendations for protection of potable water and food.
* Recommendations for recovery and re-entry (off-site).
* Operation of DEP/BRP EOG. Initially, SSES notifies PEMA, who, in turn, notifies DEP/BRP. DEP/BRP calls back to SSES to obtain radiological and plant condition information and establish.a communication link with SSES. If the emergency warrants, DEP/BRP responds to the EOF. The primary method of notification to PEMA is via the Centrex Telephone Network (CTN). CTN communications between SSES and DEP/BRP are used for transmitting radiological and technical information/recommendations.
6.4.3 Page 16 of 19 Federal Agencies As detailed in the Federal Radiological Emergency Response Plan (FRERP), the Federal government maintains extensive capabilities to assist states and licensees in responding to radiological emergencies.
The ED and, upon EOF activation, the RM are authorized to request Federal assistance.
Such requests should be coordinated with PEMA and/or DEP/BRP. NRG -designated Lead Federal Agency (LFA) under the National Response Plan (NRP). The primary method of notification to the NRG is via the Emergency Notification System (ENS). Upon notification of an emergency classification, the NRG will enter one of several response modes based on the severity of the event. Response modes include: Normal (Increased Regional Monitoring)
Monitoring Activation Expanded Activation In the Normal and Monitoring modes, NRG site presence is provided by the Resident Inspectors who typically observe activity in the Control Room and TSC. Upon Activation, a site team will be dispatched that can arrive at the site within several hours. Response assignments are primarily at the EOF, with a few individuals located at the JIG, TSC, Control Room and OSC. If conditions warrant, the NRG can go to Expanded Activation that has a much larger response to staff shift type operations and additional team support personnel.
DOE -provides radiological monitoring and assessment assistance.
Page 17 of 19 Emergency Plan, Rev. 62, Page 64 of 295 The primary method of notification to DOE is by telephone, although assistance is typically requested through the Lead Federal Agency (NRC) or through the State (DEP/BRP).
Initial DOE response is by a Radiological Assistance Program (RAP) team dispatched from the DOE Brookhaven Area Office. This team can arrive within eight hours and would operate primarily out of the EOF. If the situation necessitates additional technical assistance, DOE can set
* up and staff a Federal Radiological Monitoring and Assessment Center (FRMAC) in the vicinity of SSES. A FRMAC, which draws DOE resources and personnel from its Nevada Operations Office, can be operational within about 24 hours. The location of such a center would be selected based on actual radiological deposition patterns.
The Federal FRMAC team is initially managed by DOE, with personnel also*provided by NRC, EPA, USDA, HHS, and other agencies.
The State and Susquehanna would assign personnel to the FRMAC to coordinate monitoring activity.
OHS -FEMA -responsible for coordinating all Non-technical Federal response.
If the emergency situation has warranted implementation of the National Response Plan (NRP}, DHS-FEMA will set up and staff a Federal Response Center in the vicinity of SSES. The location of such a center would be selected based on current needs and conditions.
Access to all Federal non-technical assistance is through the Federal Response Center where representatives of participating agencies are based. Other Federal Agencies In addition to NRC, DOE, and DHS-FEMA, other Federal agencies are available to provide assistance under the National Response Plan (NRP). The extent of participation depends on the nature and magnitude of the event. A full listing of these agencies and description of their missions is
* found in the National Response Plan (NRP). Additional information on available resources can be found in NUREG-1442/
:FEMA-REP-17, "Post-Emergency Response Resources Guide." Joint Information Center (JIC) The National Response Plan (NRP) provides for each participating agency to be represented at a Joint Information Center, along with the State and the facility licensee.
For Susquehanna SES, it is expected that these parties will agree to utilize Susquehanna's JIC to fulfill this on-scene Joint Information Center role. Resources Available to Support Federal Response A Lodging and Food Service -Lodging and food service for personnel operating from the FRMAC, Federal Response Center, and JIC are available from local commercial resources in the Wilkes-Barre, Hazleton, and Bloomsburg areas.
Emergency Plan, Rev. 62, Page 65 of 295 B. Communications
-Capability provided by DOE and DHS-FEMA, supplemented by standard telephone service to be established when facilities are selected, are adequate for the FRMAC and Federal Response Center. C. Security -Security arrangements for the FRMAC and Federal Response Center can be made by the DOE and DHS-FEMA, respectively, with local resources.
D. Transportation
-Federal response personnel will provide their own transportation by renting commercially available vehicles.
E. Airport -Wilkes-Barre/Scranton International Airport, Avoca, Pennsylvania.
6.5
* RESTORATION The Susquehanna ERO continues to provide appropriate emergency response functions until such time as the emergency has been terminated or the Talen Corporate Leadership Council (CLC) has approved the implementation of a long-range restoration organization.
Termination from an emergency condition is through joint evaluation by -the organizations involved.
In the case of a severe emergency involving off-site consequences, this would include the Recovery Manager, DEP/BRP, and NRC. The Senior Vice President and Chief Nuclear Officer requests that the Talen Corporate Leadership Council establish a restoration organization when the following guidelines have been met:
* In-plant systems are stable, adequate core cooling established and contingency systems and plans available.
* In-plant radiation levels a.re stable or are decreasing with time.
* Releases of radioactive material to the e*nvironment are under control or have ceased.
* Any fire, flooding or similar emergency conditions are under control or have ceased. Although planning for restoration varies according to the emergency, a long-term restoration organization that is general in nature has been defined. The restoration organization is a project-type organization with their major activities conducted from the EOF. This organization is depicted in Figure 6.6 and major responsibilities are defined below.
* Restoration Manager -A designated officer or senior manager from Susquehanna to manage SSES restoration operations.
* Plant Operations Manager -A designated manager from Susquehanna qualified to control plant operations including security.
* Technical Support Manager-A designated manager from Susquehanna qualified to manage a technical group.
* Radiological Manager -A designated manager qualified to manage the radioactive waste and radiological control aspects. Page 18 of 19 Emergency Plan, Rev. 62, Page 66 of 295
* Maintenance Manager -A designated manager qualified to coordinate the activities of Susquehanna, NSSS supplier, and construction forces on proposed plant modifications or other construction support.
* Advisory Support Function -Advisory support consists of senior representatives of the NSSS supplier, the NRC, and special consultants.
* Scheduling/Planning Manager -A designated manager to coordinate plans an.d schedules for the Restoration Manager.
* Administration and Logistics Manager -A designated manager who is responsible for providing administrative, logistic, communications and personnel support.
* Public Information Manager -A designated manager qualified to manage public relations activities.
During restoration operations, the radiation exposure limits of 1 OCFR20 apply. Compliance with those limits is the responsibility of the Restoration Manager via the applicableRadiation Protection organization.
At the time of declaring that an emergency has entered the restoration phase, the Restoration Manager is responsible for providing notification to all applicable agencies.
Restoration actions that plan for, or may result in, radio.active release are evaluated by the Restoration Manager as far in advance of the event as is possible.
Such events and data are reported to the appropriate off-site emergency response organizaUons and agencies prior to initiating release. Page 19 of 19 Table 6.1 Emergency Plan, Rev. 62, Page 67 of 295 STATION EMERGENCY PLAN MINIMUM STAFFING REQUIREMENTS (Note A) Caoabilitv for Additions Maior Functional Area Major Tasks Position Title or Exoertise On Shift SO min 90min Plant Operations and Shift Manager (SRO) 1 ----Assessment of Operational Unit Supervisor (SRO) .1 (Note B) ----Aspects Plant Control Operators (RO) 3 (Note C) ----Non-Licensed Operators (NLO) 4 ----Emergency Direction and Control Emergency Director (Note D) 1 --(Emergency Director)
Notification/Communication Notify licensee, State, Local, and Emergency Plan Federal personnel
& maintain Communicator 1 (Note E) 1 1 communication EOF Support Supervisor
---1 NRC communicator 1 (Note F) 1 --Radiological Accident Emergency Operations Facility Recovery Manager ----1 Assessment and Support of _(EOF} Director---------------------------
--------------------------------------
-------------------
----------------
----------------
Operational Accident Radiation Protection
& Dose Radiation Protection Assessment Assessment Coordinator
--1 --Dose Assessment Supervisor
---1 Rad Assessment Staff -___ 1(Note I)_ __ ___ 2 (Note J) ___ ---------------------------------------------
--------------------------------------
-------------------
Offsite Surveys (Field Teams) Radiological Monitoring Team --2 (Note K) 2 (Note L) Personnel
--------------------------------------
-------------------
----------------
_Onsite [out-of-plantJRP_TechJl
________ . 1 _ Survey Team Personnel
________ 1 -------------------
----------------
----------------
Radiation Protection
& Dose Assessment:
RP Technicians 2 3 3 a. Access Control b. RP coverage for repair, corrective actions, search and rescue, first aid, & firefighting C. Personnel Monitoring
: d. Dosimetry
: e. Dose Assessment
: f. In-Plant Surveys Chemistrv/Radiochemistrv Chemistry Technicians 1 1 --Page 1 of 3 Maior Functional Area Plant System Engineering Repair and Corrective Actions Firefighting Rescue Operations and First Aid Site Access Control and Personnel Accountability Page 2 of 3 Table 6.1 Emergency Plan, Rev. 62, Page 68 of 295 STATION EMERGENCY PLAN MINIMUM STAFFING REQUIREMENTS Major Tasks Technical Support Management of Damage Control Teams ---------------------------------------------
Repair and Corrective Actions (onshift requirements may be fulfilled by NLOs) Firefighting communications
--Security, personnel accountability Position Title or Exoertise On Shift Shift Technical Advisor 1 Operations Coordinator
--Core/Thermal Hydraulics Engr. --Electrical Engr. --Mechanical Engr --Technical Support Coordinator
--Eni::iineerinq Support Supervisor
--Damage Control Team Coordinator
--OSC Coordinator
-------------------------------------------
-------------------
Mechanical Maintenance/ (Note G) Rad Waste Operator (Note G) Electrical Maintenance/
Instrument and Control Technician
-Fire Brigade per Technical Requirements Manual -(Note H) Security Personnel All per Security plan Security Coordinator
--15 Plus Fire Brigade and Security Plan Required Personnel (Note A) Capabili1' for Additions 60 min 90 min --*--1 --1 --1 --1 --1 ----1 1 --1 ---------------
-----------------
1 --1 1 Local Support Local Support 1 --22 14 Table 6.1 Emergency Plan, Rev. 62, Page 69 of 295 STATION EMERGENCY PLAN MINIMUM STAFFING REQUIREMENTS Notes for Table 6.1 Note A The Capability for Additions column refers to reporting times. Reporting location may be the OSC, TSC or EOF. Note B As a result of having a common control room, the Unit Supervisor can be shared between the two units. See Appendix K for staffing assignments during various events or accidents.
Note C One PCO will be assigned to each unit. See Appendix K for staffing assignments during various events or accidents.
Note D The role of Emergency Director is fulfilled by the Shift Manager position.
See Appendix K for staffing analysis.
Note E The Emergency Plan Communicator position is a proficient Licensed Operator (LO). See Appendix K for staffing analysis.
Note F The NRC Communicator position is a proficient Senior Reactor Operator (SRO). See Appendix K for staffing analysis.
Note G Fulfilled by one of the NLO's on-shift to provide initial damage control repair activities until additional support arrives. Such activities include racking breakers, changing fuses manipulating valves, moving equipment, and starting equipment locally. Note H
* Minimum of two individual's on-shift with the capability of performing Rescue Operations/First Aid and* is a collateral duty of Fire Brigade and Security personnel.
See Appendix K for staffing analysis.
I. Note I RP Specialist in the OSC. Note J Dose Assessment Staffer and Field Team Director in the EOF. Note K "A" Radiological Monitoring Team personnel (see Figure 6.2 and 6.4)-One team with two people who are 60 minute responders that which are then dispatched from the vicinity of the plant within 60 minutes. Team is then turned over from the TSC to the EOF. This team is not required for TSC activation but is required for EOF activation.
Note L "B" Radiological Monitoring Team personnel (see Figure 6.4) -One team with two people who are 90 minute responders that are dispatched from the EOF. This team is not required for EOF activation unless the "A" team is unavailable, in which case it will be used for EOF activation.
Page 3 of 3 Emergency Plan, Rev. 62, Page 70 of 295 TABL'E' 6.2 ' ~f *: ',*Iii A'Do1~n_ ONlAL ASSISTANCE.
FROM OUTSIDE SU'SQUEHANNA
*NUCLE'.A'R
_ LlC ---------------------------' Name/Address Availabili Hours 1. Committed Resources
* General Electric Engineering advise and analysis for N/A GE Facilities NSSS equipment Operations and Maintenance 48 EOF expertise on NSSS equipment
* INPO Operations and Maintenance On call 24 hrs. a day INPO HQ in Atlanta Atlanta, GA expertise Dissemination of information N/A INPO HQ in Atlanta
* Other Nuclear Utility 4 EOF Support NOTE: Information necessary to contact appropriate vendors in case of an emergency is maintained in the Emergency Telephone Instructions and Directory.
Page 1 of 1 Emergency Plan, Rev. 62, Page 71 of 295 TSC ORGANIZATION
.-----------------
* I : EMERGENCY
: I DIRECTOR*
: I I ---------------~ .------------: Operations
: .------------: Security : Admin Staff r-Rad Pror-: : Coordinator*:
"-----1------*
_______ ] _______ . Shift Manager Susquehanna Steam Electric Station Units 1 and 2 Emergency Plan TSC ORGANIZATION FIGURE 6.2 I I : Emergency Plan : : Communicator*
: I I ~------]*-----*
--------------* I I : NRC : : Communicator*
: I I L***************
: Coordinator*:
: Coordinator*:
L*************
L****** -----* *------------*
I "A" Rad I I I I ---------------, I I . : Damage Control : --I Monitoring 1---r Team Coard.* : I L****** ******** .-------------l--------------
*osc C d' t **: I Tech Support : 1 oor ma or
* 1 Coordinator*
* L**************
L ****** ******' --. I -------------
: Core Thermal r I --* t i------------
--. : Electrical Engineer : L ******* *******' :---M;;h;~rc;i-
--:
* Engineer : L **************
Engineering Support I Team (2) I *------------
HPN Communicator TSC Dose Calculator
_j Additi ------. onal i Rad Staff : I I L-----------
I ,-------------------------------------------------------------*
t '2~~e:riaJ~~
TlnJrri~T
!~S~ire_fllE:_nJ~
Ln_ ~C~&#xa3;>~dJLJ!:~
:::iltb
_6.; l !o! _6.fl:~T~te_r~~~<?_n_s~J
-----Individuals may be located in the OSC, TSC, or Field.
* Designates positions required for TSC activation.
** Located in the OSC. See Figure 6.3 Note: Rad Monitoring Team (2) refers to 1 team with 2 people. Page 1 of 5 Emergency Plan, Rev. 62, Page 72 of 295 OSC ORGANIZATION
------------*
-------------
Non-Ogerations Suggort Personnel Four RP Technicians One Electrical Maintenance or l&C Technician Report @ 90 minutes
* Designates positions required for OSC activation.
~---------------------.
I I : osc : : COORDINATOR
* : I I I I -----------
----------*
:r'1ori-!fgera1iaiis
~uQ120 *I I :Four RP Technicians cian *One Chemistry Techni :one Mechanical Maint enance ance or l&C :one Electrical Mainten :i-echnician
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;ii; ji~1; ]3: i to1 &sect;Q~~i;~; 1iip:0!1;;.J
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1 I : Designates minimum requirements in accordance with Table 6.1 for 90-minute response.
: I : L--**************************************************************
Page 2 of 5 ,. ----. l. --------, RP Specialist
: :(Rad Assessment Staff)* -----------------*
Chemistry Coordinator Susquehanna Steam Electric Station Units 1 and 2 Emergency Plan OSC ORGANIZATION FIGURE6.3 Emergency Plan, Rev. 62, Page 73 of 295 r-;N-GiNEERTNG-1 1 SUPPORT 1 1 SUPERVISOR' 1 !. **********
! ENGINEERING SUPPORT EOF ORGANIZATION
~---~;SE ___ i I I 1 ASSESSMENT I 1 SUPERVISOR' 1 !. **********
! .----------------------, I RECOVERY MANAGER* l 1* I ~----------
----------~
TECHNICAL ADVISOR .--------------
------------
* I
* EOF SUPPORT * : SUPERVISOR'
: I I ------------
:--E~;;c;E*Ncv
* *:
* DOSE ASSESSMENT
: : STAFFER' : *(RAD Assessment Staff)1 LIAISON SUPPORT SUPERVISOR 1 PLAN : 1 COMMUNICATOR'*
*-----------*
L*************'
I I 1 FIELD TEAM DIRECTOR':
1 (RAD Assessment Staff) 1 I I
,-----------.
I 'A"RAD I 1 MONITORING
: : TEAM (2)* : *-----------
*---,;:;;D---i I MONITORING 1 1 TEAM (2)** : !.-----------
ENVIRONMENTAL SAMPLING TEAM ADDITIONAL RAD STAFF OFFSITE AGENCY LIAISONS NEP DUTY PLANNER ADMIN. STAFF SECURITY .---------------------------------------------------------------
!. Q~!liSU'!.t~!l rnJUiT_urn_
i:e.milr~rzi~~~
Ju !1!:~!2~11c..e_
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.!3 .. 1-f.or JQ _l'Qi~~~ _r~!lP.,O_nJ~:.:
* Designates positions required for EOF activation.
PUBLIC INFORMATION MANAGER PUBLIC OFFICIALS CONTACTS ADMIN. STAFF TECHNICAL BRIEFERS NEWS MANAGER Susquehanna Steam Electric Station Units 1 and 2 Emergency Plan ** Not required for activation unless "A" team unavailable.
NOTE: RAD Monitoring Team (2) refers to 1 Team with 2 people. .----------------------------------------------------------------.
EOF ORGANIZATION FIGURE 6.4 : Designates minumum requirements in accordance with Table 6.1 for 60 minute response.
l I I Page 3 of 5 PUBLIC INFORMATION MANAGER ADVISORY SCHEDULING/
SUPPORT PLANNING FUNCTIONS MANAGER Page 4 of 5 CORPORATE HEADQUARTERS
' RESTORATION MANAGER TECHNICAL PLANT SUPPORT OPERATIONS MANAGER MANAGER Emergency Plan, Rev. 62, Page 74 of 295 ADMIN/ LOGISTICS MANAGER RADIOLOGICAL MAINTENANCE MANAGER Susquehanna Steam Electric Station Units 1 and 2 Emergency Plan LONG TERM RESTORATION ORGANIZATION FIGURE 6.6 MANAGER Emergency Plan, Rev. 62, Page 75 of 295 COMMUNICATION INTERFACES WITH OFF-SITE AGENCIES .............
... ......... . . ........ .... ... ......... . n ENS. Control Roa NRC Communicat TSC NRC Communicator NRC Liaison Support Supervisor*
* Responsible for Interface with Agencies located in EOF Page 5 of 5 HPN TSC HPN Communicator I CTN Emergency
-Director( PAR) Recovery Manager -PAR) n CTN. PEMA DEP/BRP Tech Support Coordinator Engineering Support Supervisor ontrol Room ergency Plan ommunicator TSC Emergency Plan Communicator EOF Communicator
.............................
I LCEMA l CTN Rad Protection Coordinator DASU/Liaison Support Supervisor I CCEMA -Susquehanna Steam Electric Station Units 1 and 2 Emergency Plan COMMUNICATION INTERFACES WITH OFF-SITE AGENCIES FIGURE 6.7 Emergency Plan, Rev. 62, Page 76 of 295 7 .1 ASSESSMENT ACTIONS FOR ALL EMERGENCY CLASSIFICATIONS Provisions are made for assessment through the course of an emergency to ensure effective coordination, direction and upgrading of emergency activities in a timely manner. The assessment actions ate described in detail in Emergency Plan Position Specific Instructions (EP-PSs).
Continuous assessment of the status of plant systems and radiological conditions is provided by plant instrumentation and is supplemented by routine surveillance functions.
The occurrence of an Unusual Event is recognized by instrument alarms or indications, surveillance results, or other observation of an off-normal condition by an individual at the station.
* Assessment actions are described below. For a Notification of Unusual Event, one or more of the actions listed below will be initiated; for higher emergency classifications, actions are continued, intensified, and increased in frequency.
Table 7.1 provides a Summary of Notification
& Response Actions outlined in Section 7.1.
* Perform surveillance of in-plant instrumentation.
* Initial and continued observation of off-normal conditions.
* . Obtain assistance from off-duty personnel and/or off-site support groups ..
* Deploy on-site damage control team$.
* Perform reactor coolant sampling and analysis.
* Depioy field radiological monitoring teams to perform direct .radiation measurements and air sampling.
* Perform do$e calculation activities.
Correlate with field team data.*
* Perform sampling and analysis of environmental media. 7.1.1 Page 1 of 9 Off-Site Dose Calculations The Emergency Director is responsible for initiating off-site dose calculation and assessment activities.
These activities are performed by Radiation Protection trained personnel who report to the Technical Support Center (TSC) (or the Control Room for all initial entries into the Emergency Plan). Data from the vent effluent monitors and the meteorological towers serve as inputs for the off-site dose calculation methods. The ED is responsible for calling in* personnel to the TSC to perform off-site dose assessment activities.
The Radiation Protection Coordinator reports to the TSC within 60 minutes of notification.
Page 2 of 9 Emergency Plan, Rev. 62, Page 77 of 295 Field monitoring teams are directed to selected monitoring location(s) by either the Radiation Protection Coordinator, Dose Assessment Supervisor, Dose Assessment Staffer, or Field Team Director via radio and/or phone communication.
The results of the teams' surveys are used to update projected doses and dose calculational assumptions.
The initial field monitoring team is staffed within 60 minutes and is dispatched from the vicinity of the plant within 60 minutes. An additional field monitoring team is staffed within 90 minutes and dispatched from the EOF. See Table 6.1 and Figures 6.2 and 6.4. Each radiological monitoring team is supplied with a survey meter and low volume air sampler. TLDs are located at 17 sites around the station to provide early information on accumulated off-site doses. Two sets of TLDs are provided at each of these sites; one set for dose accumulation during the period of releases and one set maintained for the normal monitoring period or exchanged early at the Dose Assessment Supervisor's discretion to meet information needs.
* The ED and Recovery Manager recommend appropriate protective actions to PEMA Operations Center, Harrisb~irg, based upon the results of the off-site dose *assessment activities.
7 .1.1.1 Meteorology The SSES on-site meteorological measurement system is based upon an on-site primary meteorologicai tower located to the east southeast of the station.
The primary tower provides measurements of wind speed, wind direction, and wind direction variability at its 1 O and 60-meter levels, temperature differential between the 1 O and 60-meter levels, and ambient temperature and dew point at the 10-meter level. Precipitation is measured .at ground level. In case of primary tower faiiure, a 10-meter on-site backup meteorological tower will provide measurements of wind speed, wind direction, and wind direction variability.
The meteorological systems are instrumented to provide continuous data to*the control room and the Plant Integrated Computer System (PICSY) for utilization in the TSC and EOF. Data that enters PICSY is viewable through various display formats and is also transmitted to ttie NRG via EROS. Digital dataloggers are present at all of the SSES meteorological towers. All data is stored locally and is available for acquisition by interrogation across telephone lines. Primary and backup tower strip chart recorders are located in the control room. Site specific, meteorological information for emergency dose assessment purposes can also be obtained by contacting either a meteorologist or the National Weather Service Station using the phone numbers provided in the SSES Emergency Telephone Directory.
Page 3 of 9 Emergency Plan, Rev. 62, Page 78 of 295 7.1.1.2 Radiation Protection Considerations In the event of an unplanned radioactive release from either the reactor building vents, the turbine building vents, or the standby gas treatment vent; continuous gross noble gas readings are available from the vent monitors.
Each monitor is also equipped with in-line iodine and particulate sampling capability.
These in-line samples are periodically removed and analyzed in order to provide iodine and particulate release rate information.
Event declarations are based on Noble Gas readings or iodine and particulate sample results. The following Radiation Protection considerations are taken into account: selection of the accident type to closely approximate the isotopic mix and average gamma energies of the release occurring, radioactive decay from time of reactor shutdown, plume decay-in-transit and iodine and particulate depletion due to precipitation.
7.1.1.3 Dose Calculations for Airborne Releases A dose calculation model is used to make current, site specific estimates and predictions of atmospheric effluent transport and diffusion during and immediately following an accidental airborne radioactivity release. The purpose of the prediction is to provide an input to the assessment of the consequences of accidental radioactive releases to the atmosphere and to aid in the implementation of emergency response decisions.
Page 4 of 9 Emergency Plan, Rev. 62, Page 79 of 295 The dose calculation model used is a fast running, time-dependent, variable trajectory plume segment "B" model with the following capabilities:
NOTE: A class "B" model is a numerical model that represents the actual spatial an.d temporal variations of plume distribution.
* Computes atmospheric dispersion at the site based on atmospheric stability as a function of site specific terrain conditions with 15-minute upgrades of source term and meteorological conditions.
*
* Provides estimates of deposition and relative concentration of radioactivity within the plume exposure and ingestion EPZs for the duration of the release.
* Incorporated in the calculations is wet and dry deposition which enables dose estimates from three pathways -plume, ground shine, and ingestion
.. The dose program complies with the "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," (EPA-400), .adopting the dose calculation methodology in ICRP #26/30: The accident dose assessments are based on the adult physiology per EPA 400, except for one case-that is, child thyroid dose conversion factors are used in calculating thyroid COE. However adult physiology is used in calculating thyroid COE for purposes of evaluating the neeq for a sheltering only PAR when evaluating controlled venting of containment.
Calculations of TEDE are made using the (adult) dose factors provided in EPA-400. The following calculational options are available:
* TEDE (Total Effective Dose Equivalent) integrated doses consisting of the sum of external doses from plume shine, 50 year committed effective dose equivalent from inhalation (CEDE), and 4 day ground shine doses.
* EDE and COE dose rates for field team management.
* Fifty year thyroid committed dose (COE), from inhalation of
* radioactive materials.
* Population dose (person rem) out to 50 miles.
* Summary print of projected doses for each of four projection times.
* Integrated ground dose for projected times specified by the user. The dose calculation program is a standalone program running on PCs located in the TSC and EOF.
Emergency Plan, Rev. 62, Page 80 of 295 7.1.1.4 Liquid Release Calculations Estimates of downstream river water concentrations are made by employing effluent sample analysis or discharge monitor data, discharge flow rates and river elevation readings.
The river elevation is used to estimate the travel time to the point of interest.
The calculated degree of mixing, together with the discharge monitor data and the discharge flow rates are used to calculate downstream concentrations.
 
===7.2 CORRECTIVE===
 
ACTIONS 7.3 Detailed operating procedures and plant procedures are utilized by the plant operating personnel to assist them in recognizing emergency events and taking the corrective actions necessary to place the plant in a safe condition.
Table 6.1 shows personnel available to respond to an emergency.
Additionally, EP-PSs describe subsequent and supplemental corrective actions for the scope of potential situations within each of the emergency classifications.
These procedures are designed to guide the actions of the personnel to correct or mitigate the condition as early and as near to the source of the problem as feasible.
Some essential corrective actions may involve the risk of emergency exposure to ERO personnel.
Such actions could involve preventing the release of large quantities of radioactive material, reducing damage to major equipment or lifesaving actions. Table 7&deg;.2 specifies the limits for emergency exposure and other relevant criteria to be considered.
The ED is responsible for all corrective actions taken to mitigate the consequences of the accident on-site. PROTECTIVE ACTIONS Protective actions are implemented to prevent or mitigate consequences to individuals during or after a radiological incident.
Protective action recommendations within the SSES Exclusion Area and Site Boundary are the responsibility of the ED, but may include assistance by the EC>F. Protective actions outside the Site Boundary are primarily the responsibility of State and local emergency organizations, but may include coordination of activities, dissemination of appropriate data, and recommendations by the ED or Recovery Manager. Effective integration of SSES procedures and implementation plans with State and local implementation plans ensure that all members of the public, including those located on Susquehanna property but outside the emergency plan boundary, will be notified of protective actions to be taken and that the actions can be implernented in a timely manner. Protective action recommendations are outlined in Table 7.3. 7.3.1 On-Site Protective Actions The primary protective measure for on-site personnel in an emergency is prompt evacuation from areas that may be affected by significant radiation, contamination, or airborne radioactivity.
Respiratory protective equipment and clothing are provided at the plant and in the various emergency equipment kits for personnel who may be required to perform emergency activities.
Page 5 of 9 Page 6 of 9 Emergency Plan, Rev. 62, Page 81 of 295 Control of in-plant contamination is in accordance with SSES Radiation Protection procedures.
In the event of radioactive contamination outside fenced security areas, but within the exclusion area, access to such areas is controlled by Susquehanna with assistance from the PSP. 7 .3.1.1 Local Area Evacuation This category refers to evacuation from one area to another area within the same building.
The initiation of a Local Area Evacuation results from ARM or CAM alarm(s) sounding in the same area within a building or from observed conditions such as smoke or toxic gas, which may indicate a possible habitability problem. The initial response for individuals is to evacuate to an unaffected area of the building, notify the plant Control Room of the conditions, and await further instruction.
The ED assesses the situation, activates appropriate procedures to rectify the condition and informs the personnel when to return to their respective work area via the PA system or direct manual communication.
7.3.1.2 Radiologically Controlled Area Evacuation The initiation of a Radiologically Controlled Area Evacuation results from ARM, CAM, or other applicable monitor alarms, (i.e., fire alarms). Notification for personnel to proceed with a Radiologically Controlled Area Evacuation is announced over . the plant PA system. If all or part of the PA system is unavailable then alternate manual methods may be used to notify personnel of the need for evacuation and/or accountability.
The initial mandatory response by individuals is evacuation to an unaffected area. In this case, however, the nearest such area may not be in the same building, and multiple ARM, CAM, or fire alarms are probable.
* The decision to implement a Radiologically Controlled Area Evacuation*
is the responsibility of the ED. Factors to be considered include the apparent levels of radiation and/or airborne radioactivity involved and the exposure to personnel that would result from evacuating to Accountability Areas.
Emergency Plan, Rev. 62, Page 82 of 295 7 .3.1.3 Security and Accountability Accountability of on-site personnel during an emergency is accomplished through the use of the physical security system and station procedures.
The physical security system clearly establishes who is within the protected area. Personnel are notified to report to accountability areas during an emergency via an alert signal transmitted over the PA ~ystem. If all or part of the PA system is unavailable then alternate manual methods may be used to notify personnel of the need for evacuation and/or accountability.
The names of the personnel reporting in are compared to those logged through the security system in order to ensure total accountability.
If not completed earlier, accountability will be initiated immediately after declaration of a Site Area Emergency and will be completed within 30 minutes of the declaration of a Site Area Emergency.
For certain security-related events, an evacuation of non-essential personnel may be conducted prior to performing accountability.
Security will collect badges upon egress from the site and then perform. accountability.*
7 .3.1.4 Site Evacuation A Site Evacuation requires that all *individuals on-site, except for Control Room operations personnel and others with specific emergency assignments, leave the site. If the ED requires off-site assembly,-personnel will go to the Remote Assembly Area. The Primary Remote Assembly Area is the Susquehanna Energy Information Center (NE Sector), as shown in Figure 8.1. The altern~te Remote Assembly Area is the West Building (WSW Sector). Assembly area leaders will coordinate accountability at Remote Assembly Areas. Implementation of a Site Evacuation is the responsibility of the ED. That deQision is based on the severity of the incident, the likelihood of escalation, and the radiation and airborne radioactivity levels throughout the station. Notification is made via the PA system. If all or part of the PA system is unavailable then alternate manual methods may be used to notify personnel of the need for evacuation and/or accountability.
Accountability is accomplished in passage through the security gate. Personnel and vehicle contamination surveys are performed at the Remote Assembly Area_. using portable survey instruments.
For certain events such as some security events, on-site personnel may be directed to remain in place due to personal safety concerns until a more appropriate time for accountability and evacuation.
Station procedures specify those security*contingencies.
*
* Letter dated February 25, 2002 from Samuel J. Collins, Director, Office of Nuclear Reactor Regulations, to Robert G. Byram, Senior Vice President and Chief Nuclear Officer.
 
==Subject:==
Issuance of Order for Interim Safeguards and Security Compensatory Measures for -Susquehanna Steam Electric Station, Units 1 & 2.' Page 7 of 9 Emergency Plan, Rev. 62, Page 83 of 295 7.3.2 Off-Site Protective Actions Page 8 of 9 The responsibility for actions to protect off-site individuals rests with the Commonwealth of Pennsylvania.
DEP/BRP is responsible for evaluating information obtained from SSES and other sources and recommending appropriate off-site protective actions to PEMA. Such recommendations include: * * *
* Shelter for affected populations Evacuation of affected populations Administration of thyroid prophylaxis Control of contaminated agricultural products The principal off-site local coordinating agency is LCEMA. Since the area and population inside the ten-mile EPZ are partially within Columbia County, parallel emergency response functions are provided by CCEMA. Upon notification by PEMA of a situation that may require protective actions for off-site populations, LCEMA and CCEMA initiate appropriate actions. If PEMA has lost communication or is otherwise unavailable, it is possible that the ED or Recovery Manager may contact LCEMA and
* CC EMA directly with protective action recommendations.
If time permits, LCEMA and CCEMA obtain a review and verification by PEMA of recommendations made by the ED or Recovery Manager. LCEMA and CCEMA protective actions include: * *
* Prompt alerting of the population within ten miles of the SSES through the use of the Alert Notification System (described in Section 8.0) and Route Alerting Teams, a supplement to the siren system that is implemented, as necessary, in the event of siren failure or to alert persons or areas that may not be within the sound of the sirens. Route alerting is a municipal responsibility and is accomplished by municipal route alert teams traveling in vehicle~ along preplanned routes delivering the following message: "There is an emergency at the Susquehanna Steam Electric Station; please tune to your Emergency Alert Station."
* Transmission of specific instructions to potentially affected populations via the Emergency Alert System. Assistance for evacuation of the population within the ten-mile EPZ. Appendix G includes the estimated times to evacuate all or segments of the population from the 10-mile EPZ, jdentifies potential problem areas and provides contingencies for dealing with adverse conditions.
It was utilized in the development of detailed evacuation plans by PEMA, LCEMA, and CCEMA.
Emergency Plan, Rev. 62, Page 84 of 295 7.4 AID TO AFFECTED PERSONNEL
 
====7.4.1 Emergency====
 
Exposure All reasonable measures are taken to maintain the radiation exposure of emergency personnel who provide rescue, first aid, decontamination, ambulance, firefighting, law enforcement or medical treatment services within applicable limits specified in Table 7.2. "Guidance on Dose Limits for Workers Performing Emergency Services".
Table 7.2 summarizes the emergency exposure criteria for entry or re-entry into areas for purposes of undertaking protective or corrective actions. Actions taken to provide the support activities listed above are considered commensurate with the activities listed in Tale 7.2. Methods and conditions for permitting volunteers to receive emergency radiation exposures are described in EP-PS procedures, and provide for expeditious decisions with consideration to known and reasonable balance of associated risks. 7.4.2 Decontamination and First Aid 7.4.3 Page 9 of 9 Personnel contamination in emergency situations is controlled to the extent feasible by the normal methods of using protective clothing and surveying for contamination following the removal of such clothing.
Personnel decontamination areas are available in-plant and decontamination efforts involving significant amounts of contamination are performed under the direction of Radiation Protection personnel.
At least two persons who are qualified in first aid methods are on-site at all times. First aid to injured personnel can be performed in conjunction with any necessary decontamination methods. However, if immediate treatment of the injury is vital, that treatment takes precedence over decontamination.
This philosophy also extends to off-site emergency assistance involving radioactive contamination.
For that purpose, measures are established to ensure timely off-site medical treatment.
Medical Transportation and Treatment Arrangements and agreements have been made for the transportation and treatment of patients from SSES, who may have injuries complicated with radioactive contamination or who may have been involved in a radiation incident.
Emergency Plan, Rev. 62, Page 85 of 295 CODE: Notification of Unusual Event Alert = 1 2 3 4 Site Area Emergency General Emergency
= = = II*-----*-*-*
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---.. ------**-----------------------*---"-----------' -.. r.A~tE_J!.:r.
------~-------------------. ------___ _.;_: _______ *--------*-*
 
==SUMMARY==
OF IMMEDIATE NOTIFICATION AND RESPONSE FOR ALL CLASSIFICATIONS ON SITE IMMEDIATE NOTIFICATIONS Fire Brigade (1-4) Damage Control Team (1-4) First Aid/Rescue Team (1-4) Security Force (1-4) Dose Assessment Personnel (1-4) Field Monitoring Teams (1-4) All Other Station Personnel (1-4) ACTIONS Fight Fire (1-4) Repairs (1-4) Rescue (1-4) First Aid (1-4) Security Measures (1-4) Personnel Evacuation (1-4) Dose Calculations (1-4) Dose Assessment (1-4) Field Monitoring (1-4) Augment Shift Resources/Activate TSC (2,3,4) Augment Resources/Activate Offsite ERO (2,3,4)* Personnel Evacuation (as aooropriate)
(3,4) OFFSITE IMMEDIATE NOTIFICATIONS Fire Units (1-4) Rescue Assistance (1-4) Ambulance (1-4) Hospital (1-4) PSP (1-4) Talen Headquarters (1-4) Talen Headquarters(1-4)
Site personnel designated as off-site response (2,3,4)* ACTIONS Fight Fire (1-4) Rescue (1-4) Transport (1-4) Treatment (1-4) Assist Security (1-4) Confirmatory Calculations (2-4) Maintain Communications (2-4) Field Monitoring and Continuous Evaluation of Dose Projections (2-4). Alert Key Personnel (1) Activate and Staff Offsite ERO (2,3,4) Recommend Offsite Action (4) TSC and EOF (or alternate TSC) will be activated for certain security events such as a site-specific credible security threat. Letter dated February 25, 2002 from Samuel J. Collins, Director, Office of Nuclear Reactor Regulations, to Robert G. Byram, Senior Vice President and Chief Nuclear Officer.
 
==Subject:==
Issuance of Order for Interim Safeguards anc! Security Compensatory Measures for-Susquehanna Steam Electric Station, Units 1 &2. Page 1 of 2 Emergency Plan, Rev. 62, Page 86 of 295 *, .. --'.* ... -.. : ______ . __ . ----TABLE,*'7;1,, ,, ... , * -........ *-.; ,' ____ ,, ___ ,_ .. ',_:*"'. ..... * ,,, __ * ..........
:** .. ______ , ____ , __ ~_-_,,.__
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==SUMMARY==
OF IMMEDIATE NOTIFICATION AND RESPONSE FOR ALL CLASSIFICATIONS ON SITE OFFSITE IMMEDIATE NOTIFICATIONS I ACTIONS IMMEDIATE NOTIFICATIONS ACTIONS SEIC/JIC Provide Info to Public via Media (1-4) (1-4) LCEMA,CCEMA,PEMA,NRC Place ANS & Procedures on (1-4) Standby (2) Activate and Staff Response Centers (2-4) Activate the Emergency Response Data System (2-4) Implement Off-site Protective Measures (4) NOTES: 1. Notification is required to LC EMA, CC EMA, and PEMA within 15 minutes of indication and verification of the event for Unusual Event, Alert, Site Area, and General Emergency.
: 2. Initial notification for all levels of emergencies are to LCEMA, CCEMA, PEMA, and NRC. Page 2 of 2 Emergency Plan, Rev. 62, Page 87 of 295 TABUE 7.2 ... if: EMERGENOYJiXJ?0SURf:*
CRIT_E~IA " ,. . .;.. :.~ -*** ... Planned exposure to the whole body and/or specific organs should not exceed the following recommendations of the National Council on Radiation Protection and Measurements and the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-400).
Guidance on dose limits for workers performing emergency services is summarized in tabular format below. NOTE: These limits apply to doses incurred over the duration of an emergency, treated as a once in a lifetime exposure, and not added to occupational exposure accumulat~d under non-emergency conditions.
Doses to all workers including local offsite support agencies such as firefighting, ambulance services or Local Law Enforcement Agencies during emergencies should, to the extent practical, be limited to 5 rem. There are some emergency situations for which higher exposure limits may be justified.
The need for authorization of potential doses greater than 5 rem should be evaluated based on the criteria specified below under "Guidance on Dose Limits for Workers Performing Emergency Services." Justification of any such exposure must include the presence of conditions that prevent the rotation -of workers or other commonly used dose reduction methods. NOTE: Exposure of workers that is incurred for the protection of large populations may be considered justified for situations in which the collective dose avoided by the emergency operation is significantly larger than that incurred by the workers involved, Persons undertaking any emergency operation in which the dose will exceed 25 rem to the whole body should do so only on a voluntary basis and with full awareness ofthe risks involved, including the numerical levels of dose at which acute effects of radiation will be incurred and numerical estimates of risk of delayed effects. Guidan~e on Dose Limits for Workers Performing Emergency Services ---***-*--.. Dose Ljrfiit a --;'. ~cti~ity_
,,. .. Condition frerril --.* .: . .: .. ____ . -. ,_ -. 5 rem All 10 rem ProtectinQ Valuable Property Lower Doses Not Practicable 25 rem Lifesaving or protection of large Lower Doses Not Practicable populations
>25 rem Lifesaving or protection of large Only on a voluntary basis to persons populations fully aware of the risks involved (see attached tables) ' a Sum of external effective dose equivalent and committed effective dose equivalent to non-pregnant adults from exposure and intake during an emergency situation.
Workers performing services during emergencies should limit dose to the lens of the eye to three times the listed value and doses to any other organ (including skin and body extremities) to ten times the listed value. These limits apply to all doses from an incident, except those received in unrestricted areas as members of the public during the intermediate phase of the incident.
Page 1 of 3 Emergency Plan, Rev. 62, Page 88 of 295 TABLE. 7.2 EMERGENCY EX:POSURE CRITERIA Additional General Criteria
* Only volunteers are given planned emergency exposure.
* Attached tables provide information concerning acute and delayed health effects.
* Whenever practical, consideration is given to dividing exposure among as many personnel as possible.
* Potassium Iodide utilization for iodide prophylaxis requires the approval of the Emergency Director or the Recovery Manager in consultation with the Radiation Protection Coordinator or the Dose Assessment Supervisor and medical consultants, if available.
It is recommended that potassium iodide be administered in situations where potential exposure of the thyroid is anticipated to exceed 1 O rem or at lower dose levels if judged as needed by the RPC or DASU.
* All reasonable measures must be taken to control contamination and internal exposure.
* Persons performing emergency activities should be familiar with exposure consequences.
* Women capable of reproduction should not take part in these actions.
* Retrospective doses are evaluated on an individual case basis.
* As in the case of normal occupational exposure, doses received under emergency conditions should be maintained as low as reasonably achievable.
Health Effects Associated with Whole Body Absorbed Doses Received Within a Few Hours(a) a b C Whole Body Absorbed Dose Early Fatalities(b)
Prodromal Effects(c) (rad) (percent) (percent affected) 050 2 100 15 140 5 150 50 200 15 85 250 98 300 50 400 85 460 95 Risks will be lower for protracted exposure periods. Supportive medical treatment may increase the dose at which these frequencies occur by approximately 50 percent. Forewarning symptoms of more serious health effects associated with large doses of radiation.
Page 2 of 3 Emergency Plan, Rev. 62, Page 89 of 295 TABtE. 7.2' EMERGENCY EXPOSURE CRITERIA 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 30 to 40 7.2 19 40 to 50 5.3 15 50 to 60 3.5 11 Page 3 of 3 Emergency Plan, Rev. 62, Page 90 of 295 TABLE 7.3 ' . >.ii ii PROTECTIVE ACllON, RECOMI\IIENIPATl.diJs
,., ,j ''''"' ..... , 'I EmerQencv Conditions Susquehanna Actions Susquehanna Recommendations A. Airborne Release Determine the following:
: 1. General Public 1. Plant status and prognosis.
SSES will provide an initial PAR based on site-specific wind persistence study to the Senior State Official within 15 minutes from the declaration of a General Emergency as follows:
* Degree. of fuel damage 1. For a Rapidly Progressing Severe Accident (RPSA):
* Containment integrity
: a. Evacuate 2 mile radius;
* Decay heat removal b . Evacuate affected sectors 2-10 miles downwind.
* Ventilation systems
* Remedial, mitigating 2 . For a Hostile Action Based (HAB)
GE event: actions in progress a. Shelter 5 mile radius. 2. Status of radioactive releases.
: 3. For all other General Emergencies:
Release path, monitored, a. Evacuate 2 mile radius;
* b. Evacuate affected sectors 2-5 miles downwind.
unmonitored, both 3.1 When there is a Controlled Containment Venting of less than an hour AND a valid
* Duration of release dose assessment projects doses less than 1 ODO mrem TEDE and less than 5000 mrem
* Trend of release, Adult Thyroid CDE at EPB AND the PAR is issued by extended ERO (TSC or EOF): increasing, decreasing, a. Shelter 2 mile radius; constant b. Shelter affected sectors 2-5 miles downwind.
* Treatment availability, filtered, unfiltered Initial PAR shall also advise citizens to take Kl in accordance with the state's emergency plans
* Type of release, gap, fuel and advise remainder of the EPZ to monitor and prepare . melt
* Prognosis for changes in Continue assessment based on available plant and field monitoring information and evaluate above for subsequent PARs in accordance with: 1. Until RPSA conditions do not apply any more, ERO shall consider the following subsequent PARs based on dose assessment results or changes in wind direction affecting new sectors, if conditions exist which would require classification of a General Emergency per EALs: a. Evacuate additional affected sectors 2-10 miles downwind b. Evacuate all sectors where PAGs were exceeded or are expected to be exceeded.
: 2. Until HAB conditions do not apply any more, ERO shall consider the following subsequent PARs based on dose assessment results: a. Evacuate 2 mile radius b. Evc;1cuate all sectors where PAGs were exceeded.
Page 1 of 3 A. Airborne Release (Cont'd) Determine the following:
: 1. General Public (Cont'd) Emergencv Conditions A. Airborne Release (Cont'd.)
: 2. Dairy Cows Page 2 of 3 3. Weather Conditions, effect on dose projections.
: 4. Dose projections and avoided dose. Susquehanna Action 1. Determine the following:
: a. Peak activity for 1 131 b. Meteorological Conditions (1) Wind Speed (2) Precipitation (3) Stability Class (4) Wind Direction Emergency Plan, Rev. 62, Page 91 of 295 3. If RPSA or HAB conditions do not apply, or for all other General Emergencies, ERO shall consider the following subsequent PARs based on dose assessment results or changes in wind direction affecting new sectors, if conditions exist which would require classification of a General Emergency per EALs: a. Evacuate additional affected sectors 2-5 miles downwind b. Evacuate all sectors where PAGs were exceeded or are projected to be exceeded.
: c. Evacuate 2 mile radius, IF NOT previously recommended 3.1 When there is a Controlled Containment Venting of less than an hour AND a valid dose assessment projects doses less than 1000 mrem TEDE and less than 5000 mrem Adult Thyroid COE at EPB AND the PAR is issued by extended ERO (TSC or EOF): a. Shelter additional affected sectors 2-5 miles downwind . . If the state has informed SSES of impediments to evacuation, recommend shelter "in place" instead of "evacuate" The PAR methodology described above complies with 1OCFR50.47(b)(10), Appendix E to Part 50, Section IV Para ra h 3 and NUREG-0654, Su lement 3, Rev 1. Results Susquehanna Recommendations . . a. Forage Concentration
.05 micro Ci/kg Milk .015 micro Ci/I 1.5 Rem projected dose to the infant thyroid whichever is first. b. Known sectors potentially DEP/BRP to recommend appropriate protective affected action to affected farmers.
B. Liquid Radioactive Release Into Susquehanna River Page 3 of 3 1. Determine the following:
: a. Source of release b. Volume (approx,)
of release c. Anticipated length of time release will continue 2. Notify: a. DEP/BRP . b. Danville Water authority
: c. NRG 3. Initiate sampling of: . a ..
* Release point b. Susquehanna River 4. Initiate projections of radionuclide activity concentrations at the Danville Water Authorit . A single isotope exceeds its specific effluent concentration (EC) value. from C~lumn 2 of Table 2 of Appendix B to
* 1 OCFR20 or diluted sum of EC fractions at Danville is greater than 0.85. Emergency Plan, Rev. 62, Page 92 of 295 1. Recommend to DEP/BRP that consideration be given to termination of user intake of all downstream users. 2. Assess additional results of sampling and analyses of radionuclide activity concentrations of SSES liquid effluent and/or Susquehanna River water upstream of the Danville Water Authority, and provide appropriate updated recommendations_
to DEP/BRP based on that assessment.
Emergency Plan, Rev. 62, Page 93 of 295 8.1 ON-SITE EMERGENCY CENTERS 8.1.1 Control Room 8.1.2 Page 1 of 16 The Control Room is the primary location for the initial assessment and coordination of corrective actions for all emergency conditions.
The Control Room is equipped with the display and controls for all critical plant systems, radiological and meteorological monitorrng systems, and all station communication systems. Reference Appendix D, Enclosure
: 7. Off-site emergency functions initially served by the Control Room are transferred to the TSC or EOF for an Alert, a Site Area Emergency, or a General Emergency as deemed appropriate by the ED. If the TSC and/or EOF are staffed, the functions may also be transferred at the Notification of Unusual Event level. The primary consideration is to ensure that the number of personnel involved with the emergency in the Control Room shall not impair the safe and orderly shutdown of the reactor or the operation of plant safety systems. Operations Support Center The OSC is the primary on-site assembly area for operations support team personnel during an emergency.
There are 2 OSC areas-a primary OSC located separate from the TSC and Control Room and a backup OSC located in the Control Structure.
The primary OSC is located on the first floor of the South (Administrative)
Building.
The backup OSC occupies 340 square feet adjacent to the Control Room on Elevation 729'-1" of the control structure.
The OSC is utilized initially as the central location for as'sembly and accountability of on-shift emergency team personnel required to perform such functions as: firefighting, first aid, search and rescue, damage control, and on-site radiation monitoring.
If and when the TSC is activated, all non-operations support team personnel assemble and are accounted for in the OSC (or CR if the backup OSC is being utilized.)
TSC personnel assess the need for emergency team personnel and based on this assessment, the OSC dispqtches available team personnel and call in additional personnel as. needed. The OSC and TSC assembly areas will be monitored continuously for habitability.
If these areas become uninhabitable, retained personnel will be directed to alternate holding areas. Control and dispatch of these teams is the responsibility of the OSC Coordinator.
The OSC Coordinator manages operations and other support personnel.
Equipment required for these teams to perform their functions, as outlined in Appendix D is stored and maintained in the Control Room, Operations Support Center, Radiation Protection access control points and Maintenance tool areas.
Emergency Plan, Rev. 62, Page 94 of 295 In the event of hazards preventing site access such as certain security events, personnel who normally report to the Operations Support Center will report to the Alternate OSC at the Emergency Operations Facility.
The alternate OSC will be activated as soon as possible to support the site; however, it is recognized that the activation time in the alternate OSC may exceed 60 minutes.*
8.1.2.1 The Primary OSC The primary OSC is located on the first floor of the South (Administration)
Building.
The OSC facilities may be used for normal daily activities that do not degrade OSC emergency preparedness.
8.1.2.1.1 Habitability 8.1.2.1.1.a Allowable Post-Accident Radiation Doses The primary OSC is monitored for radiation exposure using a local ARM and Continuous Air Monitor. The radiation dose will be limited to less than 5 Rem TEDE, at which time the primary OSC will be relocated to the backup OSC. Applicable criteria are specified in General Design Criterion 19, Standard Review Plan NUREG 0800 Section 6A, and NUREG-0737, Item 11.B.2. 8.1.2.1.1.b Postulated Post Accident Radiation Doses The primary OSC is monitored for radiation exposure using a local ARM and Continuous Air Monitor. The radiation dose will be limited to less than 5 Hem TEDE-, at which time the OSC will be relocated to the backup OSC. , Applicable criteria are specified in General Design Criterion 19, Standard Review Plan NUREG 0800 Section 6.4, and NUREG-0737, Item 11.B.2. 8.1.2.1.1.c Radiation Monitoring A portable ARM will be installed in the primary OSC area and a Continuous Air Monitor is installed in the South (Administration)
Building cafeteria, which is adjacent to the primary OSC. This area serves as an accountability area and a holding area for essential personnel.
* Letter dated February 25, 2002 from Samuel J. Collins, Director, Office of Nuclear Reactor Regulations, to Robert G. Byram, Senior Vice President and Chief Nuclear Officer.
 
==Subject:==
Issuance of Order for Interim Safeguards and Security Compensatory Measures for -Susquehanna Steam Electric Station, Units 1 & 2. Page 2 of 16 Page 3 of 16 Emergency Plan, Rev. 62, Page 95 of 295 8.1.2.1.2 HVAC The primary OSC is subject to normal South (Administration)
Building ventilation.
8.1.2.1.3 Shielding There is no special shielding installed.
The primary OSC is located in an* area with no outside walls. 8.1.2.1.4 Occupant Accommodations Since the primary OSC is located in an administration building, toilet facilities and water are available . . 8.1.2.1.5 Communications The primary OSC communication system includes the plant PA system and telephone lines tied through the plant switchboard.
8.1.2.1.5.a Telephone The normal telephone service for the primary OSC uses the plant ETN system, anc:I can reach on and offsite locations.
8.1.2.1.5.b Public Address System The PA system is part of the plant PA system. The system provides two-way communications at handset stations.
Each station may originate and receive communications by switching to either a page channel or to one of five non-interfering party line channels.
Page 4 of 16 Emergency Plan, Rev. 62, Page 96 of 295 8.1.2.2 Backup OSC A backup OSC area exists in the Control Structure and would be used in the event the primary OSC becomes uninhabitable.
During normal plant operations, this area serves as an operations staff work area for shift changeover purposes as well as shift work assignment area. The Non-Emergency use of the OSC does not degrade its primary purpose. 8.1.2.2.1 8.1.2.2.2 Habitability 8.1.2.2.1.a Allowable Post-Accident Radiation Doses Back-up OSC personnel are protected from radiological hazards, including direct shine and airborne activities for postulated accident conditions to the same degree as Control Room personnel.
Applicable criteria are specified in General Design Criterion 19, Standard Review Plan NUREG 0800 Section 6.4, and NUREG-0737, Item 11.B.2 8.1.2.2.1.b Postulated Post Accident Radiation Doses The radiation dose to personnel occupying the backup OSC is the same as the Control Room personnel.
The doses from controlling accidents are summarized in Chapter 15.0 of the FSAR. 8.1.2.2.1.c Radiation Monitoring To ensure adequate radiological protection of the backup OSC personnel, a commercial grade monitor located in the center of the Control Room alarms on high gross gamma radiation dose rates. HVAC The backup OSC HVAC system is a part of the Control Room HVAC system which is described in FSAR Section 9.4.1.
Page 5 of 16 Emergency
*Plan, Rev. 62, Page 97 of 295 8.1.2.2.3 Shielding Shielding requirement for the backup OSC is the same as for the Control Room for total dose to occupants from direct shine and airborne.
Exposure does not exceed 5 Rem TEDE for the duration of the accident.
This is in accordance with General Design Criterion 19, USN RC Standard Review Plan NUREG 0800 Section 6.4, and NUREG-0737, Item 11.B.2. Duration of occupancy and method of analysis is the same as that used for the Control Room. Access control may need to be applied within five feet of the east wall of the Control Structure (including the backup OSC) as described in Emergency Plan position specific procedures.
8.1.2.2.4 Occupant Accommodations No toilet facilities are provided in the backup OSC.
Facilities are available in the Control Room and at grade level of the control structure for washing and toilet accommodations.
8.1 :2.2.5 Communications The backup OSC communication system includes the plant PA system and telephone lines tied through the plant switchboard.
8.1.2.2.5.a Telephone The normal telephone service for the backup OSC uses the plant ETN and CTN systems. Both systems have the capability to reach on and offsite locations.
8.1.2.2.5.b Public Address System The PA system is part of the plant PA system. The system provides two-way communications at handset stations.
Each station may originate and receive communications by switching to either a page channel or to one of five non-interfering party line channels.
Emergency Plan, Rev. 62, Page 98 of 295 8.1.3 Technical Support Center The TSC is a controlled access area that provides working space and . facilities for approximately 25 ERO personnel.
These personnel provide guidance to plant operations personnel for management of emergency conditions and accident mitigation.
The TSC is located in the existing Control Room mezzanine above the Control Room at elevation 7 41 '-1" of the control structure and occupies approximately 2500 square feet. The TSC is within approximately two minutes travel time of the Control Room by elevator or stairs.
* The TSC facilities may be used .for normal daily activities that do not degrade TSC emergency preparedness.
The TSC provides office space for Operations and Technical personnel.
Other station personnel may also use the facilities as a research or reference area. In the event of hazards preventing site access such as certain security events, personnel who normally report to the Technical Support Center will report to the Alternate TSC at the Emergency Operations Facility.
The alternate TSC will be activated as soon as possible to support the site; however, it is recognized that the activation time in the alternate TSC may exceed 60 minutes.*
* 8.1.3.1 Spatial Layout Description The TSC includes areas for work, conferencing (NRC &
* Susquehanna), document control, and computer monitoring.
Housed components are PICSY terminals, associated copiers, and VERMS Maintenance Interface Terminal. (Reference Figure 8.2.) 8.1.3.2 Fire Protection Smoke detection and automatic pre-action sprinkler system are provided.
8.1.3.3 Structural Design Criteria The TSC is part of the control structure that is a Seismic Category I structure, as defined in NRC Regulatory Guide 1.29. It is designed in accordance with Chapter 3.0 of the FSAR. *
* Letter dated February 25, 2002 from Samuel J. Collins, Director, Office of Nuclear Reactor Regulations, to Robert G. Byram, Senior Vice President and Chief Nuclear Officer.
 
==Subject:==
Issuance of Order for Interim Safeguards and Security Compensatory Measures for -Susquehanna Steam Electric Station, Units 1 & 2. Page 6 of 16 Page 7 of 16 Emergency Plan, Rev. 62, Page 99 of 295 8.1.3.4 Habitability 8.1.3.4.1 Post-Accident Radiation Doses 8.1.3.4.1.a Allowable TSC personnel are protected from radiological hazards, including direct shine and airborne activities for postulated accident conditions to the same degree as control room personnel.
Applicable criteria are specified in General Design Criterion 19, Standard Review Plan NUREG 0800 Section 6.4,. and NUREG-0737, Item 11.B.2. 8.1.3.4.1.b Postulated The radiation dose to personnel is the same as the Control Room personnel.
The doses from contrqlling accidents are summarized in Section 15 of the FSAR. 8.1.3.4.1.c Radiation Monitoring 8.1.3.4.2 H\/AC Commercial grade monitors are provided to alarm on high gross gamma radiation dose rates. In addition, airborne radioactivity concentrations are monitored by portable monitors.
Iodine detection capability is provided.
The TSC H\/ AC system is a part of the Control Room H\/ AC system which is described in FSAR Section 9.4.1. 8.1.3.4.3 Shielding Shielding is the same as for the Control Room for total dose to occupants from direct shine and airborne.
Exposu,re will not exceed 5 Rem TEDE for the duration of the accident.
This is in accordance with General Pesign Criterion 19, USNRC Standard Review Plan NUREG 0800 Section 6.4, and NUREG-0737, Item 11.B.2. Duration of occupancy and method of analysis is the same as for the control room. Access control may need to be applied within five feet of the east wall of the Control Structure (including impacted TSC areas) as described in Emergency Plan position specific procedures.
Page 8 of 16 Emergency Plan, Rev. 62, Page 100 of 295 8.1.3.4.4 Occupant Accommodations No sleeping accommodations or toilet facilities are provided.
Use of the plant's existing facilities at grade level of the control structure for washing and toilet accommodations is available.
Self-contained breathing apparatus are *available for personnel who are qualified in their use. 8.1.3.5 Communication Links The TSC communications system is comprised of three telephone networks (ETN, CTN, and FTS), VHF and UHF radios, and the plant PA system. They provide reliable primary *and back-up communication links to emergency response facilities on-and off-site.
8.1.3.5.1 Telephones The TSC uses the CTN system as primary communications with the ETN system available at various locations and the FTS 2001 reserved for federal government agencies.
8.1.3.5.2 Radio The TSC has a four-channel 450 MHz UHF and a two-channel 150 MHz VHF radio system with digital voice privacy capability.
The VHF radio is an emergency backup for communication with LCEMA and CCEMA, and to communicate with the field monitoring teams. The UHF radio provides primary and backup security, emergency, operational and maintenance communication links.
* 8.1.3.5.3 Public Address System The PA system is part of the plant PA system. The system provides two way communications at handset stations.
Each station may originate and receive communications by switching to either a page chan.nel or to one of five non interfering party line channels.
8.1.3.6
* Power Supply The TSC is part of the existing power block as described in Chapter 8.0 of the. FSAR: 8.1.3. 7 Instrumentation The TSC utilizes the same field sensors and signal conditioning equipment that is provided to monitor plant systems. TSC instrumentation is identical to the field instrumentation used to operate the plant. A detailed description of this instrumentation is provided in Chapter 7.0 of the FSAR.
Emergency Plan, Rev. 62, Page 101 of 295 8.1.3.8 TSC Data Presentation The TSC includes human factors engineered man-machine capabilities to allow personnel to determine:
* * * * *
* plant conditions during normal operation plant steady-state conditions prior to an accident transient conditions producing an initiating event plant system dynamic behavior during an accident projected behavior and effects of offsite airborne radioactivity releases.
The man-machine interface is provided by the Plant Integrated Computer System (PICSY), located in the TSC. (Reference Figure 8.2.) 8.1.3.9 Records and Documents The TSC contains up-to-date records and references for use during emergency conditions. (Reference Appendix D.) Records are updated and managed by DCS utilizing Plant Administrative Procedures.
8.1.3.10 Security The TSC is located within a plant vital area and is subject to the vital area access controls as identified in the Security Plan. 8.2 SUSQUEHANNA OFF-SITE EMERGENCY CENTERS 8.2.1 Joint Information Center 8.2.2 Page 9 of 16 For a Notification of Unusual Event, the Susquehanna Energy Information Center, located on U.S. Route 11, is utilized as the Joint Information Center. For other event classifications, the East Mountain Business Center, Plains Township, will be activated as the Joint Information Center. Emergency Operations Facility The EOF is an emergency response facility that provides continuous management of Susquehanna activities during radiological emergencies that may have offsite impact. The EOF is located on East Mountain Boulevard in Plains Township, off PA Route 115 five miles north of exit 105 of the Northeast Extension of the Pennsylvania Turnpike and one mile south of exit 170A of Interstate
: 81. As the EOF is located beyond 1 O miles from the site, the NRC Commission approval was required prior to the relocation.
This was granted April 17, 1996 (see REFERENCES, Section 3.19). The non-emergency activities of the EOF are such that its main function is not degraded.
Page 10 of 16 Emergency Plan, Rev. 62, Page 102 of 295 8.2.2.1 Architecture The EOF is a one-story, rectangular structure.
The building was constructed using standard building codes. 8.2.2.1.1 Spatial Layout Description Reference Figure 8.3. 8.2.2.1.2 Fire Protection Automatic wet pipe sprinklers are provided throughout the building.
8.2.2.2 Structural Classification The EOF is classified as a structure, the failure of which would not result in release of significant radioactivity, and is not required for reactor shutdown.
This structure is classified as Non-Category I. 8.2.2.3 Habitability The EOF is located outside the EPZ; therefore, no special habitability needs are required.
8.2.2.4 Communications The EOF communications system is comprised of three telephone networks (ETN, CTN, and FTS), VHF radios, and a PA system. They provide a reliable primary and back-up communications network. 8.2.2.4.1 Telephones The EOF uses a combination of the CTN and ETN systems with the FTS system available for federal governmental agencies.
Cellular telephones may also be used as needed. 8.2.2.4.2 Radio . The EOF has a two-channel 150 MHz VHF radio system that is used as an emergency backup to the telephone system to communicate with the field monitoring teams, the TSC, CCEMA, and LCEMA. 8.2.2.5 Power Reliability Power is supplied fo the EOF via two independent underground power lines that supply the industrial park complex. Upon experiencing.a loss of power from the normal supply, a diesel generator starts and supplies power to the building.
Emergency Plan, Rev. 62, Page 103 of 295 8.2.2.6 EOF Data Presentation The EOF includes human factors engineered man-machine interface capabilities to allow personnel to: * * *
* access environmental conditions coordinate raqiological monitoring activities recommend implementation of off-site emergency plans monitor Emergency Response Data System 8.2.2. 7 Records and Documents The EOF contains up-to-date references and records. Documents are managed by DCS using plant administrative procedures.
8.2.2.8 Security EOF access during an emergency is limited to authorized personnel.
Intrusion detection devices monitor the EOF during unoccupied periods. 8.2.3 Alternate Operations Support Center (OSC) The alternate OSC is accessible even if the site is under threat of or experiencing hostile action since it is located within the Emergency Operations Facility.
It functions as a staging area for OSC staff and has the capability for communication with the emergency operations facility, control room, and plant security.
The alternate OSC provides the OSC staff with the capability for damage control team planning and preparation when the primary OSC and backup OSC cannot be safely accessed during hostile action. 8.2.4 Alternate Technical Support Center (TSC) Page11of16 The alternate TSC is accessible even if the site is under threat of or experiencing hostile action since it is located within the Emergency Operations Facility.
It functions as a staging area for TSC staff and has the capability for communication with the emergency operations facility, control room, and plant security.
The alternate TSC provides the TSC staff with the capability to perform offsite notifications and for engineering assessment activities when the primary TSC cannot be safely accessed during hostile action. 
 
===8.3 Emergency===
 
Plan, Rev: 62, Page 104 of 295 COUNTY AND STATE EMERGENCY CENTERS 8.3.1 8.3.2 County Emergency Centers Both LCEMA and CCEMA have EOCs that meet or exceed the minimum Federal criteria for sufficient space, communications, warning systems, self-sufficiency in supplies and accommodations and radiological protection factor. Both counties maintain full-time employees, providing 24-hour per day coverage either at their EOC or their "911" Centers, to coordinate emergency planning and evaluation. "CTN" telephone connections exist between SSES and each County EOC. Location of the county EOCs: *
* Luzerne County Emergency Management Building Wilkes-Barre, Pennsylvania Columbia County Columbia County Courthouse 911 Annex Bloomsburg, Pennsylvania State Emergency Center The Commonwealth Response Coordination Center (CRCC) is located at 1310 Elmerton Avenue in Harrisburg.
This center has 24 hour per day coverage and is equipped with a reliable communications system that includes "CTN" telephone connections between the CRCC and SSES, and
* ties to all area and county EOCs. During an emergency, representatives from appropriate State agencies will assemble at the CRCC to manage and support the emergency response activities.
Facilities are also available at the EOF for PEMA personnel.
 
===8.4 ASSESSMENT===
 
CAPABILITIES
 
====8.4.1 Radiation====
 
Monitoring System This on-site system, consisting of ARMs, CAMs, and process monitors, contributes to personnel protection, equipment monitoring and accident assessment by measuring and recording radiation levels and concentrations at selected locations throughout the station. Reference Appendix D. 8.4.2 Fire Protection Page 12 of 16 Fire protection at SSES is provided by a network of fire detection, suppression, and extinguishing systems. These systems and associated fire alarms are activated by a variety of fire and smoke detection devices throughout the plant. Types of detectors include combustion product, smoke, thermal, and flame. For more detail, reference the SSES Fire Protection Review Report.
Emergency Plan, Rev. 62, Page 105 of 295 8.4.3 Natural Phenomena Monitors 8.4.4 8.4.5 Monitors are provided for detecting and recording natural phenomena events that could result in plant damage due to ground motion or structural vibration.
Reference Appendix D. Environmental Monitoring This program establishes the pre-operational background levels, detects any gradual buildup of long-lived radionuclides, and verifies that operation of the plant has no detrimental effect on the health and safety of the public or the environment.
Reference Appendix D. Radiological Monitoring Team Equipment Reference Appendix D. 8.5
* PROTECTIVE FACILITIES
 
====8.5.1 Control====
Room 8.5.2 8.5.3 Page 13 of 16 Protective features (Reference the SSES FSAR): a. Adequate shielding by concrete walls. b. CREOASS. c. ARM system indications.
: d. Emergency and essential lighting and power. e. Basic protection equipment for emergency teams (Appendix D), and listings/locations of additional emergency supplies/equipment.
: f. Communications systems. Station Accountability Areas Specific locations are designated for accountability of all station personnel.
They are located on the basis of logical access routes and physical separation from likely areas of radiation and/or airborne radioactivity.
Remote Assembly Areas Upon declaration of a Site Evacuation, the ED may send personnel to their homes or to Remote Assembly Areas. These areas are designated for assembly of personnel who can be used to augment the plant staff. Locations were selected on the basis of: a. Space availability for all personnel who may be within the exclusion area at the time of an evacuation.
: b. Assurance of a controlled area for contamination surveys and for possible establishment of decontamination stations.
Emergency Plan, Rev. 62, Page 106 of 295 8.5.4 Alert Notification System An ANS consisting of sirens with ratings of 121 dB at 100' exists within the ten-mile EPZ around SSES. Siren location (see Figure 8.4) was determined by a detailed study including field surveys, actual determination of average background noise level, and consideration of population distribution within the 10-mile EPZ. Activation of the ANS is via radio control from either the LCEMA Emergency Operations Center or CCEMA Emergency Operations Center. A back-up satellite system can also activate the sirens from LCEMA or CCEMA. A redundant control station located at the EOF has full radio control capabilities, and will be used for the purpose of testing and maintenance activities.
Direct Current (DC) batteries provide a back-up source of power to the normal Alternating Current (AC) supply. The Nuclear Emergency Alert signal is a 3 minute steady tone. Public response to this signal is to proceed indoors and tune their radio or television to the Emergency Alert System Network serving their local area for additional information.
Testing of the system takes place annually and includes verification of the system's ability to alert the general public. 8.6 ADDITIONAL COMMUNICATIONS SYSTEMS 8.6.1 8.6.2 Commercial Telephone System Two independent telecommunications networks exist to proyide primary and backup telephone communications between ERFs and offsite agencies.
These systems are the Centrex Telephone Network (CTN) and Electronic Tandem Network (ETN) .. CTN extension locations include: Control Room, TSC, EOF, JIC, SEIC, DEP/BRP, PEMA, LCEMA, and CCEMA. This is the primary system for emergency communications.
Plant Emergency Alarm System A plant emergency alarm system provides audible warning of emergency conditions to. plant personnel.
The system consists of a multi-tone generator, tone selector switch, area selector switch, and message tape recorder.
The Emergency Alarm System is integral to the PA System and is powered via the Vital AC UPS. The Plant Emergency Alarm System is tested at least weekly. 8.7 ON-SITE FIRST AID AND MEDICAL FACILITIES A first aid treatment facility, equipped with normal industrial first aid supplies, is located on the first floor of the S&A Building.
Standard first aid kits are at designated locations throughout the station. Inventories
*are performed regularly.
Page 14 of 16 Emergency Plan, Rev. 62, Page 107 of 295 8.8 DAMAGE CONTROL EQUIPMENT Damage control equipment.consists of normal and special purpose tools and devices used for maintenance functions throughout the station. The ED has access to keys for maintenance tool cribs, shops and other locations where damage control equipment is stored. Inventories are performed regularly.
 
===8.9 INFORMATION===
 
SYSTEMS 8.9.1 .Plant Integrated Computer System
* Page 15 of 16 The PICSY is used for emergency data configuration for the following reasons: * * * * * * * *
* It contains graphic and trending capabilities.
It provides for historical data recording and retrieval.
It has flexibility to permit interfacing to additional 1/0 equipment and other sources of data. Its design provides for a high degree of reliability.
It is capable of displaying and reporting plant data needed in the EOF and TSC. It is located in a secure area within the control structure.
It has a redundant system design. The EROS and SPDS functions are integrated into its design. All of the PICSY data and functions are easily made available at locations remote from SSES. 8.9.1.1 Data Acquisition Data is acquired from 1/0 hardware in the plant as well as over data interfaces to various other plant equipment.
All data is checked for validity and errors before being displayed to the user. Isolation is applied to all safety-related inputs. All data fs archived.
Both short term and long term data are available for retrieval at any PICSY SOS. Long term qata is available for at least the previous fuel cycle. 8.9.1.2 Data Preparation Display formats needed by the ERF are generated and stored within the PCS using standard proven PICSY software.
A configuration management software system is employed to tr~ck changes to all formats and the database itself. Proven system and application software has been developed which performs data display and system security.
The database includes raw data, data converted to engineering units, data checked on a real-time basis, and various types of calculated data. User interaction from the PICSY SOS is independent from each station and controlled by multiple copies of the identical software.
Page 16 of 16 Emergency Plan, Rev. 62, Page 108 of 295 8.9.1.3 Data Presentation Three SDSs are available in the TSC for display of Unit 1, Unit 2, and Common data. Procedures and methods for call-up and error indications of TSC function are identical to those used in the control room with one exception.
Control Room monitors are usually fitted with touch screens in lieu of track balls and keyboards.
Data is presented in formats that are easy to understand and interpret.
Variables not in a normal condition are presented with an indication of that condition.
Alarms are represented by using the same color coding techniques as in the control room. Output formats are designed according to human factors engineering criteria, and include pattern and coding techniques.
8.9.1.4 Availability A minimum system availability of 99% or greater can be expected, based on analytical calculations.
Emergency Plan, Rev. 62, Page 109 of 295 ' ,, '' .* TABLES .. 1 ; *' ' .. * " '' ' RELAflONSHlP OF'THE. PRIMARY PARAMETER?z SEqONDARY DISPLAY, AND ALGORITHl\,1S j .. * ',, ON:SPDS . ' . Primary Secondary Parameter Display Algorithm Reactor Power 1. Reactor Core Status a. Reactivity Monitoring
: b. Core Flow C. Core Spray Reactor Water 1. Reactor Water Level History a. Reactor Water Level Level Reactor Pressure 1. Reactor Pressure History a. Reactor Pressure 2. S/R Valve Lifts a. S/RV Positions (non-ADS)
Drywell Pressure 1. Drywell Pressure and Temperature
: a. Drywell Pressure History b. Drywell Temperature
: 2. Containment Status a. Suppression Pool Water Level b. Suppression Chamber Pressure C. Suppression Pool Water Temperature
: d. Suppression Chamber Atmosphere Temperature
: e. S/RV Positions (ADS) 3. Containment Hydrogen/Oxygen Limits a. Containment Atmosphere Control Noble Gas 1. Radioactive Effluent Release a. Off-Gas Pretreatment Effluent Release b. Prima_ry Containment Activity C. Reactor Building Vent d. Turbine Building Vent e. Liquid Effluent f . Standby Gas Treatment
: 2. Containment Isolation . a. Containment Isolation Page 1 of 1 
..............
l -_r .... ** .......... **---Page 1 of 1 --........ ..., I . . ' --*-***-* , .... ----*1.~ .. "'
* I . ' '-. . . t . ' ' . I t , *~ ' ' Emergency Plan , Rev. 62 , Page 110 of 295 '. ' . \ -----.* , __ _ :
NUCLEAR REGULATORY COMMISSION u 0 rn o Oil 0 0 0 0 61 rn 0 Oil ------10 Oi rnm 0 Oi Typical work station including desk, chair, telephone as necessary for emergency response for the listed positions.
Administrative Coordinator Security Coordinator TSC Dose Calculator with MIDAS HPN Communicator Radiation Protection Coordinator Emergency Director TSC Emergency Plan Communicator TSC NRC Communicator Operations Coordinator Technical Support Coordinator Damage Control Team Coordinator Engineering Support Area NSSS Engineer Core thermal Hydraulic Engineer Electrical/I&
C Engineer lgal uuu Engineering Support Area
* Page 1 of 1 Field Team Radio Verms Interface Elevator Emergency Plan, Rev. 62, Page 111 of 295 SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND2 EMERGENCY PLAN Technical Support Center FLOOR PLAN FIGURE 8.2 Indicates telephone-may be a standard telephone.
May also represent FTS phone. TERMINAL Cabinet Symbol for Computerfifiilf Station-b!Llill!LI PICSY SPDS MIDAS (Symbol is not necessarily indicative c;,f the specific number of computer installations.
The symbol designates a typical installation)
Er1gi11cering Suppo<t ~111idQ;lc:if Ar,1'1c::1,r.*cnt Page 1 of 1 :::J CJ a EOF Su""&deg;" Emergency Plan, Rev. 62, Page 112 of 295 East Mountain Business Center/ Floor Plan EOF/JIC Go..AuitmJt*
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[g1 lloanl M8dla WO!lt Roon, SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND2 EMERGENCY PLAN EOF / MOC (JIC) Al TERNATE TSC FLOOR PLAN FIGUREB.3 Audllodum
! t f; ;; 1 Emergency Plan, Rev. 62, Page 113 of 295 Susquehanna OVPM 2008-09 Legend Prep!lred tor; ~ncan Sil)n11! Corporation 0 1 :2. 4 5 8 ~!;,a I I : I I .. 0 , 4 8 12 Page 1 of 1 10 1 M iles 1 K i tometers 16 ; -... , 10 Mile R ad iu s Plant " ASCT-121 OVPM Contours SUSQUEHANNA STEAM ELECTRIC STATION Units 1 and 2 EMERGENCY PLAN SIREN LOCATION Figure 8.4 Emergency Plan, Rev. 62, Page 114 of 295 9.1 ORGANIZATIONAL PREPAREDNESS
 
====9.1.1 Training====
Page 1 of 7 a. All unescorted personnel entering or working within the SSES Radiologically Controlled Area receive as a minimum, the following instruction:
* Appropriate portions of the SSES EP.
* Use of emergency facilities and equipment, familiarization with statio.n alarms and personnel response, and station communications systems.
* Personnel accountability, evacuation, and radiation exposure criteria.
* Radiation protection, emphasizing protective clothing, equipment, and personnel dosimetry. , b. Those individuals working on the SSES site, inside the protected area, but outside the Radiologically Controlled Area, are provided with instructions on warning signals, accountability areas, and evacuation routes. c.. Personnel assigned to the Susquehanna ERO receive specialized training for their respective assignments. (Reference Table 9.1) d. PEMA conducts a training program throughout the State and assists the counties in developing training policy for disaster operational readiness.
The county and local EMAs are responsible for planning and conducting disaster preparedness training of respective emergency response personnel.
Susquehanna works closely with PEMA and the county EMAs in coordinating training programs.
In addition, orientation training for State and county agencies and personnel involved in SSES emergency planning efforts is made available by Susquehanna.
: e. Annually, DEP/BRP and state, county, and municipal EMAs are invited to participate in a training program conducted by Susquehanna.
The initial training program relates the importance of emergency planning and the interface between the Susquehanna and offsite emergency organizations with an emphasis on classification; EALs; reporting requirements; assessment, protective, and corrective actions; and communications networks.
In addition, DEP/BRP is offered a sp~cific review of dose calculations/projections, protective actions guides, and reportable information.
Page 2 of 7 Emergency Plan, Rev. 62, Page 115 of 295 f. The State Police, annually, are invited to participate in a training program on appropriate EP-PSs, with emphasis on the classification of emergencies, communications, and specific areas of responsibility.
: g. Susquehanna provides training annually to local off-site support organizations.
These local organizations are encouraged to become familiar with the SSES, key station personnel, and are invited to attend training conducted by or for Susquehanna.
Initial core training for local fire companies and ambulance associations includes:
* Interface with the Site Security Force
* Basic radiation protection indoctrination and training
* SSES facility layout Fire companies also receive training in the following areas:
* On-site fire protection system equipment
* Differences between on-site firefighting equipment and fire company supplied equipment
* Communications system
* Review of sections of the SSES EP and EP-PSs
* The on-site ERO with emphasis on the interface between the SSES fire brigade and fire company personnel
: h. Personnel assigned to the Emergency Planning Organization receive training as required by EP administrative procedures.
Emergency Planning experience may be used in lieu of training.
Each year a fire drill, which includes local fire company support, is held to test these areas. Annually local ambulance associations are invited to attend specialized training regarding the handling of contaminated/injured victims.
9.1.2 Page 3 of 7 Emergency Plan, Rev. 62, Page 116 of 295 Drills and Exercises Each drill or exercise is conducted to: (1) ensure that the participants are familiar with their respective duties and responsibilities, (2) verify the adequacy of the SSES EP procedures, (3) test communications networks and systems, (4) determine availability and operability of emergency supplies and equipment, and (5) every two years verify the adequacy of off-site agency plans. Drills and exercises are conducted to simulate actual emergency conditions as closely as possible and may be scheduled such that more than one type of the following drills or exercises can be conducted simultaneously to meet the guidance of NUREG-0654, NSIR/DPR-ISG-01 Section IV.G and the requirements of 1 OCFR50 Appendix E:
* Annual medical drill involving offsite support
* Annual fire drill involving offsite support
* Annual radiological drill to site area or general emergency level with offsite participation biennially
* Annual full-scale ANS test
* Annual environmental monitoring drill
* Semi-annual Health Physics drill testing survey sampling and analysis techniques
* Annual drill that tests ability to obtain and analyze a post accident coolant sample
* Perform augmentation exercise every eight years
* Hostile Action Based exercise every eight years Page 4 of 7 Emergency Plan, Rev. 62, Page 117 of 295 All ERO teams (not necessarily each individual) shall be provided the opportunity to develop and maintain key emergency response skills within the scope of their duties during each exercise cycle. Additionally, the ERO (not necessarily each ERO team) shall be provided the opportunity to demonstrate key skills in response to the following scenario elements in drills or exercises during each exercise cycle. Drills are considered to be performance-enhancing experiences (exercises, drills, functional drills, tabletop drills, mini-drills, etc.) that reasonably simulate the interactions between appropriate ERFs and/or individuals that would be expected to occur during emergencies.
* All functions in each ERF (e.g., all ERFs that are responsible for dose assessment perform those duties in response to a radiological release).
* Use of alternative facilities to stage the ERO for rapid activation during hostile action.
* Real-time staffing of facilities during off-hours (i.e., 6:00 p.m. to 4:00 a.m.).
* Providing medical care for injured, contaminated personnel (every two years).
* Response to essentially 100 percent of initiating conditions identified in the site emergency plan implementing procedure for classification of emergencies.
* Response to actual industry event sequences appropriate for the nuclear plant technology (e.g., BWR or PWR).
* All ERO teams must be provided the opportunity to demonstrate key skills within the scope of their duties.
* Use of procedures developed in response to an aircraft threat and in. compliance with 10 CFR 50.54(hh)(1).
* Use of the strategies associated with 1 O CFR 50.54(hh)(2) to mitigate spent fuel pool damage scenarios (all strategies, such as makeup, spray, and leakage control, but not every variation of a given strategy).
* Use of the strategies associated with 10 CFR 50.54(hh)(2) to mitigate reactor accidents and maintain containment (1 O strategies for boiling water reactors, but not every variation of a given strategy).
Additional non-integrated drills and tests are conducted as follows:
* Bi-weekly Silent Tests for sirens
* Quarterly Growl Tests for sirens
* Quarterly fire drills
* Monthly communications drills with state and county agencies
* Monthly communications tests with the NRC Drill scenarios for major drills are prepared to involve participation of several emergency teams and all cir specific parts of the ERO including varying degrees of participation of State, County, and Federal agencies and local off-site support organizations.
Following the conduct of drills, critiques are held to clearly identify deficiencies and action plans for resolution.
Procedures are established to assure the timely implementation of corrective actions. , Ingestion pathway exercises are conducted by the offsite agencies in accordance with PEMA Annex E. Susquehanna Steam Electric Station personnel provide support as required.
Emergency Plan, Rev. 62, Page 118 of 295 9.1.3 Overall Coordination of Nuclear Emergency Preparedness Page 5 of 7 The Manager-Security/Emergency Preparedness is responsible for the overall coordination of all nuclear emergency planning activities.
The Manager-Security/Emergency Preparedness is assisted in this effort by: the Plant Manager for activities involving the Susquehanna Site, the General Manager-Nuclear Engineering for engineering issues, the Manager-Nuclear Training for on-site training, the Community Relations Manager-Susquehanna for communications with the public and news media, and the Manager-Nuclear Oversight for audits of Emergency Planning.
The Manager-Security/Emergency Preparedness is typically responsible for:
* Revising of the SSES Emergency Plan
* Revising of EP-PSs and other Emergency Planning Administrative procedures
* Conducting of integrated drills and exercises and communication drills
* Defining EP training scope for ERO
* Defining EOF and JIC EP Training
* Coordinating EP interface between State and Federal agencies
* Coordinating maintenance and testing of ANS
* Coordinating interface between state, county, municipal, and Susquehanna ERO
* Assuring operational readiness of Emergency Response Facilities 
 
===9.2 Emergency===
 
Plan, Rev. 62, Page 119 of 295 REVIEW AND UPDATING 9.2.1 SSES Emergency Plan 9.2.2 The Manager-Security/Emergency Preparedness is responsible for the review and revision of the SSES Emergency Plan, ensuring:
* A review of the SSES Emergency Preparedness Program is performed periodically by persons who have no direct responsibility for implementation of the program in accordance with 1 OCFR50.54t.
* Annual review of the SSES Emergency Plan.
* Annual review of Letters of Agreement.
* Recommendation of Emergency Plan changes to PORC.
* PORC review of Emergency Plan changes and submission of changes to NSRB.
* Revisions or a report of change to the Emergency Plan that do not change the effectiveness of the plan are submitted to the NRC within 30 days from the implementation of such change(s).
* Perform an annual review of the Evacuation Time Estimate (ETE) to ensure 1 OCFR50 Appendix E Section IV and NUREG 0654 Element J.8 requirements are maintained.*Update the full ETE should the criteria from Appendix E be met and re-submit the ETE to the NRC. Emergency Plan Procedures The Manager-Security/Emergency Preparedness is responsible for the review and revision(s) of the Emergency Plan Procedures, ensuring:
* The periodic review is accomplished in accordance with established plant procedures.
-* Revisions to procedures are done in accordance with established plant procedures.
*
* Controlleq copies of procedure revisions are issued by station document control programs.
* ERO personnel are briefed on revisions as required.
Page 6 of 7 Emergency Plan, Rev. 62, Page 120 of 295 9.3 MAINTENANCE AND INVENTORY OF EMERGENCY EQUIPMENT/SUPPLIES The Manager-Security/Emergency Preparedness is responsible for periodic inventory and inspection of emergency equipment and supplies, and for periodic testing of emergency communications systems. This testing includes verification of phone numbers that are contained in Emergency Plan procedures.
Equipment, supplies, and parts having limited shelf lives are checked and replaced as necessary.
Monthly communications drills and tests are also conducted from Susquehanna ERFs and offsite agencies.
Any deficiencies found during these activities are either cleared immediately or documented for corrective action. 9.4 PUBLIC EDUCATION AND INFORMATION Under the direction of the Manager-Security/Emergency Preparedness, the following methods are utilized to ensure that emergency planning information and education is provided and transmitted to residents and transients in the EPZ annually.
 
====9.4.1 Telephone====
 
Directory Inserts With the cooperation of Pennsylvania Emergency Management Agency, Luzerne County Emergency Management Agency, and Columbia County Emergency Management Agency, emergency information is provided in all telephone directories distributed within the ten mile EPZ. This information includes:
* * * * * *
* explanation of Emergency Classifications what to do when you hear the sirens public Protective Actions student pick-up points evacuation routes to reception centers evacuation Plan Map callback number for special needs 9.4.2 Programs are Offered to Acquaint the News Media With:
* SSES Emergency Plan
* information concerning radiation
* points of contact for the release of public information during an emergency
 
====9.4.3 Educational====
 
Training Programs Educational training programs on emergency preparedness are made available to the general public through the staffs of the Susquehanna Energy Information Center and Nuclear Emergency Preparedness.
 
====9.4.4 Other====
Distributed Publication(s)
This information includes:
Page 7 of 7 * * * * * *
* explanation of Emergency Classifications what to do when you hear the sirens public Protective Actions student pick-up points evacuation routes to reception centers evacuation Plan Map callback number for special needs TABLE 9.1 Emergency Plan, Rev. 62, Page 121 of 295 TRAINING OF SUSQUEHANNA SES EMERGENCY RESPONSE PERSONNEL
: 1. Emergency Directors
: 2. Personnel responsible for accident assessment/
m.anagement
: 3. Radiation Monitoring Teams 4. Fire Brigade 5. Damage Control Teams Page 1 of 2 Shift Managers, and currently assigned Emergency Directors Emergency Director; Emergency Coordinators, Recovery Manager, Dose Assessment Personnel Radiation Protection Supervision; Radiation Protection Technicians; and Site Personnel Unit Supervisors
-Fire Brigade Leader, Maintenance Site Support Services ersonnel -Fire Bri ade Members Non-Licensed Operators; Maintenance Supervision; Maintenance Personnel; Radiation Protection Technicians; l&C Supervision; l&C Personnel . Ittitial:
Ttairiin :a11d F>eriodic Retraihin Initial training:
EP and EP PSs. Retraining:
Retraining:
Retraining:
Changes in responsibilities.
Annual EP and EP PSs. Applicable EP PSs and changes. Annual Radiation monitoring EP PSs and applicable Radiation Protection Procedures Hands-on instrument usage. Fre uenc : Annual Training and retraining are outlined in the SSES Fire Protection Review Report. Repair and Damage Control are a normal part of the job functions.
Initial training:
Availability of damage control equipment, use of communication systems, and interfaces with other emergency teams. Retraining:
Fre uenc : Review of the above topics. Annual TABLE 9.1 Emergency Plan, Rev. 62, Page 122 of 295 TRAINING OF SUSQUEHANNA SES EMERGENCY RESPONSE PERSONNEL Personnel Cateaorv '1 Involved Personnel Initial Training and Periodic Retraining
: 6. First Aid and Rescue Work Groups having 24-hour coverage at Personnel (Emergency Susquehanna: (supplemental team members Medical Response Teams) directed by Team Leader) Security Force Members Training and retraining:
Communication system and interfaces with local medical support personnel.
Non-Licensed Operators Training and retraining:
First Aid, CPR Training, and availability of on-site medical treatment supplies and equipment; (see Note) Radiation Protection Training and retraining:
CPR Training and radiological hazards (see Note) Training and retraining:
CPR Training (see Note) Chemistry Retraining frequency:
See Note Maintenance Site Suooort Services 7. Fire Suooort Personnel Local Fire Companies Traininq and retraininq are outlined in Section 9 of the SSES EP. 8. Medical Support Personnel Berwick Hospital Staff; Ambulance Companies; Initial training:
Treatment and handling of contaminated/injured Geisinger Medical Center Staff personnel, communication systems, radiological hazards and interfaces with SSES personnel.
Retraining:
Review of the above topics. Retraininq freauencv:
Annual 9. Corporate Support Corporate Management Personnel; including Initial training:
EP and appropriate EP PS's. Personnel Nuclear Fuel and Analysis, Nuclear Design Engineering and Technology Retraining:
Applicable EP-PSs and changes. Retraininq freauencv:
Annual 10. Securitv Personnel Security Supervision; Security Force Members Training is outlined in the SSES Training and Qualification Plan. 11. Public Information Joint Information Center Personnel Initial training:
EP and Public Information EP PS. Personnel Retraining:
Applicable EP-PSs and changes. Retraininq freauencv:
Annual NOTE: Specific training and retraining requirements are identified in the Training Matrices for Emergency Planning, Security, Radiation Protection, Chemistry, Operations, Maintenance Site Support Services and all ERO members. Page 2 of 2 Security-Communications/Interface, First Aid, CPR annually NLO -First Aid and CPR biennially RP -Communications/Interface, First Aid, CPR biennially CHEM -First Aid and CPR biennially MSSS -First Aid and CPR biennially Page 1 of 3 Emergency Plan, Rev. 62, Page 123 of 295 APPENDIX A LE1TERS OF AGREEMENT Emergency Plan, Rev. 62, Page 124 of 295 Letters of Agreement have been established with those State and Local agencies as well as local and industry support service groups that are responsible to ensure a high level of emergency preparedness for the SSES. These agreements have been established to assure all parties are aware of their commitment to SSES and the public in the vicinity of the SSES during an emergency including a HOSTILE ACTION event. The following list of agencies and support groups have signed letters of agreement:
Agency/Support Group Berwick Ambulance Association Berwick Hospital Center Berwick Volunteer Fire Department Columbia County Commissioners Dan E. Bower, Inc Department of Energy Department of Environmental Protection/Bureau of Radiation Protection Federal Radiation Monitoring and Assessment Center (FRMAC) GE BWR Emergency Support Geisinger Medical Center Hobbie Volunteer Fire Co. -EMS Hunlock Creek Ambulance Association Institute of Nuclear Power Operations Lackawanna County Commissioners Latona Trucking . Luzerne County Council Medico Industries Mocanaqua Volunteer Fire Company Nanticoke Ambulance/Medic 25 Nanticoke Fire Department National Weather Service Pennsylvania Emergency Management Agency Pond Hill-Lily Lake Ambulance Association Salem Township Volunteer Fire Co. Shickshinny Volunteer Ambulance Assoc. Stell Enterprises Summerhill Fire Department Wilkes Barre Scranton International Airport Page 2 of 3 Emergency Plan, Rev. 62, Page 125 of 295 These letters of agreement provide for:
* Coordination of plann!ng efforts by State and local agencies; industry support groups; fire ambulance and hospital support services; and Susquehanna.
* Appropriate emergency response to assure employee and public safety during an emergency condition at SSES.
* Mutual notification capabilities.
* Appropriate training and exercising of emergency response capabilities.
* Fire, first aid and medical support.
* Environmental monitoring and assessment support.
* Other emergency support services as deemed necessary The Manager-Security/Emergency Preparedness is responsible for renewing letters of agreement every year where applicable.
In some instances, where the letter of agreement is for a specified duration longer than 1 year, letters need not be renewed until the end of the specified duration.
Copies are maintained and controlled within Document Control Services to assure appropriate review and updating takes place. NOTE: Page 3 of 3 Reference Action Request 1066721 for why separate LOA is not needed for Pennsylvania State Police.
Emergency Plan, Rev. 62, Page 126 of 295 APPENDIX B WIND ROSES, DOSE/DISTANCE PLOTS AND JOINT FREQUENCY DISTRIBUTION ORIGINAL DOCUMENT ISSUED 01/1992 SPECIFIC FIGURES MAY HAVE OTHER ISSUE DATES. Page 1 of 17 Emergency Plan, Rev .. 62, Page 127 of 295 INTERPRETATION OF WIN-O*ROSES Perhaps the best way to discuss the interpretation is to take a specific example. Let us consider the wind rose for Spring (Figure I). This wind rose represents the average wind conditions at the 1 O meter level for a total of 4 Springs (1973-1976).
Spring is defined as the months of March, April, and May. Similarly Summer consists of June, July, and August, Autumn is September, October, and November, and Winter is December, January, and February.
In looking at Figure I we see that the winds are most frequently from the West. Thus they will carry plant effluents towards the East. We also see that 11.5% of all the winds are from the West. Winds from the West at speeds of 0-1.5 meters per second (mps) comprise 1.6% of all *winds; winds from the West at speeds of 1.5-5.0 mps comprise 6.9% of all winds; winds from the West at speeds of greater than 5 mps comprise 3.0% of all winds. We can also see that 0.8% of all the winds are calm and therefore are not assigned a direction.
In addition the least frequent winds are from the Southeast.
It is also apparent that the lightest winds (0-1.5 mps) most frequently are associated with winds from the East-Northeast and East while the strongest winds (greater than 5 mps) are most frequently associated With winds from the West. Page 2 of 17 Emergency Plan, Rev. 62, Page 128 of 295 INTERPRETATION OF DOSE./DISTANCE
:PLOTS _, ---*-***. --* -* **-_,_. __ . The dose/distance plots have been removed and reference to the use of MIDAS as the approved methodology/tool for determining magnitude of and for continually assessing the impact of the release. MIDAS has the capability to provide assessments using event-specific fuel damage estimates.
Additionally, MIDAS can provide information at additional distances than were provided in the deleted Dose/Distance nomographs.
The system performs estimates and predictions of atmospheric effluent transport and diffusion during and immediately following an accidental airborne radioactive release from the facility.
Page 3 of 17 The data in Tables 8-6 through 8-13 are from meteorological measurements taken at the Susquehanna site during the time period from 1999 through 2003. Examples are provided of the way that a joint frequency distribution may be interpreted.
The first example relates to the likelihood of a specific stability class occurring on the Susquehanna site. Table 8-7 for Stability Class B shows that this Moderately Unstable class occurs about 1363143823
(=0.031) or 3.1 % of the time. Table B-9 for Stability Class D shows that this Neutral class occurs about 17841143823
(=.407) or about 40. 7% of the time. Looking at all of the information, the reader will see that the more common stability classes that occur at Susquehanna are the D (Neutral) and E (Slightly Stable) stability classes. The second example relates to the wind speeds that are more common for specific stability classes occurring on the Susquehanna site. Table B-7 for Stability Class B shows that for this Moderately Unstable class, the most common wind speed is in the range from 3.1-5.0 mis (6.9-11.2 mph), a relatively high wind speed. Table B-10 for* Stability Class E shows that for this Slightly Stable class, the most common wind speed is in the range from 1.1-1.5 mis (2.5-3.4 mph), a relatively lower wind speed. The third example relates to the wind directions that are more common for the Susquehanna site. The Table B-13 of the Joint Frequency Distribution presents a summary for all stability classes observed at the Susquehanna site. The most common wind direction is ENE, meaning that most commonly, the wind is blowing from the ENE over the Susquehanna site. The second most common wind direction is SW, meaning that next most commonly, the wind is blowing from the SW over the Susquehanna site. As can be seen from review of the table, upriver and downriver winds occur quite commonly at the site. Page 4 of 17 LEGEND: 111111111:C::::::::::=JIIIIIIIIIIIII
'0-1.5 1.5-5.0 >5 Meters Per Second Page 5 of 17 Emergency Plan, Rev. 62, Page 130 of 295 N s ~ev. 11, 10/88 SUSQUEHANNA STEAM ELECTRIC STATION . UNITS 1 AND 2 EMERGENCY PLAN WIND FREQUENCY DISTRiBUTIQN IN PERCENT PERIOD OF RECORD-1973-1976 (SPRING SEASON) FIGURE B-i LEGEND: HIIIIIII 0-1.5 1.5-5.0 ;*S Meters Per Second Page 6 of 17 Emergency Plan, Rev. 62, Page 131 of 295 N s Rev. 11, 10/88 SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 EMERGENCY PLAN WIND FREQUENCY DISTRIBUTION IN PERCENT . PERIOD:OF RECORD-1973-1976 (SUMMER SEAS.ON) FIGURE B LEGEND: UIIIIIII 0-1.5 1.5-5.0 >S Met.er_s Per Second Page 7 of 17 Emergency Plan, Rev. 62, Page 132 of 295 N s Rsv. 11, 10/88 SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 EMERGENCY PLAN WIND FREQUENCY DISTRIBUTION IN PERCENT PERIOD OF RECORD-1973-1976 (AUTUMN SEASON) . FIGURE B-3 LEGEND: 111111111c=:=:==::J11111111 0-1.5 1.5-5.0 >S Meters Per*second Page 8 of 17 Emergency Plan, Rev. 62, Page 133 of 295 N s Rev. 11, 10/88 SUSQUEHANN~
STEAM ELECTRIC STATION UNITS 1 AND 2 EMERGENCY PLAN WIND FREQUENCY DISTRIBUTION IN PERCENT PERIOD OF RECORD-1973-1976 (WINTER SEASON) FtGURE B-4 LEGEND: IIIIIIIIJill1:::::::=::::J111111111 0-1.5 1,5-5.0 >5 Meters Per Second Page 9 of 17 Emergency Plan, Rev. 62, Page 134 of 295 N Rev. 11, 10/Sa SUSQUEHANNA STEAM ELE.CTRIC STATION UNITS 1 AND 2 EMERGENCY PLAN WIND FREQUENCY DISTRIBUTION IN PERCENT PERIOD OF RECOR0-1973-1976 (ANNUAL AVERAGE) flG_URE B-5 Emergency Plan, Rev. 62, Page 135 of 295 Joint Frequency Distribution Hours at Each Wind Speed and Direction Period of Record = 01/01/99 1 :00 -12/31/03 23:00 Total Period Elevation:
Speed: 10M SPD Direction:
1 OM WD Lapse: DT60-10 Stability Class: A Delta Temperature:
Extremely Unstable Wind SQeed (m/s) Wind 0.23-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-Direction 0.50 0.75 1,_Q 1.&sect; 2.0 3.0 5.0 7.0 10.0 13.0 18.0 > 18.0 Total from N 1 0 0 2 3 11 28 4 0 0 0 0 49 NNE 0 0 0 3 1 28 58 4 0 0 0 0 94 NE 0 0 0 7 15 45 23 0 0 0 0 0 90 ENE 0 0 1 8 17 11 4 0 0 0 0 0 41 E 0 0 4 26 8 4 1 0 0 0 0 0 43 ESE 0 1 7 12 7 8 6 0 0 0 0 0 41 SE 0 0 2 6 14 33 20 0 0 0 0 0 75 SSE. 0 0 2 6 19 36 14 1 0 0 0 0 78 s 0 0 2 10 28 62 63 1 0 0 0 0 166 SSW 0 0 0 12 38 105 88 4 0 0 0 0 247 SW 0 0 1 10 38 177 261 28 1 0 0 0 516 WSW 0 0 0 4 7 29 125 35 2 0 0 0 202 w 0 0 0 1 2 4 48 5 0 0 0 0 60 WNW 0 0 0 1 2 6 12 0 0 0 0 0 21 NW 0 0 0 0 1 0 6 3 0 0 0 0 10 NNW 0 0 0 1 0 1 12 4 0 0 0 0 18 Totals 1 19 109 200 560 769 89 3 0 0 0 1751 Number of Calm Hours for this Table 18 Number of Variable Direction Hours for this Table 0 Page 10 of 17 Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 297 1751 43823 SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 EMERGENCY PLAN JOINT FREQUENCY DISTRIBUTION FIGURE B-6 Emergency Plan, Rev. 62, Page 136 of 295 Joint Frequency Distribution Hours at Each Wind Speed and Direction Period of Record = 01 /01 /99 1 :00-12/31/03 23:00 Total Period Elevation:
Speed: 10M SPD Direction:
1 OM WD Lapse: DT60-10 Stability Class: 8 Delta Temperature:
Moderately Unstable Wind SQeed (m/s} Wind 0.23-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-Direction 0.50 0.75 .1Q 1..&sect; 2.0 3.0 5.0 7.0 10.0 13.0 18.0
> 18.0 Total from N 0 1 0 1 5 9 42 8 0 0 0 0 66 NNE 0 0 0 3 20 47 34 3 0 0 0 0 107 NE 0 0 0 12 16 46 24 0 0 0 0 0 98 ENE 0 0 1 24 13 10 2 0 0 0 0 0 50 E 0 0 9 15 7 10 3 0 0 0 0 0 44 ESE 0 0 4 11 14 5 5 0 0 0 0 0 39 SE 0 0 2 10 11 16 11 0 0 0 0 0 50 SSE 0 0 0 4 11 11 6 0 0 0 0 0 32 s 0 0 2 11 14 38 21 0 0 0 0 0 86 SSW 0 0 1 11 39 55 28 3 0 0 0 0 137 SW 0 0 0 4 36 105 175 31 4 0 0 0 355 WSW 0 0 1 1 7 23 100 43 2 0 0 0 177 w 0 0 0 0 1 8 34 4 0 0 0 0 47 WNW 0 0 0 0 1 1 18 1 0 0 0 0 21 NW 0 0 0 0 1 5 10 2 0 0 0 0 18 NNW 0 0 0 0 4 8 19 3 2 0 0 0 36 Totals 0 1 20 107 200 397 532 98 8 0 b 0 1363 Number of Calm Hours for this Table 18 Number of Variable Direction Hours for this Table 0 Page 11 of 17 Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 297 1363 43823 SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 EMERGENCY PLAN JOINT FREQUENCY DISTRIBUTION FIGURE B-7 Emergency Plan, Rev. 62, Page 137 of 295 Joint Frequency Distribution Hours at Each Wind Speed and Direction Period of Record= 01/01/99 1:00-12/31/03 23:00 Total Period Elevation:
Speed: 10M SPD Direction:
1 OM WD Lapse: DT60-10 Stability Class: c Delta Temperature:
Slightly Unstable Wind SQeed (m/s} Wind 0.23-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-Direction 0.50 0.75 1.Q 1.,.&sect; 2.0 3.0 5.0 7.0
* 10.0 13.0 18.0
> 18,0 Total from N 0 0 0 3 7 23 73 6 0 0 0 0 112 NNE 0 0 1 8 21 52 59 6 0 0 0 0 147 NE 0 0 0 12 24 45 20 0 0 0 0 0 101 ENE 0 0 2 25 20 14 4 0 0 0 0 0 65 E 0 1 7 19 8 8 3 0 0 0 0 0 46 ESE 0 1 6 15 16 10 3 0 0 0 0 0 51 SE 1 0 7 9 17 13 11 0 0 0 0 0 58 SSE 0 1 4 12 18 21 12 0 0 0 0 0 68 s 0 0 4 26 28 50 28 0 0 0 0 0 136 SSW 0 0 1 24 35 76. 17 2 0 0 0 0 155 SW 0 0 1 18 43 146 186 37 1 0 0 0 432 WSW 0 0 1 3 11 38 139 61 7 0 0 0 260 w 0 0 0 8 7 7 51 21 1 0 0 0 95 WNW 0 0 0 0 .2 14 31 1 0 0 0 0 48 NW 0 0 1 0 3 9 30 4 o* 0 0 0 47 NNW 0 0 .0 1 1 19 31 1 E? 2 0 0 0 70 Totals 3 35 183 261 545 698 154 11 0 0 0 1891 Number of Calm Hours for this Table 18 Number of Variable Direction Hours for this Table 0 Page 12 of 17 Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 297 1891 43823 SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 EMERGENCY PLAN JOINT FREQUENCY DISTRIBUTION FIGURE B-8 Emergency Plan, Rev. 62, Page 138 of 295 Joint Frequency Distribution Hours at Each Wind Speed and Direction Period of Record = 01/01/99 1 :00-12/31/03 23:00 Total Period Elevation:
Speed: 10M SPD Direction:
1 OM WO Lapse: DT60-10 Stability Class: D Delta Temperature:
Neutral Wind Si;ieed (m/s) Wind 0.23-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-Direction 0.50 0.75 1Q 1.&sect; 2.0 3.0 5.0 7.0 10.0 13.0 18.0
> 18.0 Total from N 2 7 23 74 119 433 716 98 0 0 0 0 1472 NNE 1 16' 64 214 267 519 324 15 0 0 0 0 1420 NE 9 33 119 276 281 418 164 6 0 0 0 0 1306 ENE 8 51 130 219 153 158 54 3 0 0 0 0 776 E 10 85 158 202 124 119 32 5 0 0 0 0 735 ESE 15 67 144 144 117 146 58 7 3 1 0 0 702 SE 7 53 110 219 169 200 121 14 1 0 0 0 894 SSE 10 38 74 163 158 179 89 9 1 0 0 0 721 s 3 26 84 210 204 257 106 7 0 0 0 0 897 SSW 0 15 54 220 242 368 139 2 0 0 0 0 1040 SW 1 8 29 193 242 594 864 170 7 0 0 0 2108 WSW 0 3 15 87 132 254 627 425 90 1 0 0 1634 w 0 1 6 38 80 196 396 172 35 0 0 0 924 WNW 0 2 4 23 49 157 314 108 19 0 0 0 676 NW 1 2 1*1 31 45 225 632 178 6 0 0 0 1131 NNW 0 4 8 33 52 268 752 280 8 0 0 0 1405 Totals 67 411 1033 2346 2434 4491 5388 1499 170 2 0 0 17841 Number of Calm Hours for this Table 18 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period Page 13 of 17 297 17841 43823 SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 EMERGENCY PLAN JOINT FREQUENCY DISTRIBUTION FIGURE B-9 Emergency Plan, Rev. 62, Page 139 of 295 Joint Frequency Distribution Hours at Each Wind Speed and Direction Period of Record= 01/01/99 1:00-12/31/03 23:00 Total Period Elevation:
Speed: 10M SPD Direction:
1 OM WO Lapse: DT60-10 Stability Class: E Delta Temperature:
Slightly Stable Wind Si:1eed (m/s) Wind 0.23-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-Direction 0.50 0.75 1..Q 1,&sect; 2.0 3.0 5.0 7.0 10.0 13.0 18.0 > 18.0 Total from N 1 14 28 90 138 144 53 2 0 0 0 0 470 NNE 3 33 112 324 269 254 79 1 0 0 0 0 1075 NE 13 124 289 551 197 159 54 0 0 0 0 o* 1387 ENE 20 279 467 493 87 29 7 3 0 0 0 0 1385 E 41 378 361 154 33 29 5 0 0 0 0 0 1001 ESE 45 265 207 99 30 24 8 5 0 0 0 0 683 SE 37 201 229 152 48 50 23 10 4 0 0 0 754 SSE 19 109 183 213 95 63 40 6 0 0 0 0 728 s 10 75 216 413 193 151 49 18 0 0 0 0 1125 SSW 3 42 126 397 334 309 84 4 0 0 0 0 1299 SW 2 14 39 188 209 343 210 10 1 0 0 0 1016 WSW 0 4 12 64 80 83 61 14 3 0 0 0 321 w 2 1 9 36 33 37 19 4 Cl 0 0 0 141 WNW 0 2 7 16 23 34 13 0 0 0 0 0 95 NW
* 1 2 4 19 42 87 24 2 0 0 0 0 181 NNW 0 5 6 21 41 116 35 2 0 0 0 0 226 Totals 197 1548 2295 3230 1852 1912 764 81 8 0 0 0 11887 Number of Calm Hours for this Table 18 Number' of Variable Direction Hours for this Table 0 Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period Page 14 of 17 297 11887 43823 SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 EMERGENCY PLAN JOINT FREQUENCY DISTRIBUTION FIGURE 8-10 Emergency Plan, Rev. 62, Page 140 of 295 Joint Frequency Distribution Hours at Each Wind Speed and Direction Period of Record= 01/01/99 1 :00-12/31/03 23:00 Total Period Elevation:
Speed: 10M SPD Direction:
1 OM WD Lapse: DT60-10 Stability Class: F Delta Temperature:
Moderately Stable Wind Si;ieed (m/s) Wind 0.23-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-Direction 0.50 0.75 1.,.Q 1.,&sect; 2.0 3.0 5.0 7.0 10.0 13.0 18.0 > 18.0 Total from N 1 5 6 25 11 5 2 0 0 0 0 0 55 NNE 5 21 34 66 32 9 1 0 0 0 0 0 168 NE 13 92 198 257 50 1 1 0 0 0 0 0 612 ENE 21 361 806 994 149 6 0 0 0 0 0 0 2337 E 44 371 356 149 9 0 0 0 0 0 0 0 929 ESE 23 160 122 15 0 0 0 0 0 0 0 0 320 SE 14 82 82 25 2 0 0 0 0 0 0 0 205 SSE 8 32 78 49 6 1 0 0 0 0 0 0 174 s 2 29 78 121 14 1 1 0 0 0 0 0 246 SSW 1 16 24 81 37 4 1 0 0 0 0 0 164 SW 1 4 15 38 21 19 2 0 0 0 0 0 100 WSW 0 0 5 6 4 3 1 0 0 0 0 0 19 w 2 2 3 5 0 1 0 0 0 0 0 0 13 WNW 1 0 0 2 2 1 0 0 0 0 0 0 El NW 0 0 2 1 1 2 1 0 0 0 0 0 7 NNW 1 0 3 2 5 2 2 0 0 0 0 0 15 Totals 137 1175 1812 1836 343 55 12 0 0 0 0 0 5370 Number of Calm Hours for this Table 18 Number of Variable Direction Hours for this Table 0 Page 15 of 17 Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 297 5370 43823 SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 EMERGENCY PLAN JOINT FREQUENCY DISTRIBUTION FIGURE 8-11 Emergency Plan, Rev. 62, Page 141 of295 Joint Frequency Distribution Hours at Each Wind Speed and Direction Period of Record= 01/01/99 1:00-12/31/03 23:00 Total Period Elevation:
Speed: 10M SPD Direction:
1 OM WD Lapse: DT60-10 Stability Class: G Delta Temperature:
Extremely Stable Wind Sgeed (m/s) Wind 0.23-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1-Direction 0.50 0.75 1,Q 1..&sect; 2.0 3.0 5.0 7.0 10.0 13.0 18.0
> 18.0 Total from N 1 2 2 3 1 0 0 0 0 0 0 0 9 NNE 1 16 17 17 3 1 0 0 0 0 0 0 55 NE 2 71 168 162 19 1 0 0 0 0 0 0 423 ENE 8 167 690 1065 186 4 0 0 0 0 0 0 2120 E 13 120 219 102 3 0 0 0 0 0 0 0 457 ESE 4 63 55 9 0 0 0 0 0 0 0 0 131 SE 3 31 35 12 2 1 0 0 0 0 0 0 84 SSE 0 14 23 15 3 0 0 0 0 0 0 0 55 s 0 5 12 17 0 0 0 0 0 0 0 0 34 SSW 1 2 8 7 5 1 0 0 0 0 0 0 24 SW 0 2 3 1 0 1 0 0 0 0 0 0 7 WSW 0 1 0 0 0 0 0 0 0 0 0 0 1 w 0 0 0 0 0 1 0 0 0 0 0 0 1 WNW 0 0 0 0 0 0 0 0 0 0 0 0 0 NW 0 1 0 0 0 0 0 0 0 0 0 0 1 NNW 0 2 0 1 0 0 0 0 0 0 0 0 3 Totals 33 497 1232 1411 222 10 0 0 0 0 0 0 3405 Number of Calm Hours for this Table 18 Number of Variable Direction Hours for this Table 0 Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period Page 16 of 17 297 3405 43823 SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 EMERGENCY PLAN JOINT FREQUENCY DISTRIBUTION FIGURE B-12 Emergency Plan, Rev. 62, Page 142 of 295 Joint Frequency Distribution Hours at Each Wind Speed and Direction Period of Record= 01/01/99 1:00-12/31/03 23:00 Total Period Elevation:
Speed: 10M SPD Direction:
Summary of All Stability Classes Delta Temperature Wind SQeed (m/s) Wind 0.23-0.51-0.76-1.1-1.6-2.1-3.1-Direction 0.50 0.75 1...Q 1..&sect; 2.0 3.0 5.0 from N 6 29 59 198 284 625 914 NNE 10 86 228 635 613 910 555 NE 37 320 774 1277 602 715 286 ENE 57 858 2097 2828 625 232 71 E 108 955 1114 667 192 170 44 ESE 87 557 545 305 184 193 80 SE 62 367 467 433 263 313 186 SSE 37 194 364 462 310 311 161 s 15 135 398 808 481 559 268 SSW 5 75 214 752 730 918 357 SW 4 28 88 452 589 1385 1698 WSW 0 8 34 165 241 430 1053 w 4 4 18 88 123 254 548 WNW 1 4 11 42 79 213 388 NW 2 5 18 51 93 328 703 NNW 1 11 17 59 103 414 851 Totals 436 3636 6446 9222 5512 7970 8163 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 10M WD Lapse: DT60-10 5.1-7.1-10.1-13.1-7.0 10.0 13.0 18.0
> 18.0 Total 118 0 0 0 0 2233 29 0 0 0 0 3066 60 0 0 0 0 4017 6 0 0 0 0 6774 5 0 0 0 0 3255 12 3 1 0 0 1967 24 5 0 0 0 2120 16 1 0 0 0 1856 26 0 0 0 0 2690 1 0 0 0 0 3066 276 14 0 0 0 4534 578 104 1 0 0 2614 206 36 0 0 0 1281 110 19 0 0 0 867 189 6 0 0 0 1395 305 12 0 0 0 1773 1921 200 2 0 0 43508 18 0 297 43508 43823 SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 EMERGENCY PLAN JOINT FREQUENCY DISTRIBUTION FIGURE B-13 Page 17 of 17 Page 1 of 2 Emergency Plan, Rev. 62, Page 143 of 295 APPENDIXC SSES EMERGENCY PLAN POSITION SPECIFIC PROCEDURES
{TYPICAL)
Emergency Plan, Rev. 62, Page 144 of 295 APPENDIXC SSES EMERGENCY PLAN POSITION SPECIFIC PROCEDURES (TYPICAL)
,,,'f;V,>, '.,/ ,', ",;,, ,,,.,-',,,-, , '" ~-' ,& , ',, J<'"i',y'\(,'+ ,c_,,""'*""''*,'Y,i,~', " ~-/.0/.", ,''0, , c.;, ,' o-,, "'' EMERGENCY PLAN POSITION SPECIFIC PROCEDURES (Response Procedures)
CR Procedures EOF Procedures Emen::iency Director Recoverv Manaoer Emeroency Plan Communicator EOF Suooort Supervisor NRC Communicator NEP Duty Planner EOF Emergency Plan Communicator TSC Procedures Environmental Sampling Team Emergency Director Radioloaical Monitorino Team TSC Technical Suooort Coordinator EOF Administrative Assistant TSC Operations Coordinator EOF Liaison Support Supervisor Radiation Protection Coordinator EOF Dose Assessment Staffer TSC Dose Calculator EOF Dose Assessment Supervisor RP Tech I (Oscar) Field Team Director Security Coordinator EOF Environmental Sampling Director TSC Administrative Coordinator EOF Technical Advisor TSC E Plan Communicator Enoineerino Support Supervisor HPN Communicator Fuels Lead Engineer / Core Thermal Hydraulics Enoineer RP II Dose Calculator EOF Systems Lead Enoineer Damaoe Control Team Coordinator EOF Support Engineer Severe Accident Management Coordinator TSC NRC Communicator TSC Information Coordinator JIC Procedures Fuels Lead Engineer / Core Thermal Public Information Manager Hydraulics Engineer TSC RP Radio Communicator News Manaaer JIC Technical Briefer Support Services Manager OSC Procedures Media & Public Officials Contact OSC Coordinator JIC Loakeeper RP Specialist JIC Writer Maintenance Foreman/Field Unit Supervisor JIC Administrative Coordinator Chemistrv Coordinator OTHEREMERGENCYPLANRESPONSEPROCEDURES Offsite Organization Response to Plant Events , , Emergency Telephone Instructions and Susquehanna Offsite Organization Response Directory to Plant Events Remote Assembly Area Contamination Control Termination and Restoration Brief Non-Technical Description of EALs EAL Classification Bases SSES MIDAS-NU User Manual Personnel Accountability Page 2 of 2 Emergency Plan, Rev. 62, Page 145 of 295 APPENDIX D EQUIPMENT INFORMATION LISTINGS Page 1 of 16 Emergency Plan, Rev. 62, Page 146 of 295 CONTENTS OF APPENDIX D Equipment Information Listings Enclosure 1 Typical Station Decontamination Area Equipment Typical Damage Control Equipment Storage Box Contents Enclosure 2 Onsite Search and Rescue/First Aid, Typical Ambulance and Hospital Radiation Emergency Equipment and Supplies.
Enclosure 3 Natural Phenomena Monitors Enclosure 4 Radiological Monitors Enclosure 5 Environmental Monitoring Systems Enclosure 6 Typical Radiation Protection Van Radiation Emergency Monitoring Equipment Enclosure 7 Emergency Classification Dependent Instrumentation Enclosure 8 Typical Initial Emergency Equipment for Initial Incident Response Typical TSC Equipment Enclosure,9 Typical EOF Equipment Page 2 of 16 Emergency Plan, Rev. 62, Page 147 of 295 ENCLOSURE 1 TO APPENDIX D Typical Station Decontamination Area Equipment Decontamination Procedures Coveralls . Decontamination Soap Disposable Bath Towels Plastic Gloves+ Cotton Inserts Frisker Hand Brushes Masking Tape Paper Towels Shoe Covers, paper . Sponge Typical Damage Control Equipment Storage Box Contents Amprobe Bars, Pry, Large Bars, Pry, Rolling Lead _ Black Wire, 1 /4 lb. Rolls, 16 Gal,lge Box, Tool, 23"
* Bucket, 14 quart, Plastic Cable Cutters Clamps, C, Medium Clamps, C, Large Clamps, C, Small Electricians Pouch with Miscellaneous Hand Tools .Enerpac, Rescue Unit Flashlight, 5 cell Hammer, Ball Peen, 16 oz.
* Hammer, Sledge, 1 O lb. Hammer, Sledge, 8 lb. Multimeter Nylon Rope, 100' coils, 3/4" Nylon Rope, 25' coils, 3/8" Nylon Rope, 50' coils, 3/8" Nylon Rope, 50' coils, 3/4" Plastic Sheet, 20' X 20', Fire Retardant Pliers, Lineman Pliers, Water Pump Page 3 of 16 Plugs, Wood, 1" & 6" Plugs, Wooden Box, 1", 1%', 1%', 2", 2%'', 3" Rubber, Roll 1/16" thick, 10' X 3' Screwdrivers, Large Standard Screwdrivers, Medium Standard Screwdrivers, Phillips, Large Screwdrivers, Phillips, Medium String, Ball Twine, Bale Wedges, Wooden Wrench, Adjustable, 12" Wrench, Adjustable, 8" Wrench, Allen Pac 3/16", 7/32", 1/4", 5/16", 3/8" Wrench, Allen Pac .050", 1/16", 5/64", 3/32", 7/64", 1/8", 9/64", 5/32", 3/16", 7/32" Wrench, Chain Wrench, Hex, #110 Wrench, Hex, #17 Wrench, Hex, 24" Wrench, Pipe, 18" Wrench, Pipe, 14" Emergency Plan, Rev. 62, Page 148 of 295 ENCLOSURE 2 TO APPENDIX D Typical Onsite Search and Rescue/First Aid, Ambulance.
and Hospital Radiation Emergency Equipment and Supplies Onsite Search Rescue/First Aid: Adjustable Litter Basket Stretcher (Stokes) First Aid Team Initial Response Kit with Inventory Sheet Ambulance Kit: Masking Tape Waste "Rad" Bags Plastic Gloves Cotton Gloves Hospital:
Dosimeter Charger Survey Meter Frisker with Probe Herculite Lead Container, high activity samples Page 4 of 16 Folding Litter Portable Oxygen-Demand Valve (size D tank With assorted airways, cannulas, and masks) Sco 1 op Stretcher Trauma Kit Assorted Splinting Devices Herculite Shoe Covers Portable Frisker and Probe Lab Coats Self Reading Dosimeters Set of Radiation Signs and Ribbon Stanchions/Pylons Step-off Pad Thermoluminescent Dosimeters, badge type Thermoluminescent Dosimeters, ring type Emergency Plan, Rev. 62, Page 149 of 295 ENCLOSURE 3 TO APPENDIX D Natural Phenomena Monitors METEOROLOGICAL MONITORING INSTRUMENTATION
: 1. Wind Speed Instrument
: a. Elevation 10 meters and 60 meters. 2. Wind Direction Instrument
: a. Elevation 10 meters and 60 meters. 3. Air Temperature Difference Instrument
: a. Elevation 10/60 meters. 4. Ambient Temperature Gauge Instrument
: a. Elevation 10 meters. 5. Dew Point Gauge Instrument
: a. Elevation 10 meters. 6. Rainfall Gauge Instrument
: a. Ground level. SEISMIC MONITORING INSTRUMENTATION INSTRUMENTS AND SENSOR LOCATIONS
: 1. Triaxial Accelerometers and Triggers a. Reactor Equipment, Unit 1 b. Reactor Bldg. Floor (RHR), Unit 1 c. ESSW Pumphouse Floor (a) d. Containment Foundation, Unit 1 (a) e. Containment Structure, Unit 1 f. Containment Foundation, Unit 2 (a) 2 Response-Spectrum Analyzer/Recorders (a) The Unit 1 Containment Foundation, Unit 2 Containment Foundation and ESSW Pumphouse Floor Accelerometer Channels have associated triggers.
These triggers provide control room indication and annunciation.
Page 5 of 16 Instrument Type Air Sampling Equipment Personnel Dosimetry Portable Survey Instruments Countinq Room Page 6 of 16 Emergency Plan, Rev. 62, Page 150 of 295 RADIOLOGICAL MONITORS Individual Detectors Continuous Air Monitors High volume samplers Low volume samplers Breathinq zone samplers Electronic Dosimetry TLD's GM survey instruments Ion chamber survey instruments Ion chamber survey instruments Telescoping GM survey instruments GM count rate meters Meter with alpha scintillation probe Neutron detector Portal monitors Low backqround qas proportional counters Liquid scintillation counter. scintillation
-alpha scintillation
.: beta High Purity Ge Spectrometer GM End Window Scaler ,', Function & Sensitivity Particulate, Iodine Equipment
& Gas Monitor Particulate, Iodine Particulate, Iodine Particulate, Iodine 0 -100,000 mrem 0 -2 R/hr O -5 Rem/hr 0 -50 Rem/hr 0 -1,000 R/hr O -50,000 cpm 10 CPM to 100,000 CPM 0 -5 Rem/hr N/A Emergency Plan, Rev. 62, Page 151 of 295 ' ,, ' " -***-* " ,, ", ,, ,"' ,, ''' '" . ... ''"-~ Encl(>s~re 4 to Appendix D (Cont'd.)
';; AREA RADIATION MONI'TOR$ (ARMs) ' " ' " -* *-.:.-.... Location Range Local Channel# Buildina and Area Elev. {mR/hr) Alarm 1 1 R/2R Resid Heat Removal Area 645' 0.1-1000 Yes 2 1 R/2R RCIC Pump Turbine Room 645' 0.01-100
* Yes 3 1 R/2R HPCI Pump Turbine Room 645' 0.01-100 Yes 4 1 R/2R Radwaste Sump Area 645' 0.1-1000 Yes 5 1 R/2R Control Rod Drive (North} 719' 0.1-1000 Yes 6 1 R/2R Control Rod Drive (South) 719' 0.1-1000 Yes 7 1 R/2R OffQas Bv Pass Line 656' 0.1-1000 Yes 8 1 R/2R Cleanup Recirc. Pump Access Area 749' 0.01-100 Yes 9 1 R/2R CRD Repair Area 719' 0.1-1000 Yes 10 1 R/2R Fuel Pool Room 749' 0.1-1000 Yes 11 1 R/2R Sample Station Room 749' 0.01-100 Yes 12 1 R/2R Recirc. Fan Room 799' 0.01-100 Yes 13 1 R/2R New Fuel Storaae Vault 817' 0.1-1000 Yes 14 1 R/2R Spent Fuel Pool 818' 0.1-1000 Yes 15 1 R/2R RefuelinQ Floor Area 818' 0.01-100 Yes 16 1 R/2R Access to Remote .Shutdown 670' 0.01-100 Yes 17 1T/2T Cond. Pumps Area 656' 0.01-100 Yes 18 1 T /2T RFPT Area at Reactor Bid a Access 676' 0.01,.100 Yes 19 1T/2T Air Ejector Room 682' 0.1-1000 Yes 20 1T/2T Feedwater Heater Area '" 699' 0.1-1000 Yes 21 1T/2T Rx Recirc. MG Set Area 729' 0.01-100 Yes 22 1T/2T Generator Bav Area 729' 0.01-100 Yes 23 1T/2T H&V Equip. Room 762' 0.01-100 Yes 24 1T/2T Turbine Front End 729' 0.01-100 Yes 25 1 R/2R Resid. Heat Removal Area ,645' 0.1-1000 Yes 26 1 R/2R TIP Drive Area 719' 0.1-1000 Yes 27 S&A Bldg. Entrance to Turbine Floor 729' 0.01-100 Yes 28 S&A Blda. 2nd Floor Corridor 691' 0.01-100 Yes 29 RW Corr. Pers. Access Area 646' 0.1-1000 Yes 30 RW Opt. Surveil. Contr. Area 646' 0.1-1000 Yes 31 RW Corr. to Collection Tank 646' 0.1-1000 Yes 32 RW Controlled Zone Shop 676' 0.1-1000 Yes 33 RW Control Room 676' 0.1-1000 Yes 34 RW StoraQe and Equip. Area 676' 0.1-1000 Yes 35 RB Sampling Cask Storage Area 818' 0.01-100 Yes 36 RB Railroad Access Area 670' 0.01-100 Yes Page 7 of 16 Emergency Plan, Rev. 62, Page 152 of 295 .* -EndO$Ute 4 to Appendix D (Cont'd) AREA RADIATION MONITORS (,ARMs) Location Range Local Channel# Building and Area Elev. (mR/hr) Alarm 37 Standby Gas Treatment Room 806' 0.01-100 Yes 38 Control Structure Rad Chem Lab. 676' 0.01-100 Yes 39 Control Structure Control Room 729' 0.01-100 Yes 40 S&A Access to Unit 1 Turbine Bldo. 676' 0.01-100 Yes 41 RB Tip Chamber Shield Area 719' 100-1,000,000 Yes 42 RB Refueling Floor Area 818' .01-100 Yes 46 (43 U-2) RB New Fuel Storage Vault 817' 0.1-1000 Yes 47 (44 U-2) RB Spent Fuel Pool Area 818' 0.1-1000 Yes 48 1 R/2R HPCI Pump & Turbine Room 645' 100-1,000,000 No 49 1 R/2R Refueling Floor Area 818' 100-1,000,000 No 50 1 R/2R Control Rod Drive North 719' 100-1,000,000 No 51 1 R/2R Control Rod Drive South 719' 100-1,000,000 No 52 1 R/2R RWCU Recirc. Pump Access Area 749' 100-1,000,000 No 53 1 R/2R Access to Remote Shutdown Panel 670' 100-1,000,000 No 54 1 R/2R Fuel Pool Pump Room 749' 100-1,000,000 No 55 1 R/2R RHR Room -Loop A 645' 100-1,000,000 No 56 1 R/2R RHR Room -Loop B 645' 100-1,000,000 No 57 1 R/2R RCIC Pump Turbine Room 645' 100-1,000, 000 No Page 8 of 16 Emergency Plan, Rev. 62, Page 153 of 295 Endo$,-ire 4 to Appendix:
D (C()nt'd.)
... ii*' PROCESS MONITORS I S~stem I Det. T~~es I Range I Location I Main Steam Line ION 1-10 6 mR/hr Near main steamlines Chambers between primary and (IC) secondary containment walls, just downstream of MSIVs Refueling Floor Wall GMs O.Ol-100 Exhaust ducting upstream Exhaust Duct mR/hr of inboard isolation damper, prior to discharge through reactor building vent Refueling Floor High GMs O.Ql,.100 Exterior to fuel pool Exhaust Duct. mR/hr ventilation exhaust duct Railroad Access GMs O.Ol-100 Exhaust duct prior to Rx Exhaust Duct mR/hr buildinq vent . Emergency Outside GMs O.OI-IOO
* In the outside intake air Air Intake mR/hr plenum Offgas Pretreatment ICs 1-10 6 mR/hr Discharge of the delay (SJAE) pipe after SJAE Liquid Radwaste Scintillation 10-10 7 Off-line on liquid waste Effluent (SCIN) cpm effluent discharge Service Water (FPC) SCIN 10-1 -10 6 Downstream of fuel pool cps HX prior to discharge to coolinq towers RHR Service Water SCIN 10-1 -10 6 On the downstream piping of each RH R HX cps RX Building Closed SCIN 10-1 -10 6 Suction piping of the cpm Water RBCCW pumps Standby Gas GM O.Ol-100 Inside exhaust ductwork Treatment mR/hr SGTS Vent Exhaust Containment Monitor IC 1-10 8 R/hr Drywell Page 9 of 16 Emergency Plan, Rev. 62, Page 154 of 295 ~* -***** Enclosure 4 to Appendix D (Cont~d.)
___ -.. . VENT MONITORS . . . I T~ee I Minimum I Location I SCIN 1 o-6 micro Ci/cc gas. Five locations in turbine building, reactor building, and SGTS vents Iodine Sampling NA* Cartridae Particulate Filter NA* # VERMS use Solid State detectors.
* Sensitivity dependent on sample size and count time. Sensitivities equal to or better than 10E-11 micro Ci/cc are achievable.
Page 10 of 16 Emergency Plan, Rev. 62, Page 155 of 295 __ ,,. ,, ,, --_ E~~losure Sto Appendix b ' ENVIRONMENTAL MONilOIUNG SYSTEMS --11. Environmental Monitoring S~stems I Instrument S~stem I Individual Detectors I Pur~ose A.. Radiological off-site fixed air sampling sample particulates Environmental stations sample iodine Monitoring Program direct radiation monitor measure gamma dose (REMP) System stations (dosimeters)
B. Analytical Facilities near-site radiation radiochemical analysis of chemistry laboratory*
environmental and bioassay samples off-site environmental analysis as above, and also very contractor**
low-level activity analysis
* Near-Site Radiation Chemistry Laboratory; used for effluent, reactor coolant and primary containment sample analysis Capabilities:
(1) Gamma Spectrum Analysis:
25-50 samples per 24 hour day; samples may be in the form of water, air (filters/charcoal cartridges and gas marinelli beakers) and other free-flowing liquids. (2) Liquid Scintillation Analysis:
25 samples per 24 hour day; samples in liquid form. Equipment:
(1) Intrinsic germanium detector with associated electronics and computer system. (2) Liquid scintillation detectors.
** Off-site Environmental Contractor (Teledyne Brown Engineering, Inc.); used for post-accident environmental samples Location:
Knoxville, TN. Capabilities:
(1) Gamma Spectrum Analysis:
50 samples per 24 hour day; samples may be in the form of food, milk, water, air filters and charcoal cartridges.
* (2) Gross Alpha/Beta Analysis:
50 samples per 24 hour day; samples may be in the form of air filters and water. Equipment:
(1) Intrinsic germanium detector with associated electronics and computer system. (2) Liquid scintillation detectors.
(3) Gas proportional detector.
Response Time: (1) During normal hours staff existing at facility.
(2) During off normal hours two hours following notification.
Page 11 of 16 I I Emergency Plan, Rev. 62, Page 156 of 295 Enclosyres t<> AppEincli)( D (Coritr<).)
__ ---J:NVIRONMl;NTAL MQNlTOR.ING SYSTEMS 2. Typical Radiological Monitoring Team Equipment Emergency Planning and Grid Coordinate Maps Stopwatch, tweezers, masking tape Gc;1mma Survey Meter with current calibration Low Volume Air Sampler and Head Potassium Iodide Tablets Radioactive Material Stickers Particulate Filters, box Silver Zeolite Cartridges Disposable Plastic Gloves Plastic sample bags and labels Flashlight Spare Batteries Portable Frisker with Probe 3. Typical Emergency Environmental Sample Kit Contents Assortment of Sampling Bags
* Flashlight Grid Coordinate Map Electronic Dosimeters Pliers Page 12 of 16 Plastic Gloves Sample Containers Sample Labels Scale Scissors Spare Batteries Emergency Plan, Rev. 62, Page 157 of 295 ENCLOSURE 6 TO APPENDIX D Typical Radiation Protection Van Radiation Emergency Monitoring Equipment Survey Meter with current calibration Portable Frisker with probe Low Volume Air Sampler with head (AC powered) Low Volume Air Sampler with DC power plug DC to AC Inverter VHF mobile radio , Respirators Iodine Canister Potassium Iodide Tablets Sets of Anti-contamination Clothing
* Disposable gloves Calculator Frisker Check source Silver Zeolite cartridges Particulate Filters Tweezers Page 13 of 16 Stopwatch Masking Tape Microfiber Wipes Smear Papers Plastic bags for samples Extension cord Work light Flashlight First Aid Kit Spare batteries Safety Vests Gamma Survey Meter Check Source Emergency Plan, Rev. 62, Page 158 of 295 ENCLOSURE 7 TO APPENDIX D Emergency Classification Dependent Instrumentation Vent Stack Monitors Meteorological Tower Indication Airborne Sampling System Liquid Radwaste Sampling*
Liquid Discharge Radiation Monitors RHRSW Radiation Monitors SW Radiafion Monitors Spent Fuel Pool Level Indication Area Radiation Monitors Refuel Floor Exhaust Radiation Monitors Primary Containment Isolation Valve Position Indication Reactor Coolant System Sampling Reactor Pressure Vessel Level Indication (Fuel Zone, Shutdown Range, Extended Wide Range) Main Steam Isolation Valve Position Indication Main Steam Line Flow Indication Main Steam Line Tunnel Temperature Indication
* Drywell Sump Level Indication Reactor Building Temperature Indication Containment Pressure Indication Containment Hydrogen / Oxygen Analyzers Containment High Range Radiation Monitor AC Power -13.8KV (Downstream Loads/ Breaker Position)
AC Power -4KV (Downstream Loads / Breaker Position) 125 VDC Power (Downstream Loads/ Breaker Position)
Nuclear Instrumentation (APRM, SRM) Suppression Pool Temperature Indication Suppression Pool Level Indication Reactor Pressure Vessel Pressure Indication Drywell Equipment Drain Tank Level Indication Offgas Pretreatment Radiation Monitor Seismic Monitor Instrumentation Station Flooding Instrumentation Simplex Fire Detection Reactor Coolant System Temperature Indication Reactor Building Sump Level Indication Reactor Protection System Trip Indication LRW Collection Tank Level Indication Main Condenser Hotwell Level Indication Page 14 of 16 Emergency Plan, Rev. 62, Page 159 of 295 ENCLOSURE 8 TO APPENDIX D Typical Emergency Equipment for Initial Incident Response Portable frisker with probe Low volume Air Sample with Head Gamma Survey Meter Particulate paper filters Silver Zeolite Cartridges -Spare Batteries Portable Worklight Self Reading Dosimetry Potassium Iodine Tablets Anti-contamination Clothing Full face Respirator Iodine Filter Canisters SCBA Equipment Emergency Plan Emergency Plan Position Specific Instructions Emergency Planning Map with offsite sampling locations Onsite Monitoring Locations Map Food and potable water adequate to. support 10 people for 5 days. Typical Technical Support Center Equipment Plant Technical Specifications Operating Procedures Manual Emergency Operating Procedure Manual Final Safety Analysis Report EP and EP-PSs Safety Procedure Manual Offsite Dose Calculation Manual Plant as built drawings Emergency Phone Directory Copy Machine and Telecopier Page 15 of 16 Emergency Plan, Rev. 62, Page 160 of 295 ENCLOSURE 9 TO APPENDIX D Typical Emergency Operations Facility Equipment Plant Technical Specifications Operating Procedures Manual Emergency Operating Procedures Manual Final Safety Analysis Report Emergency Plan Emergency Plan Position Specific Instructions Current Emergency Plans for PEMA, LCEMA, CCEMA Rad Health Handbook Offsite Dose Calculation Manual Emergency Phone Directory Emergency Planning Map with Offsite Monitoring Locations Calculators Flashlight First Aid Kit Page 16 of 16 Emergency Plan, Rev. 62, Page 161 of 295 APPENDIX E Susquehanna Nuclear, LLC Policy Statement:
SUSQUEHANNA SES EMERGENCY MANAGEMENT
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.. Steam Ele<,:tt1c*
Stat1on.sliall
*be .. the*resmms1b1l.1~pfJlie
.. f:>S~s Eif}ir~ei1~tPiJ:~.ctqf~1!!i//R\iey~a;qf tJt!s{1iiti:\iorj .t>~\tJi~iR~c.S?t~ry t4~~!lg~r,:
;tff e:;iiiglv,idu~Js'Yfliq, ~pa,\lJ\:Cf.tn:tb~$.a,pa,s\tyo.~~S,~~.~11wrgenfy*NlmJ!l~~1.:sa,re*pt*-~!'.~/!1.e.(!asfoJ!o:w,s,t JJPiri.&#xa2;~i~t?ii.~PR-r.-*t!iif'o~s1)i'r~nc~Ji(,~~te.w~rlt~h~&#xa5;*
th~,:&sect;h)NM~rt~~f
;~11,'_~,lJfX
.... !!lH!1~* Af~tJ9J:!'S,\!~!
I: !l.~~~IP:~ .H.1.~* rq_le,oJ~~E,~.
Ewcr1:;~ntJ~
D1rec!9v, -~s*dc~~obr:_d
*m a11!'fSSES;EiJ.'lel'gen,cyJ>(ap';)111til\'~liev~JI:&t:!t~arte"spon.siJlility bft11~'.Em~rge&#xb5;cy
,.J?:irfc.!.e~J~flftsi!~~ig'hll~~;.~IJ~m.~t~;
' .. ,. . , , Jf:.t!1f~(n~tg~n&#xa2;yti'~:cf~'(r&#xa2;:l'it!itiY#ti&sect;tj'.'&sect;ftli~l)!1&#xb5;,~f
*,.('.jp9t~ti~1r~:i::k~i1fw;cik\i>; ,Ht(l'S}3~$~ecqy~1fijal)agerjhaJl1ll$~1)lne:r~sp
{jfy'.for9vernUJllat\llg~1~!:)tit'
~ftli~'e'inc'fg%6fiirti(offisite"i>r6tid:i(x~,J:\s:tfo,i
,. '*11h~1id}i:tions5
:tiiC:ssES/'
1~aj'.erg~i}&#xa2;Y'li>Jfi;ct9t11'9.t@1nst~~pQnsitiillW.f<>j'.ptfrsit{~9p_e)'attO:n~;
The'S.SEs*E_m~~enpy:MaiuigerslsliallJi.1N~lnenfapP;liG&P!~'.p!'irn~~if&ftJ1,~iSS.ESEiiJ~i~op:9fJ!l&i;l;tc>.'
l~~Y.ehHl'.'*!tJW~t1:,t~:9?~~f~~~~' . . . fin~{~;;nfi2f~H 11 f ~Hf9l!ih11~~1~s.r~~l~,~!e8ttie1~!,~tJ?:1.J;J;PYt
~!JgJL.havethe autHontyJo*aqto~n. , *of Susqueli'an~a\NucJea!;
1 ,}J1,Jk1n ,a!! \llll1t(l!'S,'Com:er11111~*l&#xa5;1
&sect;n:\'t:~g~h9$:,,~!*leJisJ;u,1itiJ.~&#xb5;c_liJ!;ntfas'!J1cJ~cojic,.*$r;iV1rit)'.
1;aad.:p};\t<;lnJi~l*1'.a4JRl~~jci!}**c&#xa2;'J!s~q\!i;!1~.~
J}ti-1'{,.
bccn:assess.ed, and'the appropria:te,p
* * . ive aua corrcctiveactioni;,fiave been itnplemented
.. *ronowing, *r::~:m;:~r:;!;th~~;;~~;i11~:'.:r!5fi:J!f
~!~1.;~1~~tf!'~;,:.f t~ii;;i:!~1s1ons:and Corporate IhfoutJfotitJlf~):9f1rs:e~o'f'~{\'.elhetge11~y;c<>..@J~ionfat12&#xa2;.~P~1'ls~:an~
siippcirf\\YiliJ@lff.'Withio.ti11a1'
~!1~gtjc!l~h.h,aJ~ti&#xa3;li:!!!l',&#xb5;J..p.I>fgaj1j~~ti9,!l;sMIJ
;~,c;prqxi~~d
'af !h~,r~q\1q~_tqft!11?;$S!?,S.*13.~~l:g~!1Pr.
fl'I,~a~~r,i~.
Page 2 of 2 Emergency Plan, Rev. 62, Page 163 of 295 APPENDIX F DEVIATIONS TO NEI 99-01 REV. 6 Page 1 of 2 Emergency Plan, Rev. 62, Page 164 of 295 Susquehanna Deviations to NEI 99-01 Rev 6 INITIATING CONDITIONS and Emergency Actions Levels As documented in SSES letter to the NRC dated October 15, 2015 Susquehanna Steam Electric Station Proposed Additional Changes to the SSES Emergency Plan Basis Document Since Submittal of Response to NRC Request for Additional Information
-PLA-7399 Enclosure 2, SSES took no deviations from the generic NEI 99-01 Revision 6 guidance.
That enclosure provides a list of the SSES differences from the NRC endorsed guidance given in NEI 99-01 Revision 6. Page 2 of 2 Emergency Plan, Rev. 62., Page 165 of 295 APPENDIXG SSES EVACUATION TIME ESTIMATES ORIGINAL DOCUMENT ISSUED 11/2012 Page 1 of 23 Emergency Plan, Rev. 62, Page 166 of 295 NOTE: The information contained in Appendix G is a copy of the executive summary of the November 2012 Evacuation Time Estimate.
The entire Evacuation Time Estimate can be found in the Susquehanna*
Information Management System which also stores the annual reviews. Page 2 of 23 Lesa11d * -SSE$. GJ t,;1'1 Emergency Plan, Rev. 62, Page 167 of 295 sustruehatu:,a'.5team Electric Stiitfon Development o/Evatuci't:ioh Ti,:ne Estimate$ , -::, .'l,~,,:fo'MlfeJtit'l~s:
,;;~:~,~~.~
....... **"T"'&deg;'~~
,. tl~t"''~**~~.o!i'!'t\i\!t4_:._-..,fr
.... ..: ..
* Page 3 of 23 l<l[? Engin:e~riQg, Fl,C 4/fcorpor~te .1-1aupp,1uge, NY ~178~ rnailta:~weinisch~RIQtornpa~ies:d5itt Final 'RepQ!'.l:;
Rev. o .KLDTR,-,,527 Emergency Plan, Rev. 62, Page 168 of 295 EXECUTIVE SlJMMARY This r~p.otJ de~c_itbe~
th~ a11~lys~s 1;mqertaken an&#xa2; th~ resu_lts qbtaini:g by a st_udy to develop !:v.:louat'i\.'.m Tirne Esttm.ates (i:tE) fqr tbe susg1Jeb~nna
-'$te.c:im Electri~ St1=1tion. (S~ES) _lqc:atec,I in Lu_zerne.
County, P~nn:sylvanh;i.
ETE are. part bf t!ie t~qulred planning bast~ i;'IOP prov'iqe PPL Susquehanna, LL&#xa2; {PPL} a_nd state and iocal governme)ils with $ite-specifi'c inform*atloh needed for Proted~ive Action t::!e.cisi6ri:-fi1ctkJng.
In the. performance of :this effort, guici:ance i,s provided b_y tjoc;ur:nent$_
p&#xb5;t)lishecl
~.V feperal Goverrn:nental agencie$, MP.st 11:nportant pfthes&#xa2;. are: *"!' Criteria for Dev~lopm~tif of Ev~r&#xa2;l!afief;l Tiri'le _E$tiii'Jat~
Sti .. iclie~,-NUREGiCR;,;7.002, November 20,11.
* Criteria for Preparation and Evaluation or Radiological Emergency Response Plahs and Preparednes$
ih ~t,Jpport of Nl,.iciear Power Plants, N_URE~-'0~54/F~MA-REP-"1, Rey. *1,. l\lo_y~rnp~r*
\QSQ.,
* Deveiopment of Evacuation Titn.e Estimates fo,r Nuclear Power Piants, 1 NUREG/<;R-6863, January 2005.
* iOCfRSO, P,ppenc!ix E --"Em~rije11cy Planning a_nd .PrepareQriess r.or "f?rod!-Jd:ion c1nd iJtilizatio*n F~cIH.ties;'
Overview of Project Activities This project began in March, .2ci'12 and* extended over a pefiod of 6 m.<;mfhs.
The major activities perforriled ar~ briefly described in i:hrpriqlpg_ical sequen~e:
* Attende_9 "kh::k.:gff'; -J'.Tleetin~s )Nith PPL personnel. Acoessed us. censtis Bureau data files for the year 2010. studied Geographical tiiforrnati.c>r)
Sy$terns (GI~) maps of the area *111 the vicinity of the ssEs, then cohducted a d~t~lled fie.ltj SJJJYey of the hrgliwav*he.twotl<.
** Syrrthesized this information t.o ,create art ;:i*nalysis network representing the highway system. topology and ca_pacities within the Emergency Planning.
Zone (EPZ), plus a $hadow Regi_on. covering t!i~ r~gio_n petyVeen the EPZ bo1Jiidary afid ~p'5roxlm~teJy 1.S rnilE;!s r~diallyfr9m the plant ** Designed and sponsored a teiephone
:survey of reside*nts within the EPZ to gathe*r focus~d dat~ n$ecjed fo'r" :'this ETE sh.iqy that Were n.ot contained within th&#xa2;. census ga;tapase
... Th&#xa2; survey l!Sed wc1s .caf-ried o~t in ~Ob~; it is s:tHI valip -~JnC:e tl)ere !titl~ riot been a sfgnffic;:i-rit change in EPZ demogra,phri;s.
Ttu~ .survey Instn..1.rn~nt hi:!cl b.~en tevlewed *and modified.
by the Hcensee. and offslte respo.nse organization (ORO) persotinel prior to conducting.
the survey. * *
* Qata <::oJle.ction
*forms (provided to PPL ,at the ki.cko:ff' rn~etfng}
w.en~ r&#xa2;t!-!w*ei::J wtth dai;:1 :susqueb<!nna Stearn ElectrTc:,si:atlon Eva.cuc1ti<;m, T1(ne Estin\f.Jte Page 4 of 23 KLD.Engfneer(ng, *p~c.. R'~~,o Emergency Plan, Rev. 62, Page 169 of 295 "t>ertairiingto el;hJ>Jo:vment:transl~nts.,.-?l'i::itf
$peti.fli fa(#liHes in e~chc;:o.unt\i\
lot. The, t~affi~ 't;ietnan#
~nd ttn,*,..g&#xa2;neratf~IJ rates of :eva~uating vehicles wer$ ~sti.mated ffoiil tl-te gath&#xa2;red dci:ta. Thf ttip g~neratioh rates refle*cted the *es.t,nlatetl mohJJizat,on tlrrje {i.~~, the Hroe. re~yired :by eVijCUees to prepa:re.for the ~V~C\.lcltit.>li1:rip}
cpmp1,1\ed.
l,JS!Og the r&#xa2;suft~ O:fthe,,folephone
~urv,ey of EJ?Z* resi.det1J:s~
*~ Fo:l!9wJrig ,t~defi:ll gt.lid~lines, .the ERZ is su.btJiVided int9 .27 EfWA. Tf.l.&#xa2;se gFWA qre tfi'.en ~XC>l!peg Within circular :area$ or '-'keyhoJe" cdnfigu*raj:igns (circte$ pl&#xb5;S. rc:1dj~! ,sec;tpr:,s.)
tliat.deff'ine,cttofal of30 Evacuation Regions; . . The time.:.v~ryi11g
:e~tt:?rna*I ctrtQl'nsta.nces
~re r.ept~~e.nte*(l as, Ev~cuafipr)
'Sc~nqd_Q~, 'e~~M described in terms ,of tl1e foll&#xa2;Wing t'~c.to($:, .<:i) $e;:!s'Qn
{S1,.11:nmer, Winte*r); (t) Day of Week (Mi.dW~.$~;
W&#xa2;~~e.np.);
{3) Ti.rfre qf D~.Y (Midday, ~vening);:
at)d (4) VV&#xa2;ath~r (Good,, Rc!in, .snow). On~ .s!J~tial
~~e.nt sc$,:i~ri.o
*"' r~fl!f;lir'!$
at the plant.~ w.as consJclei'J;?ct OiW toat::!Wa.Y frtrp:act
*sc~r1arit:>
'vi/1:1s &#xa2;o*nsiderecl Wherein *.a .sing'!<=*
lane W9S elos&#xa2;d 'on li1t'.erst'at1?
BClWestbot,111(:f forthe,.clur-ation .ofthe evacuation.
e Staged :evacuatiq'ri was. c:ohs(&#xa2;lered f9r* tho.se regiens wherein the 2 mite rtfoius and ~eC!;,t:>rs dowm.lliinti to 5 miles Were ~vacuated.
* e As.p.er NJJREG/CR-.70P2:, *ti)&#xa2; phfn'J:Jihg bi:is:i~:for the:taltuli:i;t:ion of ETE 1$:
* A rapi&#xa2;ily esc,~li;itibg a~citjent at. ttw S$t:S th~t qqici!<ly assJ.Jrn~$
fhe-5-tatus. qf Genei:al Emergency s.uch tha.t the AdVi$pry to i:;.yc:1q.1qte
*.is virtuclfly c:(l)jnc:f<;tt;m{
w'ith t!'ie siren alert; ;;ind no i:!ar:ly protective actions hav~ been in.1plernented.
11 While ijfi u(iliki;Hv
'a<;~ident
*$ce.rnirto~
l'1i$ r,t~ilri!ng RcJsis will yield <ETE, meas*ure'd Ji$ the ~IJipsed tim,e from tbe Ac:{vtsory to Evacuate i.mt,il the. *stc1te.d percr.entage of the popufatlon exits *the 'hnpa.cted Regibr'I~
that repteser1t
;'Upper bound'' estimates.
This conservative Plannlog Bas!$ is.appiicabt.~
for all rnit1~tii,g.*eve.o:ts.
*~ *1fthe emerg~ncy occurs while .schools are *;11 session, the .ETE *st&#xb5;dy -assi.Jmes th"qt tbe children wiil pe *evacuated
'by bus dfr'e*ctry
:to rec~ptibh cente'ts or f,qst sGhoois
* loc~iteg outsige fhe EPZ.. Parents, :relativ~,s; ar,icJ neighbqrs
*~r~ ac:ly-ised to Abl pick *up tht?ir thJlc::lre'rl atschootprctortothe*c1rrh,1al of the buses dispat~he:d for thclf,purpose.
The.ETE for scihoplcfiildren are' calcu'lated s~para1;el:y. . ~* EVc!tlu.ees who. dq fiqt hav&#xa2; ~.c~.e$S t.Q a priv~te v1;bitle; w.ill either ride'"'sh~re with .relath,~if, frieni;:l_s or r.i'ejghbors, pr be evacuated by .bus*es provided as spectfi'ed in* the* :r;:01,1ntY ,i~va.t:&#xb5;at,{ob pl~ns*~ Those *in ,~pecial.
fad!itie'.S wOI lil<eWi.s.e b~ evac;.U~t~d with 13t1blic tr.~msit, :as needed: .. b.us~ van, or ,ah1bularwe, as requJrecl.
Sep.arat.~
'.~TE ate qalculated for .the transft'-dependent evaeJ.i~es;.
'for hortrebounci
*spetrsil
*needs pqputatJ01\
arid 'fqr:thos~
eva*cua,r~dfrqr:r1 specJ~I fatiliti~&
Cbniputa'tioh Of ET!: A: t.Q.t.a'l of'420 ETE w~fe ~omi;>Jtt;et;:l.lo.t th.e.evc!i;l}Ati9n ofth~*g~neral pt;ipljc;.
Each ETEqu~ntifi$*~
the aggr~&at.e* .evac,uation time estlmate*&#xa2;1 fpr the pQpLil~.tion Witlt!Jn ~r:ie of the '~O Eva*tuation susquehanna'Si:eam El'i:!ctrk.Sf~tlcnt Evatt;iati9n"Tin,e*
Estima,te Page 5 of 23 KLD Engineerin*g, !':>cc. . . f{&#xa2;\I. 0 Emergency Plan, Rev. 62, Page 170 of 295 Regions to evacuate from tli'at Region, LJnd.er the circumstances defined for one *.of tlie 14 Evatuatic;m S.cenario$
(30 J< 14 = 420). Sepa:rate EJE are calct.Jlc1ted
*for transit-dependel'lt.
evacuee$., inc:l,!.lt!ing school children.
fqr applica_l::>le scerrarJ9s.
Except for ~eg1on RD3, wh/ch *is the eva.c&#xb5;ation of the. 'entire EPZ, only 'a portidn pf the peop_le within the EPZ would be advised *to eva*cua'te.
That is, the Advisory to Ev~cu*ate appHes bn(y"to those paeople otcqpyihg the specified irnpactet:f regidn. lt i$ assumed th.at l0.0 p'er~ent of tile people within the impacted region will evac:uate in r~~pqn_se to this Advisqry.
Th.e pepple occupying the remainder of th~ EPZ q&#xb5;tside the impacted.
region may J;>e advised to t~ke shelter. The computatio_n pf ETE ~~sumes that 20% of th:e population within the EPZ but outsid(:!
the. impacted r~gioi), will elect to !'voluntarily" evacuate.
th addition, 20% of the population in th~ Shadow Region will also ~lec.t to evac&#xb5;ate.
These ,Volur;itar,y evacuees coulo tmp~de those who are eyi:)cuating from within th,e im_pacted regfon. The impedance that .c;:ou!q be. e,au.$ed.
PY voluntary .evc1cuees is. considered in the computatidn of ETE for the impa.ct!:id region. Staged &#xa2;vacualion is considered wherein those people within the 2~mil_e, r~gion evacuate imfr1ediately, while ;those beyond 2 friiles, but Within the EPZ, shelter-in-place.
Once 90% of*the 2-mile region is evacuatecl,, tho$e peopl~ bey9nd 2 miles. begin to evacuate.
As per federal guidance, 20% of pe*op!e beyon.d ~2 m'iles will evacuate (noh-,complianc!:!)
even though tt,ey are advised to sh&#xa2;1ter-in..:place.
The computatio'nal procedu*re is outlined as follows:-* A. !ir:ik,*n6ge representati<;>n of the highwa_y network is c9ded, Eac_h link re.presents a unidirec;:tional length Qf h\ghway; each nod~ U$Llally repres&#xa2;nts a*n intersect{Qn or merge point. the capacity of each linK is estimated bpsed qnthe field .survey obsexvations and on establishe.d traffic en&ineedhg procedures.
* The *evacuati.on trips are generatep at loc~tion~
~ailed '~zq_nal centroids" located within th~ EPZ ,anc;l ~haqc;>v,., Region. The trip generatJon rcltes vary over time reflecting the mo:biUzat:ipn prp,cess, anc:i ft9m qne location (centrdid) to .ar:iother depending 9n pop4latton qensity and on whether a centroid is :within, or outside, the impacted ar~.9.
* The evatuati9n model computes the routing patterns for evacuating vehicles that ar~ co,mplia11t
~ith federal g1.,1idelines
{ou.tbo_und relative to the loc~tion qf the_ plant), then simulate the 0 1::raffic flqw movem*ents -over spac.!:? ~.nd time, This sim.ulation process estimates the rate th<3t traffic flow exits the impacted region. The ETE statistics
*provid_e the-elc)psed times*for 9P percent,c:1nd 100 percent, respe'ctively, of *the population wittiin ~he impa:t~e*tj fE::!gi0,n, t.o ev~c1,1a~e from within *the impacted region. Thes&#xa2; sta~tstics are presented
'in tab\,lla*r and graphical formats. The 90th perc~ntile ETE have 1:;u:~tm :.idenllfied as. the v1:1lues that sho.uld be considered when makfng protective
_action dec::lsfo.11s b~cause the 100th percentile ETE'. are prolonged ,by those r,elatively few peo_pl,e who take longer to mobilize.
This-is referre.d to as the ;,evacuation tail" in Secti9h 4.0 of NUREG/CR-7002.
The use* of ,a p&#xb5;blit: outreach (inf9rm~tion) program to ernpha!?ize the n~ec;l for evacuees t;o '$*&#xb5;sq*u.&#xa2;ti~flri,a*st~<:1rh' Electrjc Station Evacuat.ioil Time ~sth:nate Page 6 of 23 KLI? Engirie.etiiig; P,<;.;, ,Rev .. o Emergency Plan, Rev. 62, Page 171 of 295 :nilnh'rl\ze
:the fime neede.d to pr&#xa2;pare to *ev 9 cJ1at$ (secure tlie' home, assemi;>le )ieedep Qloth&#xa2;.s, rhedi(3i1Jes, etcj shou,ld a'lso be :c:di1sidered.
**
* Traffic"Ma nagement This ~t1:ray 'r~fer~nces'th.~
.. compreher:isive traffic *mar'."!agernent Ji!c:1t1s l>r9vi&#xa2;Jeg i.!1 the. l1,1zer'1e c;1nd Golurribic1 Coqhty Radiolo*gn:;af Er:netgency
*Res,pohse Pl~mt; DQe :to :i;h~ detcli.l~d plans alreagy in place anc;I :the liro,iteq tra.ffic .00.ngesficm within the E'iiZ~ no c1_<;!dltfc:m~I trclffil1.
o.r c1cce.ss torifroJ me*i;J.$1,Jr~J>.
fta.ve l:>,e~)1 jd~('ltj.fieg as a .result of th:iS-$tJ1cfy.
Selected Resuits .A &#xa2;Pl'lJp'Hatien of :!?ele~te'd information 1s* presentecfon.
the raff owing pag~s ih :th~ fqrm 9f figures and tables,,exfraotedfronvth~
beiqy qfthe report;-these a.rn des1:db~,;f6ek,w~
*
* Figure Ga. qis:plays
:c;i map ,of th~ SSES EPi showing the foyot{t of the :27 ERPA that co_mprise, Jn .c3ggtega'te, the E PZ~
* Taole."3,.1 preienttthe estirnat~s.,qf perm'ah~t:ri:
r.~sii:lgnt.p'p,p,t,il~tJc;m ,iii eac;:h EilPA based. 011 the 2()'.1,0 c;::~nsus Qi\ltiJ.
* Ta pie G,.i d&#xa2;fine~ ea&#xa2;h of "the 3Q .l;v~t:uatipp .R,~gions Jn terrri's *of1:.h~ir respec~)v~
{i!rot,Jps 9f):RPA e Ta.li>J~.6~2 li~;-:ts the Ev~u::&#xb5;atic:,fi.Sc~riari.0$:
e Tables 7-".1 ant;! '7,~z are c*orn_pifations of ETE. ihes.e da:t:a are the* times neeclt:?ci to *cleat th~ *indic:.ated regions of !'Jo <!nd 100 per:-cer:it of the pqpulation oc_cupvlng these reg;on~~ respectiVe!y.
The,$e cor'npf.!tet;I ETE. include Cl0l1$ideration t:>,f hit;>biliza1:ioh
*tim.e anc;J q.f est)rt;cft;ed volunt~ry evacuati.ons from o.ther regions wi.thin the EPZ. an.a froni the Shadow Re.Jtlon.
* T,tbles 7,,.3 and ?4 preseflts ETE for the 2-mile reg19n *fpr u.ri-is.tag~q.
i':l)'l~ :$tEige,d .evaGUations for th~-90th and 1od 11 p~rcentHes., r'espec;tivf!ly, * -T~ble at:1 pre,sents.
ETE for the schoot*cfiil~i;'.en.
in ~qptd weqther.
* Taple 8-11 *presents .ETElor th'$ tfansit,-depehd&#xa2;nt*populatiofl in gooc:J W~~th~i'\
o FJgure H.:,8 presents-ari example of "'clii E\iEicu~tion Regi911 {Regicm R08) to pe eV.acuated lih~er the circumstances defined i11 Table 6:,1. Map*s .of ail regJo"n~$
are prdyiqed in A;pp~ndix H. Gonclusiohs 0 General popLJiation E"tE were c;Qmputed f.or 420 ;~miq1,1e .c;9ses --a cQ!Tlbinatiqn
<;>f 3.0 QnJqU{= ~Yc3Cll.:tfion R~glon;;;
and 14 .unfque ~v~t:ua(i<>n Scen~rk>$;
Table 7 ... f .1:lnd Table 7-2 (.fo_aurneot th&#xa2;s~ ETE for the 90th, and *1ooth per&#xa2;entifes, Thes~ ETE r,ange, frprn ltt'J.0 'thr;mtn"}
tQ 3:.35 ~t the ~(t" p*er:c;:entile . . -~ inspection ,ofTable 7,,1 and Table 7-2 ir.td'i'cates*th~t the ETE for th~ 1()0.tli ,pericentile qfe* slgbificantly kinger than those for the *9ot 11 percentile.
This is the resuft of,tfie rei~tively, lohg: mobillza,tion time of.,a small proportion
'of the resideht .popu_la"tion anq c:ongestion withii'i the EP~, When the sy/ifem o~~omes c9fc\g(;1$t~cJ;:
thiffic exits the EBZ at rate~ ~ptriewhc1t 1 1:ielow capacity until ~c;;>rne e::v~-~~ation r<;>u'l:&#xa2;$
h'ave cle;::ir~<:f.
A~ f!Jpf~ routes susql,iehahna S,tearn ,Efectrkshltfcm 1:\(it_u~ii&sect;nfim*ei:~1:ihiai:~ . . . ., . Page 7 of 23 t<LD ~tjiif,neer:inei t{c, *--'Rev. .. o Emergency Plan, Rev. 62, Page 172 of 295 #leat, f!:re ic!ggreg<'\te
*at~ -pf *egr&#xa2;ss slows sirrc:e ntanv-vet;iicles have already left *t!ie EPZ. Tow.ards -the end of the J>rocess, relativelf feW .evacuees
{those with the 'lqngest mpl:>"lliz~tJo:n
'tir:rte~_)
travei 'fr~ely out,of the EPZ. See F.itsJJres 7.;8_fhr:ou~h 7..;21. * *
* lo&sect;p*lqtion .of Table '7-3 and Table 7;.,4 indicates that a s.tageq evacuation proyiges no ben!;;!fits to evacuees from within the 2 mile regip-n an_9 unnecessarily d~J?IYS 'the evacuation ofthos~ be'yqrid 2. niile~,(compare Regipn*s R&deg;7$ th,rpllgh R30 an~l. R,egioris R:04 tHrou*~h R08 *and R02, respettiv~ly, in T~ble$7-i s:1nd: 7~2l-se.e Sett.ion 7,6 f9r adgitJon~I t:liS<:ussion, ,,-corr(parisoh .of :Scenarios 6 a"t1d 13 in fable 7-1 iodi<:;att;?s that -the Special tefu~lirig outag~ atthe plar:tt--cities not have a $ignifiqaht impact on the .ETE for the *goth percehtlle.
Seer ,S~Ction 78 for addi:bional disc:dssion.
0 ~ornparisoh of Sc~narr.os 1 ano i4' in T~ble 7-;I. indicat~s
*:thcit*the roadway clostJte"'"" one Ian~-wes.tt,ound qn 1-~Q frcn:n. th~ ihterch~ng~ -with SC 33~ to the i;*pz Qoundijnj *qoes not c,h,.;:tt:)~~
the ETE, incficatinti fhat there is excess Cgpa*ci,ty
*on the highvvay.
See S~ction 7~~.
* Nanticoke City* and Briar Creek Bo"toi.i~h .and Tbwnship are the "rnost cpr)gested areas during *an evacuation.
The iast ro_adway ih the EPt to exhibfr traffic congestion 1s SC 93 . . All Onks within the EPZ are at LOS A (free-:flowing traffjc c:ondith;ms) at 3 hour's and 20 mTn&#xb5;tes.afterthe.-Advisory*to
*Ev~cnate.
See Sectibn *7;3 and F!~L:tres 7-3 throl!gh 7-"7;
* S~par:zj~e ETE wer&#xa2; ,corrfpute,~
for,sthools; m,ed~cal f~c:zlHtJes, tr~.nsit,.d~pendent per$on_s, hpm'.ebpund specic1I n'e~ds persons and c:orredtioh'.eJ facilities.
The average sfrigle;wave ETEforth~se so1,.1rc~s pfe Within a. similar range-as the,gen:eral population ETE-.atthe,.90th p~rc~ntil~.
s~-~ Section $, * ** iable g..,5 indicc:1J~s that tqere *?Jre .enough buses and Wheelchafr vans -c:1vailable to evQcvate the transjt:.dependent population within the' EPZ ih a si"figle wave; however, afd agree*ments with other-cou-nties -Will need to be.activated ih order*to provicle en*o*ugh ambulances to evacuate the bedrid_deri population i.ri-a_ single wave. , -See Sec_:tions
~-4 andB.S;
* The g~nera_l pqpula'tioh ETE at th~ gqth. perce8tile i_s im;,~_11sitive:*to req!:,!Ption,s' jn the base trip .generation time of 4 hoqrs s,nc.e the mobilizatio_h time .of the b1,.1lk of ev~cuee_s
'i$ unqha,ngeg l:>y t_he truncaJJqn.
sere t 9-bie M-L
* Th~ .g&#xa2;ri:&#xa2;r~J popyl_a.:tiqo ETE *is r~ia~_iyely in5,&#xa2;n~itive to the vol&#xb5;nta*ry
&#xa2;v~l:&#xb5;,atlo"r:1'
*of vehicles fri tfle. ~hadow Re_giori (tripliqg the shadow' ,evacuatt:or:i
*pefceotage b.nhl increases ,goth percentile ETE by .s minutes). -See**-ral:>le M,--2. * *
* Popui'ation changes between +30% ,_or -46% are needed to result in ETE chang~~--whic:h meet H1~ cdteria for updating; ETE betwe~n decennial Cens_us_e,5.
Se!E! ::;ection M,3. Sustjuehanf"(a_Stearn Elecfric,St:ation Evacuation Time Est.mate Page 8 of 23 1<Lb:i::ng1n*e*erhig, P.&#xa2;. ' * *Rev,b "U Q) cc CD co 0 -I\.) w " N i.t /!/---~\( . -~, --If**, --: l'i'*~* , L~/ . "-, ,,,/;;k I . ,j'!.'*'t
, ,//,/ I /,:' \ Legend \
* c;? 5SES ERPA ) 2. s, 1.0 M l l e R ing s Susquehanna S t eam Electr i c Stat i on Evacu at i on Time Estimate l 0*~*;9i':t~l! Cc~C'l:: f S~61lf!"'IJt)C.i:
* 11or~*11C.~1fl'ol!
... ""'k l*s:h:u,l\.
'"<1i11C Figure 6-1. SSES EPZ ERPA ES-6 Pop_ulation 2010 2.0 2, 2.1 0i 2 ,041 2.24 1 225 7 66 4.28 7 838 I-1, 4S3 10 1 0.387&deg; 11 646 12 1, 569 1 3 1.166 1 4 1.1S6 *:;r-4.213 16 1.912 17 ---2.188 1s 1.tts 1s--,--679 20 I S.377. 21 10.462 22 5.82 6 n ss2 24 2.324 913 1 , 520 3.088 m 3 CD -, cc CD :::I (") '< "U Q) :::I :::a CD :=:: 0) I\.) "U IOMa .. 1 11 Q) cc CD ->. -...J w 0 -I\.) co (J"1 KLD Eng in eer i ng, P.C. Rev.O Emergency Plan, Rev. 62, Page 174 of 295 Table .3::1. EPZ'..Pe.rmanent Re*sident Ropulation
: 4. ,6 .7 9 .10 :11 13 14 15 l!> 20 21 22 .23. 24. 2~: Sqsqtteharin~
steam Electri<fStatibh
~v~t;:yatib!'J
:rime Esti'.l"!1ate Page 10 of 23 2,117 9,sg* 1;385 .2,:1'05 1,:ti2 609 1,5Q1 ES'-7 .2,024 . .. :2/197 2,04,1 2,241 225 'ii:i'~ 4,287 838 -'1,453 *-10,387 646. 1,569 J,.166 i,196. 4,2'.!,3 .1,~.12: 2,188: .1,iiS' 67;9 s:~11 10,462 5;82.(f 65,2 2,324 *H.73 1,520 .3,08'8 KLb Engineerjng, P.,G.: . . ~~v.o 
-0 Q) co Cl) 0 -N w Re gi on Descr i ption 1 2 3 4 S ROl 2-Mile R i ng R02 5-Mile R i ng Region W i nd D i rection To: 1 2 3 4 5 R04 N NW, N , N N E N E, W , W NW, N W ROS E N E , E , E SE R0 6 S E , S SE R07 s Re gi on Wind Direction To: 1 R09 N R lO NN E R ll N E R12 ENE R13 E R14 ES E RlS SE R16 SS E R17 s S u sq u e h a nn a Stea m Electric Stat i o n Ev acuatio n Tim e Est ima te Table 6-1. Description of Evacuation Regio n s ERPA ERPA 6 10 11 12 13 14 15 16 17 18 19 20 2 1 22 23 24 25 2 6 27 Refer to R01 m ERPA 3 Cl) -, 24 2 5 26 27 co Cl) :::::l (") '< -0 or :::::l ::0 Cl) < 0) N -0 Q) co Cl) ->. -...J 0, 0 -N (.D 0, E S-8 KLD E n g ineering, P.C. Rev.a 
"'U !l.) co (D ...... N 0 -N (.,.) Region Description 1 2 R18 SSW R19 SW R20 WSW R21 w R22 WNW R23 NW Region Wind Direction To: 1 2 R25 NNW , N , NNE NE, W , WNW, NW R26 ENE , E, ESE R27 SE , SSE R28 s R29 SSW , SW , WSW Susquehanna Steam Electric Station Evacuation Time Estimate 3 4 5 3 4 5 6 ERPA ERPA 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 Refer to ROl ERPA(s) She l ter-i n-P l ace ES-9 KLD Engineer i ng , P.C. Rev.O :::0 (D < O> N "'U !l.) co (D ...... -...J O> 0 -N (0 01 Emergency Plan, Rev. 62, Page 177 of 295 ,;~_t;;t,t~:-2, .El(~t-~;3t_1qr(st~n#r*g D&#xa2;fJiiJtfi?ns-.
*. J:. *. *'J*** --'------" ** * -* -. -t* -------! i' i J
* Day of Time of 1 1 S~enario .. Seas_o_o 1_ j, Week .. Day , ~~~ther __ ; _ _ Special _ J i. 2, 7 Winter ;8. 'Wif1ter Midwe.ek ''-!-'**.-
.... -' -.-*: rvm:hiyee k Midweek . *--:~ ~.:* .. Midweek, :weelcen*a ivlldda *-. .: .. ,* y Midda **.*.*. y Midday* L "*. "**-., .' Midday_ *Rain * --t. -*. ;snow __ ,,_.,. *-,, ,Good _ .. ...,. -..'.::*-:. :!': -** '.~ ... Noffe *.*,,*** . .-None Rpad"'(i;!Y IIJ1P!!G~
*,-d:;a,ne; .dc:,~1.ft&#xa2;,Qii i"'a.<tWB -kWit:1I:er*:a~sL1roes th~t s&#xa2;1,odl Is _In :sessJQn {al~o applies to;~pring ati<:J ,a&#xb5;tumn)/Summer'.assumes itfl;;i(scho.ol Js m:>t 1rrsessfon..
* * ****
* _;$1;1sqgeliahfja
~t&#xa2;am ~!ec~rjc;f:~~~tJorj_
ey~&#xa2;i.iatio~
Tim:~ ~s:f1~~t&#xa2; . Page 13 of 23 K(P ~n~Jv!;iefifi~, P,q1 8i!v.o. 
"'U D) (0 CD ...... 0 -+, N w Summer Miaweek: Middciy Reti<in' *Goo.d' Rain :weath'ifr:
'fatile7~L limetotleanfie Indicated Area*of 9a .i>ercent'ofthe Affected Population summer we.ekenil.
i\'iidilav
<,,bod *Rajn Weather :summ&#xa2;r*
* Midw~ek We~kend EvEj~ing.
G<<:Jod Goo,d: Wint.er Midvie'ek Midday .. . Weather
* Weather . Rain Snow* Gl?O,d Weathef-' ,Etitir~:2~flllil~iRegi!in;,:5;.Mil~Regiq~,:~ildEP&deg;t Whiter* Weekena: M1cldc1y*
.. Rain I snow Winter I W,inter. I Si(mmer * . *Midw,eek.'1
*Midweelf I Midweek 1, I We~ke11.d.
Ey~rifog J Midci~y l .Mid~ay, Gpo~ \ Sp~fiai' *1 :it<;>acl\vay
* weatner'.
'Event *. Impact .sot ~?ss . . ;j/55 * * &deg;1"40 1;:45' , .. ,11;4i}. *1
* 1"55 1 "tf,55
* i35 . ., 1*40: -: 'f*45* * '2,;25* : ~-' ,:l'.to* *Ho * . ' 1:55 ***: . ~*:::. ', *. '**)--**'*--*-
-**:;.':***'
.:.: __ ---~ 2-.. _:_**--,,;--;:..._,.;,,',,_
--Si'.:.-:.:_"'"" _ _:;:~~_,;-,.,--.J:_":.!':.
*--.. -* .. '*-"'.:-;:-"*~~.:a~)
___ --~.: .... ~:-,. .... :~-"':,.,'":~:._..
t,.).-_:;'.,......
_ -:*--*~ .. -*~--~~-: 1 Roz I 2:00 .2:-10 .1:ss: mo 1:ss: 2:os ,2:10 2:40 1:ss: .2:00 2:30 *1:ss. 2:os 2:00 ~:.Ro~~ , 0:12~0 . *
* 2~3Q: *.;,~2110'.
< ;. * .2::is:*,:., .. : .if]&sect;',. "0 ::,.,2:2p:
.**, ... :i:~b~ : *'~3-;!J:O
**~: .,:i:{Oi .. )i:lq: *, .t7:.spi ;'; ,;r7"2-:4&sect;;
*.' .. fg~~ <, * **:i:tP, .,:. 2-Mile Region andK~ynoie,tcfS'Mile?
-*~ *~ 00 $ .. :fi.tj~(1
~-j~~;;_:
":)io9G'.i;
:i~'i@i:. . ~~)&#xa3;{i~:~
'"'1r&sect;f ** r.~iif:C:
:J+/-IiiQE~
}.Ji~;2~ :"::j~fsL:i . ~,-:Lli:&sect;ot\:
_).rss:,,:
RQ6. 2:tlO 2:00 i:40 1:40 i:40 2:00 ' *-2:00 2:40 1:40 1:40 2:25&deg; 1:40 1:55: . :i::tiO --*,:@(:*
1,.Ji~A-:~.
:. ,2;09.; i:i(_** Jt~1c*, :Ji;iif :;J2&1{.~
::}JG:f.~
~:)~!9L~~--:]f1[.~:.;::J&#xa5;:~?--)J'~f]:::*:)JO:
-~ *:,@i~:;}~~)if:i.
-*~ S}llile Region 1;ind ~~y~ole'to.*E~i;BQundarj{
::M9:' : , *-Z)o':. * *2:js' .. *1:ss, .' -~;Q~ ... : :c+/-(sf ~~,.}:Jg;*-*
:?::i~~ ,**?.~t;?::*:ff~s;:*:::.t:~mr.
../*:fil~}~~.C::;lqg:*'.
: .J?,tt~]c::tt1Q.
RlO 2:15 't:25 2:05 2:15 2:05 2:i5 .2:25 '3:00 *2:10 2:15 .Z:50 . '2:10 *2:25* .2:15 R~l~ * * ~~::lg ... * . i:2.0;: . _* _ l2:oo .... *: ; , -~:io. :, * ; 'J:~~;-:. ,.::** ~:{o *<. '. :~,::i::29~
: *)~-:~p~ .* ; .~i~Q~' :.* .; .. ":~Jg:_., .*.::: ?}~Q~: C:2:Q~: ... : ; ... * ',t~1~; * *,. : : __ ~19: .** . ..... ;if rJ~.~!:::
*: {~~ri 1* :: 1:ss . . . i:od ?Jtit:\ \::*;.}:~~~~\*:~
r:~~:;;-;
:r::}I}~r;~
r:l}i;r: c::i~tt:,:
r:OQ' * .. ~~~it~~t:)i
\i}f~{::/
R14'. :l::55 ,2:00. :1:50 1:50* 1:50 1:55. 2:00 2:30*
* 1:50 .];:50 2:20 1:50 1:55 1:55. *~ .. jui* :.:: .: :~r:s,s-;
: , * '2::hq, * / . :p:.i~, . '. .. : *hsf:*:: -'.fi;~f2:
.. cr~~X? * ,;:@oL:; :;J:~];,;_~
: i. ?i.=it::* . :.it~f:~ : : ~}if' -: r:::J~cC .. :*:\li(C ~:Jsst: .. R:is
* 1:ss 2:00 t:so i:so, 1:so .1:ss. 2:00* *2:30: i:4s* i:so 2:20 1:so. i:s*s* 1:ss,. r, * *)ti( .. * ,; :J~~~s:<.
: '*.J{o{J [: *, i1r4~;: :: ' ':}if~:;:~
::~:.-f%o\*
i (: .. il~~f-:':
'JJ~1f.. )it32r: i~::Jif: ::~;{~2! . ~Jjl :, ff}~':sf *s * -*1:~~t~~
.. -;:fff * 'R1B 2:0S* : 2:w: 1:ss ,rno 2:oo 2:os: z:1cr i:~O 1:ss-.t:OO 2:30 .2:os .. , .. :J~ .. * * ::.j~3Q*: . 'i4.s:t*-;,**2;20:
i .. *.g~fi \fi:t:gs ..... * :~*~1f;; .. 13-ii&sect;'.i,/
'.. *,?,iip~*-* . :*:ifilo,d(;
'..'2:?0i::;
:R20: 2:3s, 2::40: *2:20 2:30* 2:2s 2:35 2;50 3:1s 2:20 . 3:os 2:25' 2:.30 :2:as* .]i-:-ii****;
:~;** ]l-Ci~:; ]t;J;~;.lt~;;:*
;*%!'*; tikf}if :;;:;.i~.~,];*.
m :Sus.quehanmrSteam Electric,station .l:vacliation~ttn:te:l:jtim~te.
es,1-1 KlD Engjrjeering, .P,C. R~vi o* rn 3 CD ca CD ::i "'U D) ::i ::a CD :::: 0) N "'U D) (0 CD ...... -...J 00 0 -+, N (.D (J'l "U Ill ca CD ....... 01 0 -I\) (.,.) Midweek* Weekend :s_umriler' . . Mid).&#xa5;,ee~
*
* 1 Weekena: Winte_r Weeken'd * .Mid!Neek -Midweek :Midweek, weekend. . --Good, -. .-Good Good -Good -. Good : '.sp* eciat * :_*Roadway*_-.
* Rain R -. ' R __ ill_ *.n. _s_*n_o_ w :,* __ Rai_n_* _ , Weather :W~ather * *. -"'" Weather, WiiatHet _ Weatner, , Weainer-*,event: Impact-. . Good -Stage cl. Evacuation
_+:12~Mlle
~egl~n apfil~h'q_le
_to,s;Mil~s
.. 1 ,,.: ;~:~ ,:::t i 1 1'i~:poi:~'.
_ _.: ;'*e::i~aJ:;(t
,.~'&#xa5;:s_s:;*;;-::
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er:. , . , ,~=9;%''':.
:ti'r%la~~t;:, *:-, -~;,?~~ .-i :~~:~ts;~r>
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r:>**~!~t~of
:*;{ , R26 , --,2.:0s, , 1-:os. -2:00
* z-:oo, ,2:00* _ -2.:00**
* 2.*:00 _ :2-.35 :2:00 _ :2:00 z:35' _ . 2:00: _2:00 -. 2:05, -, -*)12~-_.: :, ::~C>S~. H _ :i:~~/ .. {2~os.'*, ~-::4Jd5,, ,,: :~fof:; "-~~5~~~-. )ii~Sj--*: w~> . ;~--~~:Cl{/~
:c)-2;os;--);
-'.~~~.&sect;.']
r_-.7jtis, , : > .. d:~_; ;:::;i9~J,;
_
* R28 :i:05' -'2:05 ,2:00 , 2:00 -2:00.c _ 2:QS* .. 2~05 ~2:40 . 2':00 , .2:'00., 2:35: 1:0b, 2:00 . 2:05 * :, \~"** j Ti~J~J~;;
.'.' ~J;2~jl:b;, :>t'.~~Pi~,;;:i
~,,L~;.i9'0:;;. , *;i.:.@L .. ;~.~~~g&#xa3;.'.,~
c~,'g:f,QL:_;'
;~~3,,,.,,:
~]@.s.:i,'~;
',:::~~~:fa?f jf:;.~~,~,~~
~;:~.~~~O;
_;:
* itlO, :2:~o"' ::t:ss, .2*:4s: :1:50 :2:.45: 2:50,. *
* 2;ss :3;~5: 2::4.5 * :2;:so *3:30: *2:45' 2:sp 2:50' *SUsqu_eh~noa\S.team-'Ele.ctdr:.St.atJon, Evacuation~TimeJ:stimate
-Kt:D'.ErygH\eenng; P:c; Rev.''Q-m 3 CD ca CD ::::s "U Di" ::::s ;o CD :::: 0) I\) "U Ill ca CD ....... ""1 co 0 -I\) co 01 
-u D) ca CD ...... 0) 0 -N w 'Region r.Rifi: .. --Summer Midweek Good * *weather:[.
Rain I I
* Table 7~2; Ti me,to Clear the Indicated Area:of 100 Percent*of tlie!Affected:
Population Summer I summer I Winter I Weekeno l:.~id .. ~ee~. Midweek. Good1 Weathe( . I *"vuu, I Good 1* _,. 1* ... I Good ~am
* Weather
* weather :Ra,.n Snow Weath'er ... . . .. , ,. . .. Entire:i~Mi!e;Reg1011;;s,Mile
_Regiom and.EPi: Winter :W.nter I 'Summer* ;Roadway*
Impact , *_?f:QDL.
_ l4:0Q; : ~,;i!J~g "' , ' r.i+lOD_'-
c:_,~fql:.c.
:*j1I~t'.;
tf;'.'t1~Si:
~:, i ::.'~~m -,*~ ~@ w &#xa2; ~1-~,~,~,-,~
.-.. ]fof :: ;~ ~jfi<F *. ::>J:to*~:
.}i:i_c( _. ":;iiof: :* _,4':1~---, -*-,~!ii[?: .irr"d 1*~-*Jiifo.~:-.:, *~iii;?i)
;:*_~i_i_a:::**
.--:.;{!4~~-~
~.*-*if.icf::.*
::-'.J:~oc*~::
J:ip:--.;
J;&deg;'tJ~ -~~':0.0 :{ *2~1v1ue'!~egiori, and .Keylfotino,s'.Miles
*=!~'.:~a**.
!!(' .*... E!-j! *:Jf' . :',~t~,,;;~.J~-t~*;
~=:1~* ~l'"'.i~;:iJ**, *Ia:) 'J!**.~ ROS 4:o*s -4:05' 4:05 4:05 4':05 4:05 4:05-4:35 4:05 ~:OS 4;35*, 4:05 '4:05 ' *4:05' ~Mile'Regjon:and, Keyhole;to,E~ZBoun~ary, . ~~9,;-,: ';* ;1~10. , ':*::*f+/-ftj,,.
**,)4:id::
';i'~i1gz!;
*. J:ig?',}\l:;ff6:" :4':+/-d;'_, ,,Jl1Q, ---.,. i4=!fJ ' }@\,. *. ,*,;4.~1-~\
.: ,4;1~*, _ _, liio 4:10 ,4:io* 4:10 4:10 4:10 *4:4t:r 4:10 A:io 4:40 4:io 4:io
* 4:fo. * , RiiF-.. -*,_,4iio ,A:~o~ * ,: :---,~fik' . ..., .........
i: ,:.-~1tr[.:**-:
'. ))f :. ~~~{4~'.:j C)fii~ *:* -i ~:}f1f\ . )i(;*'. .. -,:-iiiqt:
,:,*~J@;**,:*:*
;* * );i( *:' *Ru, 4:10 *4:10 4110 4:10 4:10 4:40 4:10 4:10 *4:40 4:10 . .4:1ff 4:10 ._,,i~3i .. ,~:10 *: * :,4:rf,.;
i\:1:1tr ---.>?1:fg~ ::J.f4q:~~
;::::1:1qt'.;&#xa3;Ez1::@:i.:.
Y):jf * ,;*~'.i.:i( .: ::"}~~l2:;
-*jtil) R14 4:10 :4:10 1 4:10 4':10. 4:40' 4:10 *4:10. 4:40 4:10 4:10: -4~10 :--:~~s(}~
r:-,:4jlf
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', '.]~tW':* . *]:t(~:, 4*:10* 4:40* 4:10
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.. J)9\ :*::~~if=:
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::.)Jo;. -::jI~( .. : --,*.i:19*'.
... :,. .*_:fio*-*~
.:*_<i:i .. o** .. : 4:10 *4:1ti .4:40 4':10 .4:10 *4:4o, 4:io: *;;.;il1qf'.fi[~iif~
i: :4JoT;i ,_ ::z~iqt* :~r~Ia:. , :Rto ,4:lo 4:1b *4:10 4:10. 4*:10 4:fo 4:40. 4:lo A:10* -4::,fo: *4f10 -i:10, *4:10: *'~'..-.!,:,;.*
1* >, *, .. o:'"" _,, 1** <oC, .~',{>'.:?
-~ 'i"' '",\*"':-,,>~<
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<',';*,;,,\
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* 4't0 ' ** 'll*40; ,4;10* '''**4'10
_ :4,4p: ''. 4*10* '4'10 . * -_ *4*10* '-:~z-* -*4;10 *4;10 4:10 .*. *;1,t :'. :;/io>*_'~'.t10:
.. : __ 4;10,'._'~::~;4Q':_, iio*'.:..., .. '.4~it.'";:
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* Po.p.eJohnwaul II CatfiolitSthool Rice\Eiem entary: Susquehanna.Steam, Elec~nc:St13ti0,ri' EvatliatioiJ time:estimate, Tabfe841;.
s.chootEvatuation*JimetEstiinates*-
GoocfW~athet 90 ,90
* 90 }}0. 90 9(f :90. *90 15 15 15'.. JS 15 15 .. 15 15. 15 15 15 15 15 15 4.7 5.7 ms 5(7 o:s: 1;4 2'.0. 23 4 2 * .1 21 15:2 23 4 :13 K&#xa3;D Eng]hee~ing, 'PtC; 8ev::.O m 3 CD ca CD :::s .Q "U ii> :::s ::0 CD 0) N "U D> ca CD -->. OJ 0 -N c.o 01 "U D> cc CD I\) ...... 0 -,, I\) w i .3 4 :s 6: T '8 :g: .i9': 11, 12* 1,3 .~;2 t~A :QO; M _:~)6 1 190' 7'.4 '7;8 :111.0 i.4-_ &sect;ii()'il -I'' ,. '.,. :_120* ' .. '7.,4. :i _:9;0 ~u .:2' -12'6: (. ', :t:~4 i i90 :J;ii .. 1 :90 .10:1. :i. 1o*s, *1 10'1 : ***** ' } 3 1tb, '101. l;Zi '.90 4;6 jj4. 105'. .4,Q . 5,6: 1'20 4:6 'i 90 2:5, 12 12tf *2:s .1. [90 10:3* 1 90 4'.J '.2: 120. 4:7 ]. 90:, *4;2 :!, 9Pi 1'7*:0 ]. 90' 4;3 '2'. 129_ ,4i3 -1. 90* 4;0. . 2. 120: .4;0 . . Susqtie!lanna,Steam,ElecttiP:Station . . . -'~vacllatiofrTrme*
Estimate:
Tabt~ s~u. Tr~rtsit~D~Re:n~eijt'.~ij_cuatio~'Tini'~:Estimates
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* 30; 154 30 ,54 30 63' 30. :,~.'iv.sit.
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* 30 ,. ,s:90: :21-I l 90 1 1:1 I 14,4 I ~p. I :3o P' J~Q**, 1. :34;i I' s2 I :s I .10 I 72 .. I 30 L .:,s;20; *22; J. "). so 6]; 42J. 9 30 *1:-Li:f9:.~, ,3Q;1. . il-s s: 10
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*EvaeuaffonJime-EstimaJe ES,19' -KLDEngineenng; f>iC. :ReV/Q m 3 CD ca CD ::::s "U 65" ::::s :;o CD 0) N "U Q) cc CD -" 00 0) 0 -N (.D 01 
"'U Ol (Q CD N w 0 -N w / Legend &deg;f{ SS E S GJ ER P A /2.. E vacua t e \. -:::: 2. 5 , 1 0 M ll e R inis --Se ct o r Bo un dary Susquehanna Steam E l ectr i c Stat i on Evacu at i on T i me Est i mate ....... ,.""" I cc,rp:: , 01"'"'~.o.i.1~ Q.Ot 11Jl11t irl~ ... ......, l.o t~\Uod"o-M &#xa3;,1w nrrk'n. ,* m 3 CD ..... (Q CD :::I (") '< "'U o3" :::I :::0 CD < 0) N "'U Ol M1<1 n I (Q CD ->,. CX) -...J 0 -Figure H-8. Region ROS N C.D u, ES-20 KLD Engineering, P.C. Rev.O Emergency Plan, Rev. 62, Page 188 of 295 APPENDIX H DOWNSTREAM SUSQUEHANNA RIVER WATER USAGE Page 1 of 3 Emergency Plan, Rev. 62, Page 189 of 295 ''" .. * .,. APPENPIX.
H '* ' ********-****
*-*. ---I -,.,,,..,'
Quantity User's Name Location-River Miles Use Class (Mgd) Comment 1. Keystone Water Co. Berwick -8.0 M Sb None For emergency use only. Not used for 8 years. Pump removed. Serves about 20-25 thousand people. 2. Bloomsburg Water Co. Bloomsburg
-19.4 M Sb 0 3. Camobell Soup Co. Bloomsburg
-19.4 I None None No use of river water. 4. Danville Borough Danville -27.4 M Pr 1.8 Will expand use. Serves about 8,000 oeoole. 5. Merck & Co. Danville -27.4 I Pr 7-9 Serves about 500 people. Large quantity for coolina, small for process. 6. Danville State Hospital Danville -27.4 Pu Pr NA Serves about 4,000 people. Receives water from Danville Borough. Only in emeraencies.
: 8. Celotex Corp. Sunbury -38.5 I None None Receives water from Sunbury Municipal Authority.
: 9. Sunbury (SES) -WPS Sunbury -38.5 I Pr 245 10. Shamokin Dam Municipal Shamokin Dam -44.4 M Pr NA Serves about 2,000 people 11. Millersbura Water Co. Millersburg
-69.4 M Sb NA 12. Harrisburci Mun. Auth. Harrisburg
-91.0 M Sb NA 13. Bethlehem Steel Co. Harrisburg
-91.0 I NA NA 14. Borough of Steelton Water Steelton -93.4 M Pr 1.7 Allocated 5.0 Mgd Co. 15. Metropolitan Edison (SES) Middletown
-100.2 I Pr 245 16. Metropolitan Edison (HES) York Haven -105.2 I Pr 11,782 17. Talen (SES) Brunner Island -108.0 I Pr 745 18. Wriahtsville Water Co. Wrightsville
-119.0 M Pr NA 19. Colu'mbia Water Co. Columbia -119.0 M Pr 1.8 20. Lancaster Water Auth. Lancaster -* M Pr 8.0 Based on old data, allocated 24.0 Mad. 21. York Water Co. York-* M Sb NA 22. Safe Harbor Water Safe Harbor-129.7 M Pr 79,527 23. Talen (HES) Holtwood -137.9 I Pr 21,337 24. Phila. Electric (PS) Muddy Run -140.4 I Pr 12,931 25. Phila. Electric (NS) Peach Bottom -143.0 I NA 0.03 Page 2 of 3 Emergency Plan, Rev. 62, Page 190 of 295 ll APPENDIX_ltl
__ ;.-*** *-I **--***-**
--**-* *-**-*****-
-"-*-*******'
Quantity User's Name Location-River Miles Use Class (Mgd} Comment 26. Phila. Electric & Conowingo
-154.3 I Pr 53,018 Susquehanna Power Co. (HES) 27. Chester Water Auth. Chester-* M Sb NA 28. Baltimore Water Authoritv Baltimore, MD -* M Sb NA 29. Havre-de-Grace Municipal Havre-de-Grace, M . Pr 1.4 Auth. Md-* NOTE: River miles are from Susquehanna SES Site
* Not on River *-Ll:GEND NA Not Available (SES) Steam Electric Station (HES) Hydroelectric Station (PS) Pumpinq Station (NS) Nuclear Station I Industrial M Municipal Pu Public Pr Primary Sb Standby Mgd Million gallons per day Page 3 of 3 Page 1 of 2 Emergency Plan, Rev. 62, Page 191 of 295 APPENDIX I POPULATION UPDATE FOR SSES EMERGENCY PLANNlNG ZONE-Emergency Plan, Rev. 62, Page 192 of 295 REFER TO THE EVACATION TIME ESTIMATE IN APPENDIX G FOR THE CURRENT POPULATION INFORMATION Page 2 of 2 Emergency Plan, Rev. 62, Page 193 of 295 APPENDIXJ NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN Page 1 of 10 Emergency Plan, Rev. 62, Page 194 of 295 *,' ,-*, '',, ,,,, ., ',., '' ', .**** NUREG;,,0654 PLANNING STANDARDS AN ti 6VA:l:.UATION CRITE,RlA CROSS REFl:R.ENCE TO 'SSE$ EMERGENCY PLAN .,,* APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN 1.a. 1.b. 1.c. 1.d. 1.e. 3. 4. { 2. 3. 4. 5. 6. 7.a. 7.b. 1.c. 7.d. 8. 9. Page 2 of10 Chapter 6, Section 6.0, Table 6.2, Appendix A Chapter4 Table 5.2 Chapter 6 Chapter 6, Figures 6.2, 6.3, 6.6, 6.7 FSAR Figure 13.1-3 Chapter 6, Sections 6.2.1, 6.3.1.1 Chapter 6, Sections 6.0, 6.1, 6.2, 6.2.3, 6.2.4, 6.2.5, 6.3, 6.3.1.2, 6.3.1.4, 6.3.1.5, 8.3.1, 8.3.2 Appendix A Chapter 6, Sections 6.2.7, 6.3.1.3 ,, Chapter 6, Sections 6.0 Phase I, II, Ill, 6.1, Tables 6.1, Figure 6.2, Figure 6.3 Chapter 6, Sections 6.0, 6.1 Appendix E Chapter 6, Section 6.2.1 Chapter 6, Section 6.2.1 Chapter 6, Tables 6.1 Chapter 6, Figure 6.7 Chapter 6, Section 6.2.6 Chapter 6, Section 6.2.5, 6.5 Chapter 6, Section 6.2.1 Chapter 6, Section 6.3.2.1 Chapter 6, Table 6.2 Appendix A Chapter 6, Table 6.2 Appendix A Emergency Plan, Rev. 62, Page 195 of 295 --.. ,... " "** :---* . -,, *"' .. NUREG-0654 PLANNING STANDARDS, AND.iEV~LUATIQN CIU1ERIA CROSS REFERENCE TO SSES EMERG.ENCY PLAN . ****** APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN ...... C,'. _lzmer~ency Respc:mse Sppportf~esources " .. . _, _ , . * ..
* 1.a. Chapter 6, Sections 6.2.1, 6.3.1.1, 6.4.3 1.b. Chapter 6, Section 6.4.3 1.c. Chapter 6, Section 6.4.3 2.b. Chapter 6, Sections 6.2.1, 6.3.1.1 3. Appendix D, Enclosure 5 4. Appendix A, Table 6.2 p. Efoergen'cy Classificatio.ns
: 1. Chapter 5, Sections 5.1, 5.2, Appendix D, Appendix F, Tables F, R, S, E, H, C. 2. Chapter 5, Table F, R, S, E, H, C. . .... .. . .. .*. 1. Chapter 6, Figure 6. 7 Appendix C, Position Specific Instructions for:
* Control Room Emergency Plan Communicator
* TSC Emergency Plan Communicator
* EOF Communicator *
* Radiation Protection Coordinator
* Technical Support Coordinator
* Recovery Manager
* Dose Assessment Supervisor
: 2. Appendix C, Position Specific Instructions for:
* Emergency Director
* Control Room NRC Communicator
* Control Room Emergency Plan Communicator
* TSC Emergency Plan Communicator
* Security Coordinator
: 3. Appendix C, Position Specific Instructions for:
* Control Room Emergency Plan Communicator
* TSC Emergency Plan Communicator
* EOF Communicator 4.a., b., c., k., n. Appendix C, Position Specific Instructions for:
* Control Room Emergency Plan Communicator
* TSC Emergency Plan Communicator
* EOF Communicator Page 3 of 10 Emergency Plan, Rev. 62, Page 196 of 295 .. N0R~G~Q$J;,.:
PL,ANNINGSTAN~ARPS AND*EVAL4AiiON . *:****c1t1reMl.c1i8i~***~eFe~~~c~Io
: '.;::,t;*L, .. SSES ~MERGENCY p.LAN ''>, ~" ',,;'4 'c'J ,: *;'.t""> '; ., APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN 4.d., e., f., g., h., i., j., I. Appendix C, Position Specific Instructions for: 4.m. 6. 7. 1. 1.a. 1.b. 1.c. 1.d. Page 4 of 10
* Radiation Protection Coordinator
* Dose Assessment Supervisor Appendix C, Instructions for:
* TSC Security Coordinator
* Offsite Or anization Res onse to Plant Events Chapter 6, Sections 6.2.1, 6.3.1.1 Chapter 7, Sections 7.1.1, 7.3.2 Chapter 8, Section 8.5.4 Chapter 6, Sections 6.2, 6.2.1, 6.2.3, 6.3.1.1, 6.3.1.5 Chapter 7, Section 7.3.2, Table 7.3 Chapter 6, Figure 6.7 Chapter 8, Sections 8.1.3.5, 8.2.2.4 Chapter 6, Sections Phase le), 6.2.3, 6.2.4e), 6.2.5g), 6.3.1.1 i), 6.3.1.4e), 6.3.1.5, 6.4 Appendix C, Position Specific Instruction for:
* Control Room Emergency Plan Communicator
* TSC Emergency Plan Communicator
* EOF Communicator
* Radiation Protection Coordinator
* Tech Support Coordinator
* Recovery Manager
* Dose Assessment Supervisor Chapter 8, Sections 8.3.1, 8.3.2 Chapter 6, Sections Phase le), 6.2.3, 6.2.4, 6.3.1.5 Chapter 8, Sections 8.1.3.5, 8.2.2.4, 8.2.2.4.1, 8.2.2.4.2 Appendix C, Position Specific Instructions for:
* Control Room Emergency Plan Communicator
* Control Room NRC' Communicator
* TSC Emergency Plan Communicator
* TSC NRC Communicator
* EOF Communicator Chapter 6, Sections 6.2.1j), 6.2.3c), 6.2.4d), 6.2.5g) Chapter 8, Sections 8.1.3.5, 8.1.3.5.1, 8.1.3.5.2, 8.2.2.4, 8.2.2.4.1, 8.2.2.4.2 Emergency Plan, Rev. 62, Page 197 of 295 .. ,, --'NUREG-.0654 PLANNI~G STANDARDS AND :EVALUATION CR!TERlA CROSSJtl:F~RE~CE
'fQ SSE$ ~MERGl:NCY PLAN . .; '' APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN 1.e. Chapter 6, Sections Phase I, Phase II, Phase Ill, 6.2, 6.3 1.f. Chapter 8, Sections 6.2.1 d, 6.3.1.1 c, 6.3.1.1j, Figure 6. 7 2. Chapter 7, Sections 7.4.2, 7.4.3 Chapter 8, Sections 8.1.3.5.1, 8.2.2.4 Appendix C, Instruction for:
* Security Coordinator
* Offsite Organization Response to Plant Events 3. Chapter 9, Sections 9.1.2, 9.3 ,* ',' G. Public Educatiorr~nd lnfqrmation 1.a., b., c., d. Chapter 9, Sections 9.4, 9.4.1, 9.4.2, 9.4.3, 9.4.4 2. Chapter 9, Sections 9.4, 9.4.1, 9.4.2, 9.4.3, 9.4.4 3.a. 3.b. 4.a. 4.b. 4.c. Chapter 6, Section 6.3.2 Chapter 8, Section 8.2.1 Chapter 8, Section 8.2.1 Chapter 6, Section 6.3.2.1 Chapter 6, Sections 6.3.2, 6.3.2.1 Chapter 6, Section 6.3.2.1 e) 5. Chapter 9, Section 9.4.2 * ,''' ., ' '.' .* -. ' ','' ' -' ' i'. ' , .* ;;:< ;\ H Emergency Facili!i~~
c:!nd ,Equi_prnent
__ _ __ . 1. Chapter 8, Sections 8.1.2.1, 8.1.1.2, 8.1.3 2. Chapter 8, Section 8.1.2.2 4. Chapter 6, Sections Phase I, Phase II, Phase Ill 5. Appendix D, Enclosures 3, 4, 5, 7 5.a. Appendix D, Enclosure 3 5.b. Appendix D, Enclosure 4 5.c. Appendix D, Enclosures 4, 7 5.d. Appendix D, Enclosure 7 6.a., b. Chapter 7, Section 7.1, 7.1.1 \ Page 5 of 10 ,,. 
/ Emergency Plan, Rev. 62, Page 198 of 295 '**
* 0, *, ', ~.. ' '.'" ** :: .. ~~::::*:*.
':. \.,. * ,* S ' ' ** * * *' ,o, /" '* C *: NUREG-0654*
PLANNING STANDARDS AND EVALUATION.
CIUTEIUA CROSS REFER.ENCE TO $SES EMERGENCY PLAN -' .", ' .*** ' .. ,',, ; APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN 6.c. Appendix C, Position Specific Instructions for:
* Chemistry Coordinator
* Field Team Director Table 6.2 7. Appendix D, Enclosures 4, 5 8. Chapter 7, Section 7.1.1.1, Appendix D, Enclosure 3 9. 10. 11. 12. 1. 2. 3.a., b. 4. 5. 6. 7. 8. 9. 10. Page 6 of 10 Chapter 8, Section 8.1.2 Chapter 9, Section 9.3 Appendix D Chapter 6, Sections 6.2.4f), 6.3.1.4f)
Chapter 5, Table F, R, S, E, H, C Appendix F Chapter 7, Section 7.1 Chapter 7, Section 7.1, 7.1.1.3 Chapter 7, Section 7.1, 7.1.1, 7.1.1.3 Chapter 7, Section 7 .1.1.1 Chapter 7, Sections 7.1.1.3, 7.1.1.4 Chapter 7, Section 7.1, 7.1.1 Chapter 7, Section 7.1, 7.1.1.3 Chapter 7, Section 7.1.1.3 Appendix D, Enclosures 4, 5, 6 Chapter 7, Section 7.1.1, Table 7.3, 7.1.1.3 .. '
Emergency Plan, Rev. 62, Page 199 of 295 ::: : _c ., ._ .. " ,_ -sc>>* e* "' :* NUREG.;0654 PLANNING STANDARDS AND :EV~LUATlON CRITERIACR.OSSJtEFER.ENCEfO
.. c, : "'" ,. : ' .. : ~, ' . -SSES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN J. Ar:~tective Resp9nse * ... 1.a., b., c., d. 2. 3. 4. 5. 6.a. 6.b. 6.c. 7. 8.* Page 7 of 10 : Chapter 7, Section 7.3, 7.3.1, 7.3.2 Appendix C, Position Specific Instruction for:
* Control Room Emergency Plan Communicator
* TSC Emergency Plan Communicator
* Radiation Protection Coordinator
* Security*
Coordin?tor
* Control Room Emergency Director
* TSC Emergency Director Chapter 7, Section 7.3.1.4 Chapter 7, Section 7.3.1.4 Chapter 7, Sections 7.3.1.3, 7.3.1.4 Chapter 7, Sections 7.3.1, 7.3.1.3, 7.3.1.4 Appendix C, Position Specific Instructions for:
* Emergency Director
* Security Controller Chapter 7, Section 7.3.1 Chapter 7, Section 7.3.1 Chapter 6, Section 6.2.1 k, 6.2.41 Chapter 7, Table 7.2 Chapter 6, Sections, 6.0, 6.2.1, 6.3.1.1 Chapter 7, Tables 7.1, 7.3 Appendix C, Position Specific Instructions for:
* Emergency Director
* Radiation Protection Coordinator
* Control Room Emergency Plan Communicator
* TSC Emergency Plan Communicator
* Recovery Manager
* Dose Assessment Supervisor
* Liaison Support Supervisor
* EOF Communicator Appendix G Emergency Plan, Rev. 62, Page 200 of 295 I ,*---" .. ,..... &#xa3; .. ,., .:"' < " ,,*c:. .., ,
* NUREG~0654 PL:ANNING STANDARDS AND !EV~LQATION' CRITER!ACROSS REFE~ENCE tO $SES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN 1 O.a. Appendix C, Position Specific Instructions for: 10.b. 10.c. 10.m . . K Ra9iologicc1l
'Expqsure Control 1.a., b., c., d., e., f., g. 2. 3.a. 3.b. 5.a., b. 6.a., b., C. Page 8 of 10
* RP Tech I (OSCAR)
* Field Team Director
* Monitoring Team
* Environmental Sampling Team Appendix G Appendix H Chapter 7, Section 7.3.1.4 & Figure 8.1 Appendix G Appendix I Chapter 7, Section 7.3.2 Chapter 8, Section 8.5.4 Chapter 7, Sections 7.3.2, Appendix G . , .*.,** Chapter 7, Section 7.4.3, Table 7.2 ** Appendix C, Position Specific Instructions for:
* Security Coordinator .
* Radiation Protection Coordinator
* RP Specialist Chapter 6, Section 6.2.11, 6.2.1 k, 6.2.41 Chapter 7, Section 7.2, Table 7.2 Appendix C, Position Specific Instructions for:
* Radiation Protection Coordinator Chapter 7, Section 7.3 Appendix C, Position Specific Instructions for:
* Radiation Protection Specialist
* Radiation Protection Coordinator Appendix D, Enclosures 5,6,8 Appendix C, Position Specific Instructions for:
* Radiation Protection Specialist
*, Radiation Protection Coordin*ator
* Field T earn Director
* Monitoring Team
* Environmental Sampling Team Chapter 7, Section 7.3.1, 7.4.2 Chapter 7, Section 7.3.1, 7.4.2 * ...
Emergency Plan, Rev. 62, Page 201 of 295 "" -*-, ,, ,, .... _. "* , ' ,, NUREG-0654 PLANNING STANDARDS AND EVALUATION
' CRJ&deg;I;~~" :~1\QS$ ltEFEREN<;;E TO ,, ' SSES EMERGENCY PLAN . . *-*' -. APPLICABLE NUREG-0654 SECTION SSES EMERG-ENCY PLAN 7. Chapter 7, Section 7.3.1.4, 7.4.2 .,, . L. Me<;lical arid Public Health Support .*. ,, .* 1. Appendix A 2. Table 6.1 4. Chapter 7, Section 7.4.3 Appendix A Appendix C, Position Specific Instructions for:
* Security Coordinator
-, . M. R~q~very Reeri!ry _l?l~nni~~ Postaccident Oper-ations,., -----.. 1. Chapter 6, Sections Phase IV, 6.5 Appendix C, Position Specific Instructions for:
* Emergency Director
* Recovery Manager ,, 2. Chapter 6, Section 6.5, Figure 6.6 Appendix C, Position Specific Instructions for:
* Emergency Director
* Recovery Manager 3. Chapter 6_, Section 6.5 4. Section 6.2.4, 6.3.1.4 Appendix C, Position Specific Instructions for:
* Radiation Protection Coordinator
* Dose Assessment Supervisor
.-, ------'\ <. -, ., .. -N .. Ex~rcisesana DfilJs --.. --. ' __ ,, 1.a., b. Chapter 9, Section 9.1.2 2.a., b., c., d., e. Chapter 9, Section 9.1.2 3.a., b., c., d., e., f. Chapter 9, Section 9.1.2 4. Chapter 9, Section 9.1.2 5. Chapter 9, Section 9.1.2 = -* 0. Hadi~lo~ical Emergency Respon_~e Training ,_ 1.a. Chapter 9, Section 9.1.1, Table 9.1 1.b. Chapter 9, Sections 9.1.1, 9.1.2 2. Chapter 9, Section 9.1.2, Table 9.1 Page 9 of 10 Emergency Plan, Rev. 62, Page 202 of 295 ' ,,, ' ' ".***:" NUREG-0654 PLANNING STANDARDS AND EVALUATION CRltER.tA
~ROSS REFi;R.ENCE To i.~ SSES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN 3. Chapter 9, Section ~-1 4.a., b., c.; d., e., f. Chapter 9, Table 9.1 4.g. Chapter 9, Section 9.1.1 4.h., i., j. Chapter 9, Table 9.1 5. Chapter 9, Table 9.1 ' ,, P. Responsibility forthe PlqJrning
~ffort : Development, Periodic Review and Distribution of Emergency Pl~ns ;;**: 1. Chapter 9, Section 9.1.1, Table 9.1 2. Chapter 9, Section 9.1.3 3. Chapter 9, Section 9.1.3 4. Chapter 9, Section 9.2.1 5. Chapter 9, Section 9.2.1 6. Chapter 3, Appendix A 7. Appendix C 8. Table of Contents 9. Chapter 9, Section 9.2 10. Chapter 9, Section 9.3 Appendix 1 Table F, R, S, E, H, C, Appendix F Appendix 2 Appendix B Appendix 3 Section 6 -Phase I Section 6.2.3, 6.3.1.5, 6.4.2, 7.3.2 Page 10 of 10 Page 1 of 93 Emergency Plan, Rev. 62, Page 203 of 295 On-Shift Staffing Analysis APPENDIX K On-Shift Staffing Analysis Emergency Plan, Rev. 62, Page 204 of 295 On-Shift Staffing Analysis S , , * , , ,.-h* rr ,,. ,, .,,,.. s-t:, ,. ...
* E* "l'e 'r t',r:!c s* -t*a* *t.-1*o*n*
UJSQ ue r Janna *.. :_earn -~c !, I I r~ -~ i ~: ! ' : 'I) f J Revision 0 December 14, 2012 Page 2 of 93 Emergency Plan, Rev. 62, Page 205 of 295 On-Shift Staffing Analysis Title Introduction Executive Summary Conclusion Table of Contents Table 1, Susquehanna On-Shift Staffing Table 2, Susquehanna DBA/ISG Analyzed Events Appendix A, Phase II Analysis Results Phase II Preliminary Conclusions Phase II Recommendations Appendix B, Phase II Event Analysis Tables Phase II Event Analysis Table Index On-Shift Personnel Assignments Used During Phase II Analysis Appendix C, Phase Ill Results Phase Ill Time Motion Study Results Page 3 of 93 Page Number 1 1 &#xa3; &#xa3; ! &sect; &sect;. I &sect;. 86 95 Introduction Emergency Plan, Rev. 62, Page 206 of 295 On-Shift Staffing Analysis 1 O CFR 50 Appendix E, effective on December 23, 2011 directed that a detailed study be performed by December 24, 2012; to ensure on-shift staffing was adequate to perform critical functions until relieved by the augmented Emergency Response Organization (ERO). The NRC in the published staff guidance (Reference
: 2) endorsed NEI 10-05 as an acceptable means of performing the required staffing analysis.
This report documents the result of that analysis for Susquehanna Steam Electric Station (SSES). References
: 1. 10 CFR 50 Appendix E 2. NSIR/DPR-ISG-01, Interim Staff Guidance, Emergency Planning for Nuclear Power Plants 3. NEI 10-05, Revision 0, Assessment of On-Shift Emergency Response Organization Staffing and Capabilities . 4. SSES Emergency Plan, Revision 53, Table 6.1, Station Emergency Plan Minimum Staffing Requirements
: 5. SSES FSAR, Chapter 15
* Executive Summary A detailed staffing analysis performed in accordance with NEI 10-05 was conducted to document the adequacy*
of shift staffing as required by 10 CFR 50 Appendix E. The minimum staff described in Table 6.1 of the SSES Emergency Plan, Revision 53, was used to perform the on-shift staffing analysis.
Table 1 of this report lists the on-shift staffing as described in Revision 53 of the SSES Emergency Plan. NRC staff guidance directs the scenarios that must be used to demonstrate the adequacy of on-shift staffing to perform required functions for event mitigation, radiation protection response, firefighting, chemistry and Emergency Plari functions.
Those scenarios include specific design basis events as described in the FSAR as well as specific scenarios defined in the staff guidance document.
* Table 2 identifies the scenarios that were examined.
The next phase required of NEI 10-05 requires a dedicated team using tabletop techniques examine the scenarios for conflicts between the functional areas that must be resolved by detailed procedural analysis.
For those scenarios where no conflicts are identified in the specified areas no further actions are required.
Table 2 also identifies the scenarios that required detailed analysis due to conflicts in response functions.
Appendix A to this report
* documents the results of the procedural analysis.
Appendix B includes the completed event scenario analysis tables. The final phase of NEI 10-05, Time Motion Study (TMS), identifies any staffing conflicts with the minimum shift that must be resolved.
&deg;The TMS for Susquehanna Steam Electric Station determined that staffing conflicts do not exist. Appendix C of this report summarizes the results of the TMS. Page 4 of 93 Conclusion Emergency Plan, Rev. 62, Page 207 of 295 On-Shift Staffing Analysis The minimum staff identified in Table 6.1 of the Susquehanna Steam Electric Station Emergency Plan, Revision 53, was adequate to respond to the scenarios identified in the regulations until relieved by the augmented ERO. Table 1 Susquehanna Steam Electric Station On-Shift Staffing SSES Emergency Plan, Rev 53 Table 6.1, Station Emergency Plan Minimum Staffing Requirements Position On-Shift Shift Mana er (SM 7 1 Unit Supervisor SRO) 7 1 NRC Communicator SRO 1 , 1 1 Plant Control O erators 7 3 E Plan Communicator 2* 7 1 Shift Technical Advisor STA) 1* 7 1 Nuclear Plant O erator 4 RP Technician 3 2 Chemist Technician 4 1 Total: 15 Sec Ian 1 One Unit Supervisor assigned to each unit. The unaffected Unit Supervisor or STA assumes the role of NRC Communicator.
2 Two (2) Control Room Operators per unit. This number includes two (2) OATC Reactor Operators and two (2) BOP Reactor Operators.
The unaffected unit BOP assumes the role of E Plan Communicator.
3 Two (2) RP Technicians on shift. One (1) RP Technician provides support as Dose Calculator (Offsite Dose Assessment).
One (1) RP Technician provides support by providing In-plant surveys, job coverage, and personnel monitoring.
4 One (1) Chemistry Technician provides chemistry sampling support. 5 Fire Brigade is a collateral duty of Maintenance Site Support Services Management requiring 5 personnel without safe shutdown responsibilities.
The Fire Brigade consists of 1 Fire Brigade Leader (Field Unit Supervisor) and 4 Fire Brigade Members. Reference NDAP-QA-0445.
6 Rescue Operations/First Aid is a collateral duty of Fire Brigade and Security personnel.
7 Licensed Operators are trained and qualified as E Plan and NRC Communicators.
Page 5 of 93 Emergency Plan, Rev. 62, Page 208 of 295 On-Shift Staffing Analysis Table 2 Susquehanna Steam Electric Station DBA/ISG Analyzed Events TMS DBA/ISG Summary Description of Event or Accident Required Event# YES 1 Land and/or waterborne HOSTILE ACTION directed against the Protected Area by a HOSTILE FORCE. Adversary characteristics defined by the Design Basis Threat (DBT). NO 2 Recirc Pump Shaft Seizure (No Classification
-Phase II Analysis not required per NEI 10-05 guidance)
NO 3 Recirc Pump Shaft Break 1 NO 4 Control Rod Drop NO 5 Instrument Line Break 2 NO 6 Steam System Piping Break Outside Containment (MSLB) NO 7 Loss of Coolant Accident inside Containment (with release exceeding PAGs and resulting PARs) 3 NO 8 Feedwater Line Break Outside Containment 2 NO 9 Fuel and Equipment Handling Accident 4 NO 10 ATWS NO 11 Response actions for an "aircraft probable threat" in accordance with 1 O CFR 50.54(hh)(1) and as discussed in RG 1.214 YES 12 Control room fire leading to evacuation and remote shutdown, as referenced in IN 95-48. YES 13 Station Blackout (Current Licensing Basis) NO 14 Appendix R Fire Response 5 NO 15 SAMG 1 The SSES FSAR states that the Recirc Pump Shaft Break event is bounded by Event 2, Recirc Pump Shaft Seizure. Therefore, no Phase II Analysis is required.
2 The SSES FSAR states that the Steam System Piping Break Outside Containment is more limiting than the Feedwater Line Break Outside Containment and the Instrument Line Break. Therefore, Event 6, Steam System Piping Break (MSLB), bounds these events and no Phase II Analysis is required.
3 OBA event designated as proceeding non-mechanistically to GE with release exceeding Protective Action Guides. *
* 4 Fuel and Equipment Handling accident is not analyzed with the existing on-shift staff. The SSES FSAR states that this event involves fuel that is conditioned at least 24 hours after shutdown; therefore it is applicable to refueling conditions.
Refueling .operations are staffed for the evolution with additional operatjons, RP and support personnel.
5 Per SSES personnel, the Control Room fire with evacuation and remote shutdown is the bounding Appendix R fire scenario; therefore, no further ~nalysis of this event is required.
Page 6 of 93 Page 7 of 93 Emergency Plan, Rev. 62, Page 209 of 295 On-Shift Staffing Analysis App.endixA Phase II Analysis Results Emergency Plan, Rev. 62, Page 210 of 295 On-Shift Staffing Analysis A multi-disciplined team of subject matter experts from Susquehanna Steam Electric Station was assembled September 10-12, 2012 to provide input into the shift staffing analysis of events identified by NSIR/DPR-ISG-01, Interim Staff Guidance, Emergency Planning for Nuclear Power Plants. This team consisted of: a Shift Technical Advisor (SRO Certified);
Chemistry Foreman; an RP Supervisor; a Fire Protection Engineer; a Security Coordinator; and Emergency Planning staff (station and consultants).
The team provided analysis support during the Phase II analysis as follows: On-Shift Staffing Analysis Team Team Member Subject Matter Expertise Shift Technical Advisor Emergency Operating Procedure (EOP) actions for SROs, NPOs, and PCOs Off-Normal Operating Procedure (ONOP) actions for SROs, NPOs, and PCOs OperatinQ Procedure actions Site EmerQency Director (E Plan) Actions Fire response actions Control Room Communicator (NRC Communications) actions Fire Protection Fire Brigade Response actions Engineer, Chemistry Foreman Chemistry Technician response actions RP Supervisor RP Technician response actions Security Coordinator Security Response actions Accountability Response actions Emergency Planning EmerQency Plan response actions Site Emergency Director (E Plan) Actions The Phase II Analysis was conducted in three steps: identification of events for analysis; minimum shift staffing complement determination; and, a table top analysis of the on-shift staffing resources required for response to the identified events. The team reviewed a total of nine (9) events. The results and recommendations of the Phase II Shift Staffing Analysis are documented in this report. Phase II Preliminary Conclusions
: 1. Operations Conflicts
-Time Motion Study (TMS) is required for the STA position due to competing ON/EOP procedure actions and assigned Emergency Plan functions/tasks.
The TMS will determine if these functions can be performed by the STA during an event. Phase 11 Recommendations:
: 1. Determine the most effective methodology to perform remaining scenarios requiring detailed time motion studies (Simulator based Drill, timed in-plant response, combinations, other). 2. Schedule and conduct Phase Ill analysis for the following events: a. Design Basis Threat b. Control Room Fire with Evacuation and Remote Shutdown c. Station Blackout Page 8 of 93 Page 9 of 93 Emergency Plan, Rev. 62, Page 211 of 295 On-Shift Staffing Analysis Appendix B Phase II Event Analysis Tables Analysis FSAR OBA/ (Scenario ISG Event# Number) (Appendix A) 1 1 2 1 3 &sect;. 4 z 5 1.Q 6 11 7 .1l 8 9 15 Page 10 of 93 Emergency Plan, Rev. 62, Page 212 of 295 On-Shift Staffing Analysis Phase II Event Analysis Table Index Page Title Source Number Design Basis Threat ISG 11 Control Rod Drop FSAR 20 Limiting Fault Event Steam System Piping Break Outside FSAR 29 Containment (MSLB) Condition IV Event Loss of Coolant Accident inside ISG/FSAR 38 Containment (with release exceeding Limiting Fault PAGs and resulting in PARs) Event ATWS ISG/FSAR 46 Limiting Fault Event Response actions for an "aircraft ISG 54 probable threat" in accordance with 1 O CFR 50.54(hh)(1) and as discussed in RG 1.214 Control room fire leading to ISG 62 evacuation and remote shutdown, as referenced in IN 95-48. Station Blackout (Current Licensing ISG 11 Basis) SAMG ISG 80 Emergency Plan, Rev. 62, Page 213 of 295 On-Shift Staffing Analysis On-Shift Personnel Assignments Used During Phase II Analysis Position Designation Assignment Shift ManaQer Shift ManaQer Shift Manager/Emergency Director Unit Supervisor SR0#1 Unit 1 Shift Supervisor Unit Supervisor SR0#2 Unit 2 Shift Supervisor Field Unit Supervisor FBL Fire BriQade Leader Shift Technical Advisor STA Shift Technical Advisor Plant Control Operator PC0#1 Unit 1 Operator At Controls (OATC) Plant Control Operator PC0#2 Unit 1 Balance of Plant (BOP -Communicator)
Plant Control Operator PC0#3 Unit 2 Operator At The Controls (OATC) Plant Control Operator PC0#4 Unit 2 Balance of Plant (BOP -Communicator)
Nuclear Plant Operator NP0#1 Unit 1 Reactor BuildinQ NPO Nuclear Plant Operator NP0#2 Unit 2 Reactor BuildinQ NPO Nuclear Plant Operator NP0#3 Unit 1 Turbine Buildinq NPO Nuclear Plant Operator NP0#4 Unit 2 Turbine Building NPO Other On-Shift Assignments Used During Analysis Position Designation Assignment RP Technician RP#1 Offsite Dose Assessment RP Technician RP#2 RP Support Chemistry Technician Chem #1 Chemistrv Samplinq Maintenance Site Support FBM #1 Fire Brigade Member/Maintenance Site Services Handyman #1 Support Services Maintenance Site Support FBM#2 Fire Brigade Member/Maintenance Site Services Handyman #2 Support Services Maintenance Site Support FBM#3 Fire Brigade Member/Maintenance Site Services Handyman #3 Support Services Maintenance Site Support FBM#4 Fire Brigade Member/Maintenance Site Services Handyman #4 Support Services Page 11 of 93 Emergency Plan, Rev. 62, Page 214 of 295 On-Shift Staffing Analysis Event Timelines and Assumptions Event #1 Design Basis Threat Initial Conditions:
Time: Sunday @0230 Unit @ 100% Power RCS @ normal operating temperature and pressure Sequence of Events: 0235 Adversary force assaults SSES and attempts to breach the protected area fence Security engages adversaries and notifies Shift Manager 0236 CR personnel initiate Security Event response AOP Rx manually tripped On-site protective actions initiated Emergency Plan entered 0240 Security informs Shift Manager that PA has been breached 0245 Security informs Shift Manager that adversaries have been neutralized No injuries to site personnel No fires or collateral damage to plant equipment No adverse consequences to plant safety Page 12 of 93 On-Shift Staffing An~lysis . Appendix B Analysis #1: DBA/ISG Event #1 -Design Basis Threat TABLE 1 -On-shift Positions Augmentation Line On-shift Position Emergency Plan Reference Elapsed Time (min) 1. Shift Manager SSES E Plan Table 6.1 N/A 2. Unit Supervisor (SRO #1) 1 SSES E Plan Table 6.1 N/A 3. Unit Supervisor (SRO #2) 1 SSES E Plan Table 6.1
* N/A 4. Shift Technical Advisor (STA) SSES E Plan Table 6.1 N/A 5. Plant Control Operator (PCO #1) SSES E Plan Table 6.1 N/A 6. Plant Control Operator (PCO #2) 2 SSES E Plan Table 6.1 N/A 7. Plant Control Operator (PCO #3) SSES E Plan Table 6.1 N/A Page 13 of 93 Emergency Plan, Rev. 62, Page 215 of 295 ECL: Site Area Emergency Role in Unanalyzed TMS Table#/Line#
Task? Required?
: T2/L1 NO NO T5/L 1 T5/L3 T5/L8 T2/L2 NO NO T2/L3 NO NO T2/L4 NO YES T5/L6 T5/L7 T5/L 10 T5/L 11 T5/L 13 T2/L5 NO NO T2/L6 NO NO T5/L5 T5/L9 3 T2/L7 NO NO Emergency Plan, Rev. 62, Page 216 of 295 On-Shift Staffing Analysis Augmentation Role in Unanalyzed TMS Line On-shift Position Emergency Plan Reference Elapsed Time Table#/Line#
Task? Required? (min) 8. Plant Control Operator (PCO #4) 2 SSES E Plan Table 6.1 N/A T2/L8 NO NO 9. Nuclear Plant Operator (NPO #1) SSES E Plan Table 6.1 N/A T2/L9 NO NO 10. SAS Operator SSES E Plan Table 6.1 N/A T5/L 14 NO NO Notes: 1 Unaffected Unit Supervisor functions as the NRC Communicator 2 Unaffected Unit Plant Control Operator functions as E Plan Communicator 3 Refer to Table 2A-PCO available to perform Emerqencv Plan actions after ON/EOP actions Page 14 of 93 Emergency Plan, Rev. 62, Page 217 of 295 On-Shift Staffing Analysis Analysis#
_1 TABLE 2 -Plant Operations
& Safe Shutdown Two Units -One Control Room (Shared) . Applicable to unit -----'-1-'C&'-'2=--
Minimum Operations Crew Necessary to lmplemerit ONs and EOPs, or SAMGs if applicable Line Generic Title/Role On-Shift Position 1. Shift Mana er Shift Mana er 2. Shift Su ervisor Unit Su ervisor SRO #1 3. Shift Su ervisor Unit Su ervisor SRO #2 4. Shift Technical Advisor Shift Technical Advisor STA) 5. Reactor 0 erator #1 Plant Control O erator PC0#1 6. Reactor O erator #2 Plant Control O erator PC0#2 7. Reactor 0 erator #3 Plant Control O erator PC0#3 8. Reactor 0 erator #4 Plant Control O erator PC0#4 9. Auxilia Operator#1 Nuclear Plant O erator NPO #1 I Notes: See Table 2A for ON/EOP actions Page 15 of 93 Task Performance Validation 0 erator Trainin 0 erator Train in 0 erator Train in 0 erator Trainin 0 erator Trainin 0 erator Train in 0 erator Trainin 0 erator Train in O erator Train in Design Basis Threat Procedure Step/Actions Proc/Step Task ON-000-101 Intruder Flow Cart Attach C Step 3.9 PA Announcement Step 3.7 Notify NRC Step 3.11 Rx Scram Attach C Staff RS/DP E0-100-102 RPVControl E0-200-102 Step RC2 Verify Control Rods In RC/L-1 Isolations ECCS Initiations DGsStart RC/L-8 Reset Main Gen Lockouts RC/L-4 Control Rx Water Level RC/P-7 Cool down/Lower Pressure Using BPV ON-100-101 Scram Imminent ON-200-101 Actions Perform Scram Actions until transition to SD Page 16 of 93 Assigned Resource SR01 PC02 STA PC01 PC03 SR02 PC04 SR01 PC01 PC03 PC02 PC04 PC02 PC04 PC01 PC03 PC01 PC03 On-Shift Staffing Analysis Analysis #1, Table 2A -ON/EOP Actions Performance Time (mins) After Procedure Implementation Emergency Plan, Rev. 62, Page 218 of 295 10-15 15-20 20-25 25-30 30-35 35-40 40-45 45-50 50-55 55-60 PC01,2,3,4 PC01 PC03 Emergency Plan, Rev. 62, Page 219 of 295 On-Shift Staffing Analysis Design Basis Threat Procedure Step/Actions Performance Time (mins) After Procedure Implementation Assigned 0-5 5-10 10-15 15-20 20-25 25-30 30-35 35-40 40-45 45-50 50-55 55-60 Proc/Step Task Resource ON-000-010 MaxCRD PC01 X Attach C PC03 ON-000-010 Isolate RWCU PC01 :.*ii ., Attach C PC03 i : ! -Eval EPlan Entry SM and STA ' :x-Attach G StartESWand l/{:f .* PC02 '*" Mitigation List DGs Star!SCC DG NPO 1 **, X.' :'-,.:, Start Supp Pool ,, ' ,, ,, i 'if Cooling PC02 ,,,._ X *,, Page 17 of 93 TABLE 3-Firefighting Emergency Plan, Rev. 62, Page 220 of 295 On-Shift Staffing Analysis Analysis#
1 Line Performed By Task Analysis Controlling Method 1. N/A N/A 2. N/A N/A 3. N/A N/A 4. N/A N/A 5. N/A N/A Notes: No Fire Brigade response required for this event Page 18 of 93 Emergency Plan, Rev. 62, Page 221 of 295 On-Shift Staffing Analysis TABLE 4-Radiation Protection
& Chemistry Analysis#
1 Performance Time Period After Emer~enc, Declaration (minutes)
Line Position Performing Function/Task 0-5-10-15-20-25-30-35-40-45-50-55-60-65-70-75-80-85-5 10 15 20 25 . 30 35 40 45 50 55 60 65 70 75 80 85 90 1. In-Plant Survey (OSC) On-Shift Position:
RP 2. In-Plant Survey (TSC) On-Shift Position:
RP 3. Personnel Monitoring On-Shift Position:
: 4. Job Coverage On-Shift Position:
: 5. Offsite Radiological Assessment On-Shift Position:
RP #1 6. Other Site-Specific RP -Describe:
On-Shift Position:
: 7. Chemistry function/task
#1 -Describe:
Support Field Monitoring Team On-Shift Position:
Chem #1 8. Chemistry function/task
#2 -Describe:
On-Shift Position:
Chem #1 Notes: No RP/Chemistry actions due to "Duck and Cover" mode Page 19 of 93 Emergency Plan, Rev. 62, Page 222 of 295 On-Shift Staffing Analysis TABLE 5 -Emergency Plan Implementation Analysis#
1 Line Function/Task On-Shift Position Task Analysis Controlling Method 1. Declare the Emergency Shift Manager EP/Ops Training and Classification Level (ECL) EP Drill Program 2. Approve Offsite Protective N/A N/A Action Recommendations
: 3. Approve content of State/local Shift Manager EP/Ops Training and notifications EP Drill Program 4. Approve extension to allowable N.A N.A dose limits 5. Notification and direction to PC0#2 EP/Ops Training and on-shift staff (e.g., to assemble, EP Drill Program evacuate, etc.) 6. ERO notification STA EP/Ops Training and EP Drill Program 7. Abbreviated NRC notification STA EP/Ops Training and for DBT event EP Drill Program 8. Complete State/local Shift Manager EP/Ops Training and notification form EP Drill Program 9. Perform State/local notifications PC0#2 EP Training and EP Drill Program 10. Complete NRC event STA EP/Ops Training and notification form EP Drill Program 11. Activate EROS STA EP/Ops Training and EP Drill Program 12. Offsite radiological assessment N/A NIA 13. Perform NRC notifications STA EP/Ops Training and EP Drill Program 14. Perform other site-specific SAS 1 EP/Security Training event notifications (e.g., INPO, and EP Drill Program ANI, etc.) 15. Personnel accountability N/A N/A Notes: Site Area Emergency EAL OS2 EP-PS-100 Emergency Director, Control Room 1Security notifies LLENFBI Page 20 of 93 Emergency Plan, Rev. 62, Page 223 of 295 On-Shift Staffing Analysis Event Timelines and Assumptions Event#4 Control Rod Drop Initial Conditions:
Time: Tuesday @ 0430 Unit 2 Hot Standby, NOP & NOT Sequence of Events: 0430 Mechanical failure causes central Control Rod to drop Valid off-gas pre-treatment High/High RAD Alarm received in Control Room ARM 50 & 51 (CRD No.rth & South) High Alarms received ARM 48 (HPCI Turbine Room) in Alarm ARM 57 (RCIC Room) in Alarm Upgrade to Alert based on ARM 48 & 57 Alarms Page 21 of 93 On-Shift Staffing Analysis Appendix B Analysis #2: DBA/ISG Event #4 -Control Rod Drop TABLE 1 -On-shift Positions Line On-shift Position Emergency Plan Reference
: 1. Shift Manager SSES E Plan Table 6.1 2. Unit Supervisor (SRO #1) 1 SSES E Plan Table 6.1 3. Unit Supervisor (SRO #2) 1 SSES E Plan Table 6.1 4. Shift Technical Advisor (STA) SSES E Plan Table 6.1 5. Plant Control Operator (PCO #2) 2 SSES E Plan Table 6.1 6. Plant Control Operator (PCO #3) SSES E Plan Table 6.1 7. Plant Control Operator (PCO #4) 2 SSES E Plan Table 6.1 8. Nuclear Plant Operator (NPO #2) SSES E Plan Table 6.1 9. Nuclear Plant Operator (NPO #4) SSES E Plan Table 6.1 10. RP Technician (RP #1) SSES E Plan Table 6.1 11. RP Technician (RP #2) SSES E Plan Table 6.1 12. Chemistry Technician (Chem #1) SSES E Plan Table 6.1 Notes: 1 Unaffected Unit Supervisor functions as the NRC Communicator Augmentation Elapsed Time (min) N/A N/A N/A N/A N/A N/A N/A N/A N/A 60 60 60 2 Unaffected Unit Plant Control Operator functions as E Plan Communicator Page 22 of 93 Emergency Plan, Rev. 62, Page 224 of 295 ECL: Unusual Event Alert Role in Unanalyzed TMS Table#/Line#
Task? Required?
T2/L 1 NO NO T5/L 1 T5/L3 T5/L8 T5/L6 NO NO T5/L 10 T5/L 11 T5/L 13 T2/L2 NO NO T2/L3 NO NO T5/L5 NO NO T5/L9 T2/L4 NO NO T2/L5 NO NO T2/L6 NO NO T2/L7 NO NO T4/L5 NO NO T4/L2 NO NO T4/L7 NO NO Emergency Plan, Rev. 62, Page 225 of 295 On-Shift Staffing Analysis TABLE 2 -Plant Operations
& Safe Shutdown Two Units -One Control Room (Shared) Minimum Operations Crew Necessary to Implement ONs and EOPs, or SAMGs if applicable Line Generic Title/Role On-Shift Position 1. Shift Mana er Shift Mana er 2. Shift Su ervisor Unit Su ervisor (SRO #2 3. Shift Technical Advisor Shift Technical Advisor STA 4. Reactor O erator #3 5. Reactor O erator #4 6. Auxilia Nuclear Plant O erator Analysis#
__ 2 ____ _ Applicable to unit _2.....-__ Task Performance Validation 0 erator Trainin O erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin Operator Trainin 7. Auxilia Nuclear Plant O erator NPO #4 0 erator Trainin I Noles: See Table 2A for ON/EOP actions Page 23 of 93 Page 24 of 93 Control Rod Dro Unit #2 Procedure Step/Actions Proc/Ste ON-200-102 E0-200-102, 103 and 104 G0-200-004 Step RC2 RC/L-1 RC/L-8 ON-279-001 ON-279-001 RC/L-4 RC/P-6 RC/P-7 RC/L-4 E0-200-103 ON-200-101 ON-159-002 G0-200-004 Task Place Mode Switch in SID RPVControl Verify Control Rods In Isolations EGGS Initiations DGsStart Reset Main Gen Lockouts Close MSIV and MSL Drains RemoveSJAE from service Control Rx Water Level with HPIC RCIC Maintain Pressure with SRVs Lower pressure usin SRVs Restore Condensate injection and control RPV water level Place RHRin su ool coolin Perform Scram Actions until transition .to SD Verify Isolations Performing SD actions Assigned Resource PC03 SR02 PC03 PC04 PC03 PC04 PC04 PC04 PC04 PC04 PC03 PC03 PC03 PC04 PC03 NP02 NP04 PC03 On-Shift Staffing Analysis Analysis #2, Table 2A -ON/EOP Actions Performance Time (mins) After Procedure Implementation 0-5 5-10 10-15 15-20 20-25 25-30 30-35 Emergency Plan, Rev. 62, Page 226 of 295 35-40 40-45 45-50 50-55 55-60 Emergency Plan, Rev. 62, Page 227 of 295 On-Shift Staffing Analysis Control Rod Dro Unit #2 Procedure Step/Actions Performance Time (mins) After Procedure Implementation Assigned Pree/Ste Task Resource PC04 E0-200-104 Monitoring Rx SR02 Bldg RAD levels PC03 . and Tern StartESWand All coolers with PC03 coolin sources Announce Evac PC02 of U2 Rx Bid Page 25 of 93 TABLE 3-Firefighting Emergency Plan, Rev. 62, Page 228 of 295 On-Shift Staffing Analysis Analysis#
2 Line Performed By Task Analysis Controlling Method 1. N/A N/A 2. N/A NIA 3. N/A N/A 4. N/A N/A 5. N/A N/A Notes: No Fire Brigade response required for this event. Page 26 of 93 Emergency Plan, Rev. 62, Page 229 of 295 On-Shift Staffing Analysis TABLE 4-Radiation Protection
& Chemistry Analysis #2 Performance Time Period After Emercienc Declaration (minutes)
Line Position Performing Function/Task 0-5-10-15-20-25-30-35-40-45-50-55-60-65-70-75-80-5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 1. In-Plant Survey On-Shift Position:
RP 2. Out of Plant Survey X X X X X X X ?< X X X On-Shift Position:
RP #2 3. Personnel Monitoring On-Shift Position:
: 4. Job Coverage On-Shift Position:
: 5. Offsite Radiological Assessment X X X X X X X X X ,X X On-Shift Position:
RP #1 6. Other Site-Specific RP -Describe:
On-Shift Position:
RP 7. Chemistry function/task
#1 -Describe:
Sample and analyze RCS X X X X X X X X X X X X On-Shift Position:
Chem #1 8. Chemistry function/task
#2 -Describe:
On-Shift Position:
Chem #1 Notes: Chemistry self monitors during sampling.
No RP support required.
Chemistry sampling of RCS is from PASS due to isolation of normal sample point. RP #2 relocates Sample Van outside protected area and prepares for monitoring/sampling.
Note that RP#2 may be asked to provide radiological monitoring
/survey by Shift Manager depending upon actual emergency conditions.
This is acceptable since On-site (out-of-plant)
RP Tech is not required until 60 minutes IAW Emergency Plan Table 6.1. CH-ON-007, Chemistry Sampling Team EP-PS-108, RP Tech 1 (OSCAR) EP-PS-130, RP II Dose Calculator Page 27 of 93 85-90 Emergency Plan, Rev. 62, Page 230 of 295 On-Shift Staffing Analysis TABLE 5 -Emergency Plan Implementation Line Function/Task On-Shift Position 1. Declare the Emergency Shift Manager Classification Level (ECL) 2. Approve Offsite Protective N/A Action Recommendations
: 3. Approve content of State/local Shift Manager notifications
: 4. Approve extension to allowable NIA dose limits 5. Notification and direction to PC0#2 on-shift staff (e.g., to assemble, evacuate, etc.) 6. ERO notification SR0#1 7. Abbreviated NRC notification N/A
* for DBT event 8. Complete State/local Shift Manager notification form 9. Perform State/local notifications PC0#2 10. Complete NRC event SR0#1 notification form 11. Activate EROS SR0#1 12. Offsite radiological assessment N/A 13. Perform NRC notifications SR0#1 14. Perform other site-specific N/A event notifications (e.g., INPO, ANI, etc.) 15. Personnel accountability N/A Notes: Unusual Event EAL MU7 7 Alert EAL RA2 or FA1 EP-PS-100 Emergency Director, Control Room Page 28 of 93 Analysis#
2 Task Analysis Controlling Method EP/Ops Training and EP Drill Proqram NIA EP/Ops Training and EP Drill Program N/A EP/Ops Training and EP Drill Program EP/Ops Training and EP Drill Program N/A EP/Ops Training and EP Drill Program EP Training and EP Drill Program EP/Ops Training and EP Drill Program EP/Ops Training and EP Drill Program N/A EP/Ops Training and EP Drill Program N/A N/A Emergency Plan, Rev. 62, Page 231 of 295 On-Shift Staffing Analysis Event Timelines and Assumptions Event#6 MSL Break outside containment isolation Initial Conditions:
Time: Tuesday @ 0430 Unit 2 100% Power, NOP, NOT, NOL Sequence of Events: 0430 Double-ended guillotine MSLB occurs outside secondary containment on A MS Line Break is downstream of the MSL Isolation Valves Rx Scram occurs* MSIVs closed in 5.5 seconds 0432 SRVs open on high vessel pressure SRVs Cycle to maintain pressure at::= 1200 psig 0435:30 Rx water level above core begins to drop slowly Pressure ::= 1200 psig 0505 RxV Level at-161" -ADS initiated 0508 Low pressure ECCS systems initiated Page 29 of 93 On-Shift Staffing Analysis Appendix B Analysis #3: DBA/ISG Event #6 -Steam System Piping Break (MSLB) TABLE 1 -On-shift Positions Augmentation Line On-shift Position Emergency Plan Reference Elapsed Time (min) 1. Shift Manager SSES E Plan Table 6.1 N/A 2. Unit Supervisor (SRO #1) 1 SSES E Plan Table 6.1 N/A 3. Unit Supervisor (SRO #2) 1 SSES E Plan Table 6.1 N/A 4. Shift Technical Advisor (STA) SSES E Plan Table 6.1 N/A 5. Plant Control Operator (PCO #2) 2 SSES E Plan Table 6.1 N/A 6. Plant Control Ooerator (PCO #3) SSES E Plan Table 6.1 N/A 7. Plant Control Operator (PCO #4) 2 SSES E Plan Table 6.1 N/A 8. Nuclear Plant Operator (NPO #2) SSES E Plan Table 6.1 N/A 9. Nuclear Plant Operator (NPO #3) SSES E Plan Table 6.1 N/A 10. Nuclear Plant Operator (NPO #4) SSES E Plan Table 6.1 N/A 11. RP Technician (RP #1) SSES E Plan Table 6.1 60 12. RP Technician (RP #2) SSES E Plan Table 6.1 60 13. Security Officer #1 SSES E Plan Table 6.1 N/A 14. Security Officer #2 SSES E Plan Table 6.1 N/A Notes: 1 Unaffected Unit Supervisor functions as the NRC Communicator 2 Unaffected Unit Plant Control Operator functions as E Plan Communicator Page 30 of 93 Emergency Plan, Rev. 62, Page 232 of 295 ECL: Alert 7 Site Area Emergency Role in Unanalyzed TMS Table#/Line#
Task? Required?
T2/L 1 NO NO T5/L 1 T5/L3 T5/L8 T5/L6 NO NO T5/L9 T5/L 10 T5/L 11 T5/L 13 T2/L2 NO NO T2/L3 NO NO T2/L4 NO NO T2/L5 NO NO T2/L6 NO NO T2/L7 NO NO T2/L8 NO NO T2/L9 NO NO T4/L5 NO NO T4/L2 NO NO T2/L 10 NO NO T5/L 15 NO NO Emergency Plan, Rev. 62, Page 233 of 295 On-Shift Staffing Analysis Analysis # _____ 3 __ _ TABLE 2 -Plant Operations
& Safe Shutdown Two Units -One Control Room (Shared) Applicable to unit _2=----Minimum Operations Crew Necessary to Implement ONs and EOPs, or SAMGs if applicable Line Generic Title/Role On-Shift Position 1. Shift Mana er Shift Mana er 2. Shift Su ervisor Unit Su ervisor SRO #2 3. Shift Technical Advisor Shift Technical Advisor STA 4. Reactor O erator #2 Plant Control O erator 5. Reactor O erator #3 Plant Control O erator 6. Reactor O erator #4 Plant Control O erator 7. Auxilia Nuclear Plant O erator 8. Auxilia Nuclear Plant O erator 9. Auxilia Nuclear Plant 0 erator I Notes See Table 2A for ON/EOP actions Other (non-Operations)
Personnel Necessary to Implement ONs and EOPs, or SAMGs if applicable Line Generic Title/Role On-Shift Position 10. Security Officer Security Officer #1 PC0#2 PC0#3 PC0#4 NP0#2 NP0#3 NP0#4 Notes: Validate steam release from RX building using cameras Page 31 of 93 Task Performance Validation 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin Task Performance Validation Security Traininq Page 32 of 93 On-Shift Staffing Analysis Analysis #3, Table 2A -ON/EOP Actions Steam S stem Pi in Break Outside Containment
-MSLB Unit #2 Procedure Step/Actions Proc/Ste Task ON-200-102 Place Mode Switch in S/D E0-200-102, 103 RPVControl and 104 G0-200-004 Step RC2 Verify Control Rods In RC/L-1 Isolations ECCS Initiations DGs Start RC/L-4 Control Rx Water Level with HPIC RCIC RC/P-6 Maintain Pressure with SRVs RC/P-7 Lower pressure usin SRVs RC/L-4 Use Condensate injection and restore RPV water level E0-200-102 Attempt to feed RC/L-5 using table 5 RC/L-11 subs stems RC/L-10 Line up Low pressure ECCS S stems E0-200-103 Place RHR in SP/T-2 SU ool coolin Restore supp DOI COOiin Assigned Resource PC03 SR02 PC03 PC04 PC04 PC04 PC04 PC03 PC03 PC04 PC04 PC02 PC04 Performance Time (mins) After Procedure Implementation 0-5 5-10 10-15 15-20 20-25 25-30 30-35 Emergency Plan, Rev. 62, Page 234 of 295 35-40 40-45 45-50 50-55 55-60 Emergency Plan, Rev. 62, Page 235 of 295 On-Shift Staffing Analysis Steam Svstem Pioina Break Outside Containment
-MSLB (Unit #2\ Procedure Step/Actions Performance Time (mins) After Procedure Implementation Assigned 0-5 5-10 10-15 15-20 20-25 25-30 30-35 35-40 40-45 45-50 50-55 55-60 Proc/Steo Task Resource E0-200-112 Minus 161 enter : SR02 X : E0-200-112 Prevent ' ... :*, uncontrolled condensate PC03 X eiection .. Verify supp pool PC04 , X {! level *. Open all ADS PC04 X valves Recover level PC03 I;: 'X . with low pressure PC04. ECCS ' ON-200-101 Perform Scram PC03 .. .. '::. ,,Ia \ .. .. ' Actions until PC04 .. '*" ; 1*. '"'"''* transition to SD . .. . .. ON-159-002 Verify Isolations PC03 .x ... G0-200-004 Performing SD NP02 :' * . : * .. . ' '.:::::* ' , .. Y' *;**::: . ~, . . actions NP04 X PC03 PC04 ,. 'j ., . :,,. .. .. * . *'* .... E0-200-104 Monitoring Rx 1, ',**. . : .: .s:: . . , ' . . . .. *, '"* '' Bldg and Turbine SR02 < ~' . . .x Bldg RAD levels PC03 1*.* ': and Temp (: .. :_ .. * *. '*i:' j .:*l* ... , . .. *, .. ,. :.: ,::: .... .:::*' StartESWand
:.;,; All coolers with PC03 x. coolinq sources Announce Evac PC02 /x of U2 Rx Blda : E0-200-105 Notify RP to Perform Offsite SM \.;\ Dose Cales ., Perform post start , .. _;** NP03 X checks on DG .. ' Page 33 of 93 TABLE 3-Firefighting Emergency Plan, Rev. 62, Page 236 of 295 On-Shift Staffing Analysis.
Analysis#
3 Line Performed By Task Analysis Controllina Method 1. N/A N/A 2. N/A NIA 3. NIA N/A 4. N/A N/A 5. N/A N/A Notes: .. No Fire Brigade response required for this event. Page 34 of 93 Emergency Plan, Rev. 62, Page 237 of 295 TABLE 4-Radiation Protection
& Chemistry Line Position Performing Function/Task
: 1. In-Plant Survey On-Shift Position:
RP 2. Out of Plant Survey Relocation Field Monitoring Team Sample Van outside protected area On-Shift Position:
RP #2 3. Personnel Monitoring On-Shift Position:
: 4. Job Coverage On-Shift Position:
: 5. Offsite Radiological Assessment On-Shift Position:
RP #1 6. Other Site-Specific RP -Describe:
On-Shift Position:
: 7. Chemistry function/task
#1 -Describe:
Support Field Monitoring Team On-Shift Position:
Chem #1 8. Chemistry function/task
#2 -Describe:
On-Shift Position:
Chem #1 Notes: Chemistry post trip sampling after ERO augmentation EP-PS-108, RP Tech 1 (OSCAR) EP-PS-130, RP II Dose Calculator On-Shift Staffing Analysis Analysis #3 Performance Time Period After Emerttenc, Declaration (minutes) 0-5-10-15-20-25-30-35-40-45-50-55-60-65-70-75-5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 X X X X X X X X X X X X X X X X X X X X X X X X Note that RP#2 may be asked to provide radiological monitoring
/survey by Shift Manager depending upon actual emergency conditions.
This is acceptable since On-site (out-of-plant)
RP Tech is not required until 60 minutes IAW Emergency Plan Table 6.1. Page 35 of 93 80-85-85 90 Emergency Plan, Rev. 62, Page 238 of 295 On-Shift Staffing Analysis TABLE 5-Emergency Plan Implementation Line Function/Task On-Shift Position 1. Declare the Emergency Shift Manager Classification Level (ECL) 2. Approve Offsite Protective N/A Action Recommendations
: 3. Approve content of State/local Shift Manager notifications
: 4. Approve extension to allowable N/A dose limits 5. Notification and direction to PC0#2 on-shift staff (e.g., to assemble, evacuate, etc.) 6. ERO notification SR0#1 7. Abbreviated NRC notification N/A for DBT event 8. Complete State/local Shift Manager notification form 9. Perform State/local notifications SR0#1 10. Complete NRC event SR0#1 notification form 11. Activate EROS SR0#1 12. Offsite radiological assessment N/A 13. Perform NRC notifications SR0#1 14. Perform other site-specific N/A event notifications (e.g., INPO, ANI, etc.) 15. Personnel accountability Security Officer #2 Notes: Alert EAL FA1 7 Site Area Emergency EAL FS1 EP-PS-100 Emergency Director, Control Room Page 36 of 93 Analysis#
3 Task Analysis Controlling Method EP/Ops Training and EP Drill Program N/A EP/Ops Training and EP Drill Proaram N/A EP/Ops Training and EP Drill Program EP/Ops Training and EP Drill Program N/A EP/Ops Training and EP Drill Program EP Training and EP Drill Program EP/Ops Training and EP Drill Program EP/Ops Training and EP Drill Program NIA EP/Ops Training and EP Drill Program N/A EP/Security Training and EP Drill Program Emergency Plan, Rev. 62, Page 239 of 295 On-Shift Staffing Analysis Event Timelines and Assumptions Event#? Large break LOCA with release exceeding PAGs and resulting in PARs Initial Conditions:
Time: Tuesday @ 0430 Unit 2 100% Power, NOP & NOT Sequence of Events: 0430 Large Break LOCA occurs -Recirc Line Break Loss of Normal AC power occurs coincident with break 0435 Reactor Level -205 inches. Drywell pressure 18.5psig 0500 Dose Projection indicates 1.1 R/hr at Emergency Plan Boundary (EPB) Page 37 of 93 On-Shift Staffing Analysis Appendix B Emergency Plan, Rev. 62, Page 240 of 295 Analysis #4: DBA/ISG Event #7 -Large Break LOCA with release and PARs ECL: Site Area Emergency General Emergency TABLE 1 -On-shift Positions Augmentation Line On-shift Position Emergency Plan Reference Elapsed Time (min) 1. Shift Manager SSES E Plan Table 6.1 N/A 2. Unit Supervisor (SRO #1) 1 SSES E Plan Table 6.1 N/A 3. Unit Supervisor (SRO #2) 1 SSES E Plan Table 6.1 N/A 4. Shift Technical Advisor (STA) SSES E Plan Table 6.1 N/A 5. Plant Control Operator (PCO #2) 2 SSES E Plan Table 6.1 N/A 6. Plant Control Operator (PCO #3) SSES E Plan Table 6.1 N/A 7. Plant Control Operator (PCO #4) 2 SSES E Plan Table 6.1 N/A 8. Nuclear Plant Operator (NPO #4) SSES E Plan Table 6.1 N/A 9. RP Technician (RP #1) SSES E Plan Table 6.1 60 10. RP Technician (RP #2) SSES E Plan Table 6.1 60 11. CAS Operator SSES E Plan Table 6.1 N/A Notes: 1 Unaffected Unit Supervisor functions as the NRC Communicator 2 Unaffected Unit Plant Control Operator functions as E Plan Communicator 3 PCO is available to make offsite communications at GE (See Table 2A) Page 38 of 93 Role in Unanalyzed TMS Table#/Line#
Task? Required?
T2/L 1 NO NO T5/L 1 T5/L2 T5/L3 T5/L4 T5/L8 T5/L5 NO NO T5/L6 T5/L9 T5/L 10 T5/L 11 T5/L 13 T2/L2 NO NO T2/L3 NO NO T2/L4 NO NO T5/L9 3 T2/L5 NO NO T2/L6 NO NO T2/L7 NO NO T4/L6 NO NO T4/L2 NO NO T4/L3 T5/L 15 NO NO Emergency Plan, Rev. 62, Page 241 of 295 On-Shift Staffing Analysis TABLE 2 -Plant Operations
& Safe Shutdown Analysis#
____ 4 ____ _ Two Units -One Control Room (Shared) . Applicable to unit ___ 2=----Minimum Operations Crew Necessary to Implement ONs and EOPs, or SAMGs if applicable Line Generic Title/Role On-Shift Position 1. Shift Mana er Shift Mana er 2. Shift Su ervisor Unit Su ervisor SRO #2 3. Shift Technical Advisor Shift Technical Advisor STA 4. Reactor O erator #2 Plant Control O erator PC0#2 5. Reactor O erator #3 Plant Control O erator 6. Reactor O erator #4 Plant Control O erator 7. Auxilia Nuclear Plant Operator NP0#4 I Notes: See Table 2A for ON/EOP actions Page 39 of 93 Task Performance Validation 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Training Page 40 of 93 On-Shift Staffing Analysis Analysis #4, Table 2A -ON/EOP Actions Loss of Coolant Accident Inside Containment (Unit #2) Procedure Step/Actions Performance Time (mins) After Procedure Implementation Assigned 0-5 5-10 10-15 15-20 20-25 25-30 30-35 Proc/Step Task Resource ON-200-102 Place Mode Switch PC03 ::.x' in SID E0-200-102, RPVControl SR02 .,*: X 103 -I', . Step RC2 Verify Control Rods PC03 tJ< ... ' In RC/L-1 Isolations I ECCS Initiations PC04 DGs Start E0-200-112 Minus 161 enter SR02 E0-200-112
: Prevent uncontrolled PC03 *?X. condensate iniection
-Verify supp pool PC04 X level I** Vertfy that all ADS PC04 X valves are open Recover level with PC03 .x low pressure ECCS PC04 , ... I: *: Start standby Liquid control and PC03 . maximize CRD .. * .,, E0-200-103 Commence Dry Well PC03 } .; . *. . . . ,;f:i~i Soravs .. *x*:* *:. .. . , ", " , Commence Supp ... *. X .:*. ,, Pool coolina PC02 ' .. , .. .. Start H2 Analyzers PC03 :X: .t E0-200-102 Line up RHR service PC02 water to RHR heat PC03 'x exchanaers DG post start checks NP04 X Emergency Plan, Rev. 62, Page 242 of 295 35-40 40-45 45-50 50-55 55-60
*, .,. . :
TABLE 3 -Firefighting Emergency Plan, Rev. 62, Page 243 of 295 On-Shift Staffing Analysis Analysis #4 Line Performed By Task Analysis Controlling Method 1. N/A N/A 2. N/A N/A 3. N/A N/A 4. N/A N/A 5. N/A N/A Notes: No Fire Brigade response required for this event. Page 41 of 93 Emergency Plan, Rev. 62, Page 244 of 295 On-Shift Staffing Analysis TABLE 4-Radiation Protection
& Chemistry Analysis #4 Performance Time Period After Emergencu Declaration (minutes)
Line Position Performing Function/Task
: 1. In-Plant Survey On-Shift Position:
RP 2. Out of Plant Survey Move Field Monitoring Team Van outside PA On-Shift Position:
RP #2 3. Out of Plant Survey Perform surveys (Near Site) On-Shift Position:
RP #2 4. Personnel Monitoring On-Shift Position:
: 5. Job Coverage On-Shift Position:
: 6. Offsite Radiological Assessment On-Shift Position:
RP #1 7. Other Site-Specific RP -Describe:
On-Shift Position:
: 8. Chemistry function/task
#1 -Describe:
Monitoring Team On-Shift Position:
Chem #1 9. Chemistry function/task
#2 -Describe:
On-Shift Position:
Chem #1 Notes: EP-PS-108, RP Tech I (OSCAR) EP-PS-130, RP II Dose Calculator Support Field 0-5-10-5 10 15 X X X X X X 15-20-25-30-35-40-45-50-55-60-65-70-20 25 30 35 40 45 50 55 60 65 70 75 X X X X X X X X X X X X X X Note that RP#2 may be asked to provide radiological monitoring
/survey by Shift Manager depending upon actual emergency conditions.
This is acceptable since On-site (out-of-plant)
RP Tech is not required until 60 minutes IAW Emergency Plan Table 6.1. Page 42 of 93 75-80 80-85-85 90 Emergency Plan, Rev. 62, Page 245 of 295 On-Shift Staffing Analysis TABLE 5-Emergency Plan Implementation Line Function/Task On-Shift Position 1. Declare the Emergency Shift Manager Classification Level (ECL) 2. Approve Offsite Protective Shift Manager Action Recommendations
: 3. Approve content of State/local Shift Manager notifications
: 4. Approve extension to allowable Shift Manager dose limits 5. Notification and direction to SR0#1 on-shift staff (e.g., to assemble, evacuate, etc.) 6. ERO notification SR0#1 7. Abbreviated NRC notification N/A for DBT event 8. Complet~ State/local Shift Manager notification form 9. Perform State/local notifications SRO #1 @SAE' PC0#2@GE 10. Complete NRC event SR0#1 notification form 11. Activate EROS SR0#1 12. Offsite radiological assessment N/A 13. Perform NRC notifications SR0#1 14. Perform other site-specific N/A 1 event notifications (e.g., INPO, ANI, etc.) 15. Personnel accountability CAS Operator
* Notes: Site Area Emergency EAL FS1 7 General Emergency EAL RG1 EP-PS-100 Emergency Director, Control Room Analysis #4 Task Analysis Controlling Method EP/Ops Training and EP Drill Program EP/Ops Training and EP Drill Promam EP/Ops Training and EP Drill Prooram EP/Ops Training and EP Drill Prooram EP/Ops Training and EP Drill Program EP/Ops Training and EP Drill Program N/A EP/Ops Training and EP Drill Program EP Training and EP Drill Program EP/Ops Training and EP Drill Program EP/Ops Training and EP Drill Program N/A EP/Ops Training and EP Drill Program N/A EP/Security Training and EP Drill Program 1 Shift Manager notifies Senior State Official of PARs. Com.pletion of notification within approximately 1 minute. Page 43 of 93 Event #10 ATWS Initial Conditions:
Time: Tuesday @ 0430 Emergency Plan, Rev. 62, Page 246 of 295 On-Shift Staffing Analysis Event Timelines and Assumptions Unit 1 100% Power, NOP & NOT Sequence of Events: 0430 MS IVs close. Reactor does not trip. Supplemental and/or manual trip actions are successful.
Page 44 of 93 Analysis #5: DBA/ISG Event #10 -A TWS TABLE 1 -On-shift Positions Line On-shift Position 1. Shift Manager 2. Unit Supervisor (SRO #1) 1 3. Unit Supervisor (SRO #2) 1 4. Shift Technical Advisor (STA) 5. Plant Control Operator (PCO #1) 6. Plant Control Operator (PCO #2) 2 7. Plant Control Operator (PCO #4) 2 8. Nuclear Plant Operator (NPO #1) 9. Nuclear Plant Operator (NPO #3) On-Shift Staffing Analysis Appendix B Augmentation Emergency Plan Reference Elapsed Time (min) SSES E Plan Table 6.1 N/A SSES E Plan Table 6.1 N/A SSES E Plan Table 6.1 N/A SSES E Plan Table 6.1 N/A SSES E Plan Table 6.1 N/A SSES E Plan Table 6.1 N/A SSES E Plan Table 6.1 N/A SSES E Plan Table 6.1 N/A SSES E Plan Table 6.1 N/A Notes: 1 Unaffected Unit Supervisor functions as the NRC Communicator 2 Unaffected Unit Plant Controf Operator functions as E Plan Communicator Page 45 of 93 Emergency Plan, Rev. 62, Page 247 of 295 ECL: Alert Role in Unanalyzed TMS Table#/Line#
Task? Required?
T2/L1 NO NO T5/L 1 T5/L3 T5/L8 T2/L2 NO NO T5/L5 T5/L6 NO NO T5/L 10 T5/L 11 T5/L 13 T2/L3 NO NO T2/L4 NO NO T2/L5 NO NO T5/L9 NO NO T2/L6 NO NO T2/L7 NO NO Emergency Plan, Rev. 62, Page 248 of 295 On-Shift St~ffing Analysis TABLE 2 -Plant Operations
& Safe Shutdown Analysis#
_5 __ _ Two Units -One Control Room (Shared) , Applicable to unit _1 __ _ Minimum Operations Crew Necessary to Implement ONs and EOPs, or SAMGs if applicable Line Generic Title/Role On-Shift Position 1. Shift Mana er Shift Mana er 2. Shift Su ervisor Unit Su ervisor SRO #1 3. Shift Technical Advisor Shift Technical Advisor STA 4. Reactor 0 erator #1 Plant Control O erator PC0#1 5. Reactor 0 erator #2 Plant Control O erator PC0#2 6. Auxilia Nuclear Plant O erator NP0#1 7. Auxilia Nuclear Plant O erator NP0#3 I Notes See Table 2A for ON/EOP actions Page 46 of 93 Task Performance Validation 0 13rator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin ATWS Procedure Step/Actions Assigned Proc/Steo Task Resource E0-100-113 Place Mode PC01 Switch in SID Verify all rods IN PC01 Transition to SR01 E0-100-102 E0-100-102 RPVControl SR01 Step RC2 Verify Control PCO 1 Rods In RC/L-1 Isolations ECCS PC02 Initiations DGs Start RC/L-8 Reset Main PC02 Gen Lockouts RC/L-4 Control Rx Water Level PC02 with HPIC RCIC RC/P-6 Maintain PC02 Pressure with SRVs RC/P-6 Maintain Pressure with PC02 HPIC RC/P-7 Cool down PC02 usina HPCI RC/L-4 Restore Condensate injection and PC01 control RPV water level E0-100-103 Place RHR in supp pool PC01 coolina Page 47 of 93 On-Shift Staffing Analysis Analysis #5, Table 2A -ON/EOP Actions Performance Time (mins) After Procedure Implementation 0-5 5-10 10-15 15-20 20-25 25-30 30-35 r'}:,X : I! , ,, X :,* .. x *x I, L ,, 1,: ' X ,, ,, >, k ,,;*.' ,' ,,, X '. 1*. . . . ' I'<-*" . :Jlt 1~I: : . IL:,.Jf'./
*. ' ,, .* ,', X , . Emergency Plan, Rev. 62, Page 249 of 295 35-40 40-45 45-50 50-55 55-60
"',,*'* :-, .h:; X ,, .. ' --' .. )(" . " , -" .* '.;)t i " , , . , * . I I Emergency Plan, Rev. 62, Page 250 of 295 On-Shift Staffing Analysis ATWS Procedure Step/Actions Performance Time (mins) After Procedure Implementation Assigned Proc/Ste Task Resource ON-100-101 Perform PCO 1 Scram Actions PC02 until transition to SD ON-159-002 Recover from PCO 1 Isolations NP01 G0-100-004 Performing NPO 1 SD actions NP03 Page 48 of 93 TABLE 3 -Firefighting Emergency Plan, Rev. 62, Page 251 of 295 On-Shift Staffing Analysis Analysis#
5 Line Performed By Task Analysis Controllina Method 1. N/A N/A 2. N/A N/A 3. N/A N/A 4. N/A N/A 5. N/A N/A Notes: No Fire Brigade response required for this event. Page 49 of 93 Emergency Plan, Rev. 62, Page 252 of 295 On-Shift Staffing Analysis TABLE 4-Radiation Protection
& Chemistry Analysis #5 Performance Time Period After Emergenq Declaration (minutes)
Line Position Performing Function/Task 0-5-10-15-20-25-30-35-40-45-50-55-60-65-70-75-80-85-5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 1. In-Plant Survey On-Shift Position:
RP 2. Out of Plant Survey On-Shift Position:
RP #2 ' 3. Personnel Monitoring On-Shift Position:
: 4. Job Coverage On-Shift Position:
: 5. Offsite Radiological Assessment On~Shift Position:
RP #1 6. Other Site-Specific RP -Describe:
On-Shift Position:
: 7. Chemistry function/task
#1 -Describe:
Support Field Monitoring Team On-Shift Position:
Chem #1 8. Chemistry function/task
#2 -Describe:
On-Shift Position:
Chem #1 Notes: RP & Chemistry report to Control Room for direction from Shift Manager Chemistry Post Trip Sampling after ERO augmentation (required within 12 hours of shutdown)
Page 50 of 93 Emergency Plan, Rev. 62, Page 253 of 295 On-Shift Staffing Analysis TABLE 5-Emergency Plan Implementation Analysis#
5 Line Function/Task On-Shift Position Task Analysis Controlling Method 1. Declare the Emergency Shift Manager EP/Ops Training and Classification Level (EGL) EP Drill Program 2. Approve Offsite Protective N/A N/A . Action Recommendations
: 3. Approve content of State/local Shift Manager EP/Ops Training and notifications EP Drill Proqram 4. -Approve extension to allowable N/A NIA dose limits 5. Notification and direction to SR0#1 EP/Ops Training and on-shift staff (e.g., to assemble, EP Drill Program
* evacuate, etc.) 6. ERO notification SR0#2 EP/Ops Training and EP Drill Program 7. Abbreviated NRG notification N/A N/A for DBT event 8. Complete State/local Shift Manager EP/Ops Training and notification form EP Drill Program -. 9. Perform State/local notifications PG0#4 EP training and EP Drill Program 10. Complete NRC event SR0#2 EP/Ops Training and notification form EP Drill Program 11. Activate EROS SR0#2. EP/Ops Training and EP Drill Program 12. Offsite radiological assessment N/A N/A 13. Perform NRC notifications SR0#2 EP/Ops Training and EP Drill Program 14. Perform other site-specific N/A N/A *' event notifications (e.g., INPO, ANI, etc.) 15. Personnel accountability N/A N/A Notes: Alert EAL MA EP-PS-100 E:mergency rnrector, Control Room Page 51 of 93 Emergency Plan, Rev. 62, Page 254 of 295 On-Shift Staffing Analysis Event Timelines and Assumptions Event #11 Response actions for an "aircraft probable threat" in accordance with 1 OCFR50.54(hh)(1)
Initial Conditions:
Time: Monday@2100 Unit 1 &2 100% Power, NOP & NOT Sequence of Events: 2100 Aircraft probable threat call received from NRC ~eadquarters.
Call is verified.
Aircraft is == 25 minutes from site Page 52 of 93 On-Shift Staffing Analysis Appendix B Analysis #6: DBA/ISG Event #11 -Aircraft Probable Threat TABLE 1 -On-shift Positions Augmentation Line On-shift Position Emergency Plan Reference Elapsed Time (min) 1. Shift Manager SSES E Plan Table 6.1 N/A 2. Unit Supervisor (SRO #1) 1 SSES E Plan Table 6.1 N/A 3. Unit Supervisor (SRO #2) 1 SSES E Plan Table 6.1 N/A 4. Shift Technical Advisor (STA) SSES E Plan Table 6.1 N/A 5. Plant Control Operator (PCO #1) SSES E Plan Table 6.1 N/A 6. Plant Control Operator (PCO #2) 2 SSES E Plan Table 6.1 N/A 7. Plant Control Operator (PCO #3) SSES E Plan Table 6.1 N/A 8. Plant Control Operator (PCO #4) 2 SSES E Plan Table 6.1 N/A 9. Nuclear Plant Operator (NPO #1) SSES E Plan Table 6.1 N/A 10. Security Officer #1 SSES E Plan Table 6.1 N/A 11. Security Officer #2
* SSES E Plan Table 6.1 N/A Notes: 1 Unaffected Unit Supervisor functions as the NRC Communicator 2 Unaffected Unit Plant Control Operator functions as E Plan Communicator Emergency Plan, Rev. 62, Page 255 of 295 ECL: Alert Role in Unanalyzed TMS Table#/Line#
Task? Required?
T2/L 1 NO NO T5/L 1 T5/L3 T5/L8 T2/L2 NO NO T5/L6 NO NO T5/L 10 T5/L 11 T5/L 13 T2/L3 NO NO T2/L4 NO NO T2/L5 NO NO T5/L5 T2/L6 NO NO T2/L7 NO NO T5/L9 3 T2/L8 NO NO T2/L9 NO NO T5/L 14 NO NO 3 Refer to Table 2A -PCO available to perform EmerQency Plan actions after ON/EOP actions. Page 53 of 93 Emergency Plan, Rev. 62, Page 256 of 295 On-Shift Staffing Analysis Analysis # _6 _____ _ TABLE 2 -Plant Operations
& Safe Shutdown Two Units -One Control Room (Shared) Applicable to unit 1 & 2 Minimum Operations Crew Necessary to Implement ONs and EOPs, or SAMGs if applicable Line Generic Title/Role On-Shift Position 1. Shift Mana er Shift Mana er 2. Shift Su ervisor Unit Su ervisor SRO #1 3. Shift Technical Advisor Shift Technical Advisor STA) 4. Reactor O erator #1 Plant Control 0 erator PC0#1 5. Reactor O erator #2 Plant Control 0 erator PC0#2 6. Reactor 0 erator #3 Plant Control 0 erator PC0#3 7. Reactor 0 erator #4 Plant Control 0 erator PC0#4 8. Auxilia 0 erator#1 Nuclear Plant O erator NPO #1 I Notes See Table 2A for ON/EOP actions Other (non-Operations)
Personnel Necessary to Implement ONs and EOPs, or SAMGs if applicable Line Generic Title/Role On-Shift Position 9. Security Officer Security Officer #1 Task Performance Validation O erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Train in 0 erator Train in 0 erator Trainin Task Performance Validation Security Training Notes: Extinguish interior (PA) plant lighting and preps to extinguish exterior plant lighting Page 54 of 93 Aircraft Threat Procedure Step/Actions Proc/Steo Task ON-000-010 PA Stec 3.9 Announcement ON-000-010 Direct ON-000-010 actions ON-000-010 Establish Attach D Communications with NRC Isolate RWCU (both Units) Perform Scram Imminent Actions Maximize CRD Place CREOASS in Recirc Eval E Plan Entry Extinguish Interior (PA) Lights and Prep to Extinguish Exterior Liqhts ON-000-010 Star!ESWand Attach G DG Star!SCC DG Supp Pool Cooling in Service Page 55 of 93 On-Shift Staffing Analysis Analysis #6, Table 2A -ON/EOP Actions Performance Time (mins) After Procedure Implementation Assigned 0-5 5-10 10-15 15-20 20-25 25-30 30-35 Resource PC02 :X ,, ; : ... :*:-,:t. .. *-~>~:;~;
: * ;.~r" . SR01 . , .. . "* .. ... , .. *x STA '"****: ... PC01 : X * .. PC03 PCO 1-4 X PC02 ;'.},: PC04 :,. PC02 X SM and x: ,. STA .... .: : SAS X *. 1.**, .... fq:,, PC02 X NP01 :x PC02 .*.}Jd PC04 Emergency Plan, Rev. 62, Page 257 of 295 35-40 40-45 45-50 50-55 55-60 *::"Frt: .. .*){ .. * :::,: ' ?:: . ' ..
TABLE 3 -Firefighting Emergency Plan, Rev. 62, Page 258 of 295 On-Shift Staffing Analysis Analysis#
6 Line Performed By Task Analysis Controlling Method 1. N/A N/A 2. N/A N/A 3. N/A N/A 4. N/A N/A 5. N/A N/A Notes: No Fire Brigade response required for this event. Personnel evacuate target buildings.
Initiate "Duck and Cover'' Page 56 of 93 Emergency Plan, Rev. 62, Page 259 of 295 On-Shift Staffing Analysis TABLE 4-Radiation Protection
& Chemistry Analysis#
6 Performance Time Period After Emen1enc*1 Declaration (minutes)
Line Position Performing Function/Task 0-5-10-15-20-25-30-35-40-45-50-55-60-65-70-75-80-85-5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 1. In-Plant Survey On-Shift Position:
RP 2. Out of Plant Survey On-Shift Position:
RP #2 3. Personnel Monitoring On-Shift Position:
: 4. Job Coverage On-Shift Position:
: 5. Offsite Radiological Assessment On-Shift Position:
RP #1 6. Other Site-Specific RP -Describe:
On-Shift Position:
: 7. Chemistry function/task
#1 -Describe:
Support Field Monitoring Team On-Shift Position:
Chem #1 8. Chemistry function/task
#2 -Describe:
On-Shift Position:
Chem #1 Notes: RP/Chemistry are in "Duck and Cover" Mode. Page 57 of 93 Emergency Plan, Rev. 62, Page 260 of 295 On-Shift Staffing Analysis TABLE 5 -Emergency Plan Implementation Analysis#
6 Line Function/Task On-Shift Position Task Analysis Controlling Method 1. Declare the Emergency Shift Manager EP/Ops Training and Classification Level (ECL) EP Drill Program 2. Approve Offsite Protective N/A N/A Action Recommendations
: 3. Approve content of State/local Shift Manager EP/Ops Training and notifications EP Drill Program 4. Approve extension to allowable N/A N/A dose limits 5. Notification and direction to PC0#2 EP/Ops Training and on-shift staff (e.g., to assemble, EP Drill Program evacuate, etc.) 6. ERO notification SR0#2 EP/Ops Training and EP Drill Program 7. Abbreviated NRC notification N/A N/A for DBT event 8. Complete State/local Shift Manager EP/Ops Training and notification form EP Drill Program 9. Perform State/local notifications PC0#4 EP Training and EP Drill Program 10. Complete NRC event SR0#2 EP/Ops Training and notification form EP Drill Program 11. Activate EROS SR0#2 EP/Ops Training and EP Drill Program 12. Offsite radiological assessment N/A N/A 13. Perform NRC notifications SR0#2 EP/Ops Training and EP Drill Program 14. Perform other site-specific Security Officer #2 EP/Security Training event notifications (e.g., INPO, and EP Drill Program ANI, etc.) 15. Personnel accountability N/A N/A Notes: Alert EAL OA2 EP-PS-100 Emergency Director, Control Room Page 58 of 93 Emergency Plan, Rev. 62, Page 261 of 295 On-Shift Staffing Analysis Event Timelines and Assumptions Event#12 Control room fire leading to evacuation and remote shutdown Initial Conditions:
Time: Monday @ 0330 Unit 1 &2 100% Power, NOP & NOT Sequence of Events: 0330 Smoke, sparks and flames observed coming from back of control board Fire Brigade activated 0332 Fire Operations attempt to extinguish flames without success -fire and smoke affects operation of both units 1 &2 0340 Decision to evacuate Control Room 1 &2 Page 59 of 93 On-Shift Staffing Analysis Appendix B Analysis #7: DBA/ISG Event #12 -Control Room Fire w/Evacuation
& Remote Shutdown TABLE 1 -On-shift Positions
* Augmentation Emergency Plan, Rev. 62, Page 262 of 295 ECL: Alert Role in Unanalyzed TMS Line On-shift Position Emergency Plan Reference Elapsed Time (min) Table#/Line#
Task? Required?
: 1. Shift Manager SSES E Plan Table 6.1 N/A T2/L1 NO NO T5/L 1 T5/L3 T5/L8 2. Unit Supervisor (SRO #1) 1 SSES E Plan Table 6.1 N/A T2/L2 NO NO T5/L5 3. Unit Supervisor (SRO #2) 1 SSES E Plan Table 6.1 N/A T2/L3 NO NO 4. Shift Technical Advisor (STA) SSES E Plan Table 6.1 N/A T2/L4 NO YES T5/L6 T5/L9 TSiL 10 T5/L 13 5. Field Unit Supervisor (FBL) 2 SSES E Plan Table 6.1 N/A T3/L 1 NO NO 6. Plant Control Operator (PCO #1) SSES E Plan Table 6.1 N/A T2/L5. NO NO 7. Plant Control Operator (PCO #2) 3 SSES E Plan Table 6.1 N/A T2/L6 NO NO 8. Plant Control Operator (PCO #3) SSES E Plan Table 6.1 N/A T2/L7 NO NO 9. Plant Control Operator (PCO #4) 3 SSE$ E Plan Table 6.1 N/A T2/L8 NO NO 10. Nuclear Plant Operator (NPO #1) SSES E Plan Table 6.1 N/A T2/L9 NO NO 11. Nuclear Plant Operator (NPO #2) SSES E Plan Table 6.1 N/A T2/L 10 NO NO 12. Nuclear Plant Operator (NPO #3) SSES E Plan Table 6.1 N/A T2/L 11 NO NO Page 60 of 93 Emergency Plan, Rev. 62, Page 263 of 295 On-Shift Staffing Analysis Augmentation Role in Unanalyzed TMS Line On-shift Position Emergency Plan Reference Elapsed Time Table#/Line#
Task? Required? (min) 13. Nuclear Plant Operator (NPO #4) SSES E Plan Table 6.1 N/A T2/L 12 NO NO 14. Maintenance Site Support Services SSES E Plan Table 6.1 N/A T3/L2 NO NO Handvman #1 (FBM #1) 15. Maintenance Site Support Services SSES E Plan Table 6.1 N/A T3/L3 NO NO Handvman #2 (FBM #2) -16. Maintenance Site Support Services SSES E Plan Table 6.1 N/A T3/L4 NO NO Handvman #3 (FBM #3) 17. Maintenance Site Support Services SSES E Plan Table 6.1 N/A T3/L5 NO NO Handvman #4 (FBM #4) Notes: 1 Unaffected Unit Supervisor functions as the NRG Communicator 2 Functions as Fire Brigade Leader during fire related response events 3 Unaffected Unit Plant Control Operator functions as E Plan Communicator Page 61 of 93 Emergency Plan, Rev. 62, Page 264 of 295 On-Shift Staffing Analysis Analysis#
____ 7 __ _ TABLE 2 -Plant Operations
& Safe Shutdown Two Units -One Control Room (Shared) Applicable to unit 1 & 2 Minimum Operations Crew Necessary to Implement ONs and EOPs, or SAMGs if applicable Line Generic Title/Role On-Shift Position 1. Shift Mana er Shift Mana er 2. Shift Su ervisor Unit Su ervisor SR0#1 3. Shift Su ervisor Unit Su ervisor SRO #2 4. Shift Technical Advisor Shift Technical Advisor STA 5. Reactor O erator #1 Plant Control O erator PC0#1 6. Reactor 0 erator #2 Plant Control 0 erator PC0#2 7. Reactor O erator #3 Plant Control Operator PC0#3 8. Reactor O erator #4 Plant Control O erator PC0#4 9. Auxilia erator #1 Nuclear Plant O erator NP0#1 10. Auxilia erator #2 Nuclear Plant O erator NP0#2 11. Auxilia erator#3 Nuclear Plant O erator NP0#3 12. Auxilia Operator#4 Nuclear Plant O erator NPO #4) I Notes: See Table 2A for ON/EOP actions Page 62 of 93 Task Performance Validation 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin Operator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Train in 0 erator Trainin Control Room Fire with Evacuation Procedure Step/Actions Assigned Proc/Step Task Resource ON-1 (2)00-009 Notify Security and SR01 PA announcement Step 3.2 Activate ERO or Alt STA ERO Insert Scram and verify Control Rods PC01 SRMand IRMs PC03 Inserted Close MSIVs PC02 PC04 Placing FW in PC01 startup level PC03 control Isolate RWCU PC01 PC03 Startup HPCI and PC02 RCIC PC04 Obtain keys and SR01 take EOP boards SR02 currentlv in use ON-1 (2)00-009 EvacCR All Step 3.3 Step 4.3.1 Start Laptop PCO 1 PC03 Step 4.3.2 Transfer Switch PC02 Lineup PC04 4.3.3 Notify SM when SR01 transferred SR02 N/A SM and STA report SM/STA toOCC 4.3.4 lsolateA-D NPO 1 ESS bus feeder NP02 breakers from CR 4.3.5 Isolate RSR Service water flow NP03 thru appropriate NP04 RHR heat exchanaers Page 63 of 93 On-Shift Staffing Analysis Analysis #7, Table 2A -ON/EOP Actions Performance Time (mins) After Procedure Implementation 0-5 5-10 10-15 15-20 20-25 25-30 30-35 :~. }:,i:;: ,. ' X* /'.\.: ;r;i::,, *. ,X. X ... l::*'Jf;, .. ' X r, ,,,.* . ' ''*l~} . **;,.x ,{ X .. .*.* ., X . .:, .. X *. "*; ,* **'. /,, .:,.-.x ;*;<:''.;'it
*' Emergency Plan, Rev. 62, Page 265 of 295 35-40 40-45 45-50 50-55 55-60 .. X ,.* Ii ...
Emergency Plan, Rev. 62, Page 266 of 295 On-Shift Staffing Analysis Control Room Fire with Evacuation Procedure Step/Actions Performance Time (mins) After Procedure Implementation Assigned 0-5 5-10 10-15 15-20 20-25 25-30 30-35 35-40 1 40-45 45-50 50-55 55-60 Proc/Steo Task Resource 4.3.6 -4.3.7 Verify MSIV and PC01 MSL drains are PC03 1,* *X closed Monitor Plant PC01 i,.x,. Parameters PC03 . 4.5.1 Disable CR HMIS NPO 1 interfaces x* 4.5.2 Verify Control . *x . ::{ Structure HVAC NP02 ooeratinQ
':!_ A 4.6 Control Rx Press PCO 1 ;, ** f/r:c*, r;;f.)' }\,:, , ; *_ :;* i. r *_ ... ,:/fafi\(\~:, ; ** ,, from Remote SDP PC03 ,, , . , : , Verify Instrument NP03 ', )(' Qas in service NP04 ,, Verify all Turbines NP03 '*'':*'.., tripped NP04 X , , E0-1(2)00-102 Maintain Rx Water '* PCO 1 OP-1 (2)50-001 Level with RCIC -. X ,, PC03 : Step 2.15 , ,, , E0-1(2)00-102 Take Scram PCO 1-4 : ON-1(2)00-101 Actions :x Page 64 of 93 Emergency Plan, Rev. 62, Page 267 of 295 On-Shift Staffing Analysis TABLE 3 -Firefighting Analysis#
7 Line Performed By Task Analysis Controlling Method 1. Field Unit Supervisor (FBL) Fire Briqade Traininq 2. Maintenance Site Support Services Fire Brigade Training Handyman #1 (FBM #1) 3. Maintenance Site Support Services Fire Brigade Training Handyman #2 (FBM #2) 4. Maintenance Site Support Services Fire Brigade Training Handyman #3 (FBM #3) 5. Maintenance Site Support Services Fire Brigade Training Handyman #4 (FBM #4) I Notes: Page 65 of 93 Emergency Plan, Rev. 62, Page 268 of 295 On-Shift Staffing Analysis TABLE 4-Radiation Protection
& Chemistry Analysis#
7 Performance Time Period After Emeraenc, Declaration (minutes)
Line Position Performing Function/Task 0-5-10-15-20-25-30-35'-5 10 15 20 25 30 35 40 1 .. In-Plant Survey On-Shift Position:
RP 2. Out of Plant Survey On-Shift Position:
RP #2 3. Personnel Monitoring On-Shift Position:
: 4. Job Coverage On-Shift Position:
: 5. Offsite Radiological Assessment On-Shift Position:
RP #1 6. Other Site-Specific RP -Describe:
On-Shift Position:
: 7. Chemistry function/task
#1 -Describe:
Support Field Monitoring Team On-Shift Position:
Chem #1 8. Chemistry function/task
#2 -Describe:
On-Shift Position:
Chem #1 Notes: RP Technicians report to OSC for this event and take direction from Shift Manager. Chemistry Technician reports to OSC for this event and takes direction from Shift Manager. Chemist Post Tri Sam lin after ERO au mentation re uired within 12 hours of shutdown Page 66 of 93 40-45-50-55-60-65-70-75-80-85-45 50 55 60 65 70 75 80 85 90 Emergency Plan, Rev. 62, Page 269 of 295 On-Shift Staffing Analysis TABLE 5 -Emergency Plan Implementation Analysis#
7 Line Function/Task On-Shift Position Task Analysis Controllina Method 1. Declare the Emergency Shift Manager EP/Ops Training and EP Classification Level (ECL) Drill Program 2. Approve Offsite Protective Action N/A N/A Recommendations
: 3. Approve content of State/local Shift Manager EP/Ops Training and EP notifications Drill Program 4. Approve extension to allowable N/A N/A dose limits 5. Notification and direction to SR0#1 EP/Ops Training and EP on-shift staff (e.g., to assemble, Drill Program evacuate, etc.) 6. ERO notification STA EP/Ops Training and EP Drill Program 7. Abbreviated NRC notification for N/A N/A DBT event 8. Complete State/local notification Shift Manager EP/Ops Training and EP form Drill Program 9. Perform State/local notifications STA EP Training and EP Drill Program 10. Complete NRC event notification STA EP/Ops Training and EP form Drill Program 11. Activate EROS Will occur in the EOF EP Training and EP Drill after augmentation*
* Program 12. Offsite radiological assessment N/A N/A 13. Perform NRC notifications STA EP/Ops Training and EP Drill Program 14. Perform other site-specific event N/A N/A notifications (e.g., INPO, ANI, etc.) 15. Personnel accountability N/A N/A Notes: Alert EAL OA4/0A6 EP-PS-100 Emergency Director, Control Room
* At the time of the Phase II On-shift Staffing Analysis, EROS activation would occur in the EOF. As of DEC 2012, EROS can be started from any nuclear Susquehanna Computer (such as those in the OSC where the SM and STA could evacuate to) IAW EP-PS-135, NRC Communicator.
EROS activation time is -1 minute Page 67 of 93 Emergency Plan, Rev. 62, Page 270 of 295 On-Shift Staffing Analysis Event Timelines and Assumptions Event #13 Station Blackout Initial Conditions:
Time: Monday @ 0330 Unit 1 100% Power, NOP & NOT Unit 2 100% Power, NOP & NOT Emergency Diesel Generator E was declared inoperable at 0300 and isolated for maintenance due to failure of the Woodward governor.
Sequence of Events: 0330 Total LOOP Startup Transformers T1 O and T20 are unavailable Emergency Diesel Generator A fails to start Emergency Diesel Generator B fails to start Emergency Diesel Generator C fails to start Emergency Diesel Generator D fails to start Page 68 of 93 On-Shift Staffing Analysis Appendix B Analysis #8: DBA/ISG Event #13 -Station Blackout TABLE 1 -On-shift Positions Augmentation Line On-shift Position Emergency Plan Reference Elapsed Time (min) 1. Shift Manager SSES E Plan Table 6.1 N/A 2. Unit Supervisor (SRO #1) 1 SSES E Plan Table 6.1 N/A 3. Unit Suoervisor (SRO #2) 1 SSES E Plan Table 6.1 N/A 4. Shift Technical Advisor (STA) SSES E Plan Table 6.1 N/A 5. Field Unit Suoervisor (FBU 2 SSES E Plan Table 6.1 N/A 6. Plant Control Operator (PCO #1) SSES E Plan Table 6.1 N/A 7. Plant Control Operator (PCO #2) 3 SSES E Plan Table 6.1 N/A 8. Plant Control Ooerator (PCO #3) SSES E Plan Table 6.1 N/A 9. Plant Control Operator (PCO #4) 3 SSES E Plan Table 6.1 N/A 10. Nuclear Plant Operator (NPO #1) SSES E Plan Table 6.1 N/A 11. Nuclear Plant Operator (NPO #2) SSES E Plan Table 6.1 N/A Page 69 of 93 Emergency Plan, Rev. 62, Page 271 of 295 ECL: Site Area Emergency Role in Unanalyzed TMS Table#/Line#
Task? Required?
T2/L 1 NO NO T5/L 1 T5/L3 T5/L8 T2/L2 NO NO T2/L3 NO NO T2/L4 NO YES T5/L5 T5/L6 T5/L9 T5/L 10 T5/L 11 T5/L 13 T2/L5 NO NO T2/L6 NO NO T2/L7 NO NO T2/L8 NO NO T2/L9 NO NO T2/L 10 NO NO T2/L 11 NO NO Emergency Plan, Rev. 62, Page 272 of 295 On-Shift Staffing Analysis Augmentation Role in Unanalyzed TMS Line On-shift Position Emergency Plan Reference Elapsed Time (min) Table#/Line#
Task? Required?
: 12. Nuclear Plant Operator (NPO #3) SSES E Plan Table 6.1 N/A T2/L 12 NO NO 13. Nuclear Plant Operator (NPO #4) SSES E Plan Table 6.1 N/A T2/L 13 NO NO 14. Security Officer #1 SSES E Plan Table 6.1 N/A T2/L 14 NO NO 15. Security Officer #2 SSES E Plan Table 6.1 N/A T5/L 15 NO NO Notes: 1 Unaffected Unit Supervisor functions as the NRC Communicator 2 Functions as Fire Brigade Leader during fire related response events 3 Unaffected Unit Plant Control Operator functions as E Plan Communicator Page 70 of 93 Emergency Plan, Rev. 62, Page 273 of 295 On-Shift Staffing Analysis Analysis # _8_ TABLE 2 -Plant Operations
& Safe Shutdown Two Units -One Control Room (Shared) Applicable to unit 1 & 2 Minimum Operations Crew Necessary to Implement ONs and EOPs, or SAMGs if applicable Line Generic Title/Role On-Shift Position 1. Shift Mana er Shift Mana er 2. Shift Su ervisor Unit Su ervisor SR0#1 3. Shift Su ervisor Unit Su ervisor SR0#2 4. Shift Technical Advisor Shift Technical Advisor STA 5. Shift Su ervisor 6. Reactor O erator #1 Plant Control 0 PC0#1 7. Reactor O erator #2 Plant Control 0 erator PC0#2 8. Reactor 0 erator #3 Plant Control 0 erator PC0#3 9. Reactor 0 erator#4 Plant Control 0 erator PC0#4 10. Auxilia erator#1 Nuclear Plant O erator NP0#1 11. Auxilia erator #2 Nuclear Plant O erator NP0#2 12. Auxilia erator #3 Nuclear Plant O erator NP0#3 13. Auxilia Operator#4 Nuclear Plant Operator NP0#4 I Notes: See Table 2A for ON/EOP actions Other (non-Operations)
Personnel Necessary to Implement ONs and EOPs, or SAMGs if applicable Line Generic Title/Role On-Shift Position 14. Security Officer Security Officer #1 Task Performance Validation Operator Trainin 0 erator Trainin 0 erator Trainin Operator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin Operator Train in 0 erator Trainin 0 erator Trainin Operator Train in Task Performance Validation Security Training Notes: Support 'Blue Max' connection activities
-officer posted near location Page 71 of 93 Page 72 of 93 Station Blackout Procedure Step/Actions Proc/Ste E0-100-030 Task Attempts to start DG Cycle ESW pump DC power knife switches Press local emergency stop for each DG Monitor plant parameters on available instrumentation Establish ES riorities Operate HPIC and RCIC IAW Attach A Use SRVs to maintain ressure Operate HPIC to maintain ress Contact TCC for s stem status Align busses to Attach I Vent Hydrogen from main enerator Connecting Blue Max er ES-002-001 Secure non-class 250 volt DC loads Bypass HPIC High Dry Well Press Initiation Lineup fires system toRHRSW Bypass RCIC Low Steam Supply Press Isolation Bypass RCIC High Turbine Exhaust Assigned Resource NP04 NPO 1 NP02 NP04 PCO 1-4 SR01 SR02 PC01 PC03 PCO 1 PC03 PCO 1 PC03 STA PC02 PC04 NPO 1 NP02 NP03 NPO 1 NP02 NP04 FBL NP02 NP04 FBL NP04 FBL On-Shift Staffing Analysis Analysis #8, Table 2A -ON/EOP Actions Performance Time (mins) After Procedure Implementation 5-10 10-15 15-20 20-25 25-30 30-35 Emergency Plan, Rev. 62, Page 274 of 295 35-40 40-45 45-50 50-55 55-60 Emergency Plan, Rev. 62, Page 275 of 295 On-Shift Staffing Analysis Station Blackout Procedure Step/Actions Performance Time (mins) After Procedure Implementation Assigned 0-5 5-10 10-15 15-20 20-25 25-30 30-35 35-40 40-45 45-50 50-55 55-60 Proc/Steo Task Resource Press Trip ,:: ".\,,; Bypass HPIC CST NP04 I::* C . .. Low Water Level .. FBL . :* ., *, ' Swan 1 .... *' Bypass HPIC High NP04 .'';' . ;{''. ,, ,: Turbine Exhaust ; FBL Pressure Trio .. Crosstie RWST with ,,",,c '"" NPO 1 x. . CSTs ,, ""' : ' Page 73 of 93 TABLE 3-Firefighting Emergency Plan, Rev. 62, Page 276 of 295 On-Shift Staffing Analysis Analysis#
8 Line Performed By Task Analysis Controlling Method 1. N/A N/A 2. N/A N/A 3. N/A N/A 4. N/A N/A 5. N/A N/A Notes: No fire Brigade response required for this event. Page 74 of 93 Emergency Plan, Rev. 62, Page 277 of 295 On-Shift Staffing Analysis TABLE 4-Radiation Protection
& Chemistry Analysis#
8 Performance Time Period After Emergency Declaration (minutes)
Line Position Performing Function/Task 0-5-10-15-20-25-30-35-40-45-50-55-60-65-70-75-80-85-5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 1. In-Plant Survey On-Shift Position:
RP 2. Out of Plant Survey On-Shift Position:
RP 3. Personnel Monitoring On-Shift Position:
: 4. Job Coverage On-Shift Position:
: 5. Offsite Radiological Assessment On-Shift Position:
RP #1 6. Other Site-Specific RP -Describe:
On-Shift Position:
: 7. Chemistry function/task
#1 -Describe:
Support Field Monitoring Team On-Shift Position:
Chem #1 8. Chemistry function/task
#2 -Describe:
On-Shift Position:
Chem #1 Notes: No RP or Chemistry response required prior to ERO augmentation.
Page 75 of 93 Emergency Plan, Rev. 62, Page 278 of 295 On-Shift Staffing Analysis TABLE 5-Emergency Plan Implementation Analysis#
8 Line Function/Task On-Shift Position Task Analysis Controlling Method 1. Declare the Emergency Shift Manager EP/Ops Training and Classification Level (ECL) EP Drill Proaram 2. Approve Offsite Protective N/A N/A Action Recommendations
: 3. Approve content of State/local Shift Manager EP/Ops Training and notifications EP Drill Program 4. Approve extension to allowable N/A N/A dose limits 5. Notification and direction to STA EP/Ops Training and on-shift staff (e.g., to assemble, EP Drill Program evacuate, etc.) 6. ERO notification STA EP/Ops Training and EP Drill Program 7. Abbreviated NRC notification N/A N/A for DBT event 8. Complete State/local Shift Manager EP/Ops Training and notification form EP Drill Program 9. Perform State/local notifications STA EP Training and EP Drill Program 10. Complete NRC event STA EP/Ops Training and notification form EP Drill Program 11. Activate EROS STA EP/Ops Training and EP Drill Program 12. Offsite radiological assessment N/A N/A 13. Perform NRC notifications STA EP/Ops Training and EP Drill Program 14. Perform other site-specific N/A N/A event notifications (e.g., INPO, ANI, etc.) 15. Personnel accountability Security Officer #2 EP/Security Training and EP Drill Program Notes: Site Area Emergency EAL MS1. EP-PS-100 Emergency Director, Control Room Page 76 of 93 Emergency Plan, Rev. 62, Page 279 of 295 On-Shift Staffing Analysis Event Timelines and Assumptions Event#15 SAMG Response Initial Conditions:
Time: Tuesday @ 0500 Unit 2 in accident condition requiring entry into SAMG (refer to Event #7) Sequence of Events: 0525 SAMG entry conditions met; SAMG entered Page 77 of 93 On-Shift Staffing Analysis Appendix B Emergency Plan, Rev. 62, Page 280 of 295 Analysis #9: DBA/ISG Event# 15 -SAMG TABLE 1 -On-shift Positions ECL: General Emergency Conditions Exist Augmentation Role in Unanalyzed TMS Line On-shift Position Emergency Plan Reference Elapsed Time (min) Table#/Line#
Task? Required?
: 1. Shift ManaQer SSES E Plan Table 6.1 N/A T2/L 1 NO NO 2. Unit Supervisor (SRO #2) 1 SSES E Plan Table 6.1 N/A T2/L2 NO NO 3. Shift Technical Advisor (STA) SSES E Plan Table 6.1 N/A T2/L3 NO NO 4. Field Unit Supervisor (FBL) 2 SSES E Plan Table 6.1 N/A T2/L4 NO NO 5. Plant Control Operator (PCO #4) 3 SSES E Plan Table 6.1 N/A T2/L5 NO NO 6. Nuclear Plant Operator (NPO #2) SSES E Plan Table 6.1 N/A T2/L6 NO NO 7. Nuclear Plant Operator (NPO #3) SSES E Plan Table 6.1 N/A T2/L7 NO NO 8. RP Technician (RP #1) SSES E Plan Table 6.1 60 T4/L3 NO NO 9. RP Technician (RP #2) SSES E Plan Table 6.1 60 T4/L6 NO NO 10. Maintenance Site Support Services SSES E Plan Table 6.1 N/A T2/L8 NO NO Handvman #1 (FBM #1) 11. Maintenance Site Support Services SSES E Plan Table 6.1 N/A T2/L9 NO NO Handyman #2 (FBM #2) 12. Maintenance Site Support Services SSES E Plan Table 6.1 N/A T2/L 10 NO NO Handyman #3 (FBM #3) 13. Maintenance Site Support Services SSES E Plan Table 6.1 N/A T2/L 11 NO NO Handyman #4 (FBM #4) Notes: 1 Unaffected Unit Supervisor functions as the NRC Communicator 2 Functions as Fire Brigade Leader during fire related response events 3 Unaffected Unit Plant Control Operator functions as E Plan Communicator Page 78 of 93 Emergency Plan, Rev. 62, Page 281 of 295 On-Shift Staffing Analysis TABLE 2 -Plant Operations
& Safe Shutdown Two Units -One Control Room (Shared) Minimum Operations Crew Necessary to Implement SAMGs if applicable Line Generic Title/Role On-Shift Position 1. Shift Mana er Shift Mana er 2. Shift Su ervisor Unit Su ervisor SRO #2 3. Shift Technical Advisor Shift Technical Advisor STA) 4. Shift Su ervisor 5. Reactor O erator #4 6. Auxilia Nuclear Plant 0 Analysis # ----"9 __ _ Applicable to unit ----'2;;;;...._
__ Task Performance Validation O erator Trainin O erator Train in O erator Trainin 0 erator Trainin 0 erator Trainin 0 erator Trainin 7. Auxilia Operator#3 Nuclear Plant O erator (NPO #3 O erator Trainin I Notes: See Table 2A for SAMG actions Other (non-Operations)
Personnel Necessary to Implement SAMGs if applicable Line Generic Title/Role On-Shift Position 8. Maintenance Site Support Fire Brigade Member #1 Services Handyman #1 9. Maintenance Site Support Fire Brigade Member #2 Services Handyman #2 10. Maintenance Site Support Fire Brigade Member #3 Services Handyman #3 11. Maintenance Site Support Fire Brigade Member #4 Services Handyman #4 I Notes: See Table 2A for SAMG actions Page 79 of 93 Task Performance Validation Fire Brigade Training Fire Brigade Training Fire Brigade Training Fire Brigade Training SAMG (Unit #2) Procedure Step/Actions Proc/Step Task EP-DS-003 Using low pressure ECCS .to control injections to maintain steam lines flooded EP-DS-002 Maintenance Site Steps: Support Services RC/F-11 provide portable RC/F-23 pump truck RC/F-31 RC/F-40 RC/F-47 RC/F-48 RC/F-55 RC/F-56 Page 80 of 93 On-Shift Staffing Analysis Analysis #9, Table 2A -ON/EOP Actions Performance Time (mins) After Procedure Implementation Assigned 0-5 5-10 10-15 15-20 20-25 25-30 30-35 Resource PC04 Maintenance Site Support Services Handyman 1, 2, 3, 4 Emergency Plan, Rev. 62, Page 282 of 295 35-4 40-45 45-50 50-55 1 55-60 0 ,:".:We X ,'' ;," " ,, ,, ,,,,:;*;: ,t, , , X , ,,
TABLE 3 -Firefighting Emergency Plan, Rev. 62, Page 283 of 295 On-Shift Staffing Analysis Analysis#
9 Line Performed By Task Analysis Controlling Method 1. N/A N/A 2. N/A N/A 3. N/A N/A 4. N/A N/A 5. N/A N/A Notes: No Fire Brigade response required for this event. Page 81 of 93 Emergency Plan, Rev. 62, Page 284 of 295 On-Shift Staffing Analysis TABLE 4 -Radiation Protection
& Chemistry Analysis#9 Performance Time Period After Emergenc, Declaration (minutes)
Line Position Performing Function/Task In-Plant Survey On-Shift Position:
RP Out of Plant Survey On-Shift Position:
RP Out of Plant Survey Perform surveys (Near Site) On-Shift Position:
RP Personnel Monitoring On-Shift Position:
Job Coverage On-Shift Position:
Offsite Radiological Assessment On-Shift Position:
RP #1 Other Site-Specific RP -Describe:
On-Shift Position:
Chemistry function/task
#1 -Describe:
Support Field Monitoring Team On-Shift Position:
Chem #1 Chemistry function/task
#2 -Describe:
On-Shift Position:
Chem #1 Notes: RP continue performing actions from Event #7 EP-PS-108, RP Tech 1 (OSCAR) EP-PS-130, RP II Dose Calculator 0-5-10-15-5 10 15 20 ' ,, 20-25-30-35-40-45-50-55-60-65-70-25 30 35 40 45 50 55 60 65 70 75 . X X X X Note that RP#2 may be asked to provide radiological monitoring
/survey by Shift Manager depending upon actual emergency conditions.
This is acceptable since On-site (out-of-plant)
RP Tech is not required until 60 minutes IAW Emergency Plan Table 6.1. Page 82 of 93 75-80 80-85-85 90 Emergency Plan, Rev. 62, Page 285 of 295 On-Shift Staffing Analysis TABLE 5-Emergency Plan Implementation Line Function/Task On-Shift Position 1. Declare the Emergency Classification Level (ECL) 2. Approve Offsite Protective Action Recommendations
: 3. Approve content of State/local notifications
: 4. Approve extension to allowable dose limits 5. Notification and direction to on-shift staff (e.g., to assemble, evacuate, etc.) 6. ERO notification
: 7. Abbreviated NRC notification for DBT event 8. Complete State/local notification form 9. Perform State/local notifications
: 10. Complete NRC event notification form 11. Activate EROS 12. Offsite radiological assessment
: 13. Perform NRC notifications
* 14. Perform other site-specific event notifications (e.g., INPO, . ANI, etc.) 15. Personnel accountability Notes: Emergency Plan Actions taken during Event #7 EP-PS-100 Emergency Director, Control Room Page 83 of 93 NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA Analysis#
9 Task Analysis Controlling Method NIA NIA NIA NIA. NIA NIA NIA NIA NIA NIA NIA -NIA NIA NIA NIA Page 84 of 93 Emergency Plan, Rev. 62, Page 286 of 295 On-Shift Staffing Analysis Appendix C Phase Ill Time Motion Study Analysis Results Emergency Plan, Rev. 62, Page 287 of 295 On-Shift Staffing Analysis The results of the Phase II On-Shift Staffing Analysis conducted September 10-12, 2012 identified three (3) events with potential conflicts requiring further Phase Ill Time Motion Study analysis.
These events are listed in Table 1 below. Table 1 Susquehanna
-Phase Ill Time Motion Study Events Event/Scenario Functions to be Evaluated Affected Position TMS Method Design Basis Threat NRC Abbreviated Call Shift Technical Simulator Run Evaluate E Plan entry with SM Advisor ERO Notification Complete NRC Form NRC Notification
.. ' . ' Cc '' .* Control Room Fire Report to OSC/OCC for E Plan Shift Technical Simulator Run/ with Evacuation and Implementation Advisor Walkthrough Remote Shutdown ERO Notification Perform State/Local Notifications Completed NRC Form NRC Notification
,_i' *,;., ... ' ;.~-,. ' * '*a'(, r .,. "',-''x' V' * ., *" ' :; ii ' ,, > ., .. ,,.; .. Station Blackout Contact TCC Shift Technical
* Simulator Run ERO Notification Advisor Perform State/Local Notifications Complete NRC Form NRC Notifications
' On November 12, 2012, the selected scenarios for Time Motion Study (TMS) were conducted in the Susquehanna Station Operations Training Center on the simulator and using walkthroughs as appropriate.
In attendance to conduct the TMS Scenarios were: Dave Walsh Operations
-Shift Manaqer Douq LaMarca Operations
-Unit Supervisor
-U1 (SRO #1) Robert Bingman Operations
-Unit Supervisor
-U2 (SRO #2) David Borqer Operations
-Unit Supervisor (ST A) Arnold Avery Operations
-Plant Control Operator -OATC U 1 (RO #1) Gordon Operations
-Plant Control Operator-BOP U1 (RO #2) Shellenberqer Patrick Bone Operations
-Plant Control Operator -BOP U2 (RO #4) Ian Missien EP Rodney Brown EP Consultinq, LLC Rex Krohn EP Consulting, LLC Judi Sanquist EP Consulting, LLC The following tables document the results of the TMS for the identified events. Page 85 of 93 Emergency Plan, Rev. 62, Page 288 of 295 On-Shift Staffing Analysis APPENDIX D Function / Responsibility (Task) Analysis Template Event: Design Bases Threat (Event #1) Position:
Shift Technical Advisor Line#: T2/L4, T5/L6, T5/L 10, T5/L 13 Function Responsibility
{Task) Action Step Duration 1. Notifications 1.1 ERO Notifications 1.1.1 STA activates Alt ERO @0948 IAW < 1 minute EP-PS-135
 
===1.2. Complete===
NRC form 1.2.1 STA uses EP-PS-135, Tab 10 for initial NRC N/A notification as a quide to answer auestions
 
===1.3. Perform===
NRC Notifications 1.3.1 STA initiates NRC 50.72 Notification 1 7 minutes @1001 1.3.2 NRC notification completed
-NRC open line maintained
(@1007 2. ON/EOP Function 1 2.1. NRC Abbreviated Call 2.1.1 STA perform immediate notification to NRC -1 minute OS2 -Rapid Notification 0943 2.2. Evaluate E Plan entry with Shift Manager 2.2.1 Shift Manager entering E Plan -Directs STA 4 minutes to look at Attachment G and EP-TP-001 0941 2.2.2 EAL -OS2 SAE declared 0945 Conflicts for the STA were adequately demonstrated during the Time Motion Study (TMS). The location of the Emergency Notification System (ENS) phone allows the STA to monitor plant data on the Plant Process Computer.
This enables the STA to maintain continuous communication while continuing to monitor plant conditions/status (STA function).
Note that cordless Spectralink phones are available to on-shift personnel, if desired. 1 NRC Form 361 completed and provided to NRC HOO IAW EP-PS-135 and NDAP-QA-0720 within 1 hour of event classification.
2 ON/EOP Functions are related to Emerqencv Plan Implementation
-not a conflict.
Page 86 of 93 Emergency Plan, Rev. 62, Page 289 of 295 On-Shift Staffing Analysis Design Basis Threat (Event #1) -Timeline Time Task 0938 Crew has "shift"/Unit 0940 Control Room Shift Manager receives phone call from security Adversaries attempting to breach PA fence Update provided to Control Room Personnel Unit 1 Control Room Supervisor and Unit 2 Control Room Supervisor entering ON-000-010 0941 Shift Manager entering E Plan -Directs STA to look at Attachment G Inside/Outside isolation zone -attempting to breach inner fence SM and ST A review EALs 0942 Control Room crew start Plant Shut Down Unit 1 & 2 performing SCRAM actions -imminent scram RO notifies Generation
-units going offline OATC calls TCC to report trip 0943 Reactor Trip STA perform immediate notification to NRC Shift Manager begins to complete State/Local Notification Form 0945 PCOs dispatched to RSDP -Unit 1 and Unit 2 Site Area Emergency (SAE) declared (EAL OS2) Adversaries have breached PA fence -in PA STA will have to perform communications
-State/NRC 0946 Unit 2 CRS notified Security that 2 PCOs going to Remote Shutdown Panel (RSDP) 0947 Shift Manager provides completed State/Local form (ENR) to STA for peer check 0948 Peer check completed STA activates Alt ERO (Alternate ERO activation process) IAW EP-PS-135, NRC Communicator Shift Manager reviewing Plant conditions
-oversight 0949 Unit 1 using DIV2 for SD cooling -Unit 2 DIV2 -Unit 2 PCO monitoring EOG Start-up Shift Manager working thru EOP 0951 STA begins review of ENR form with State/Locals 0953 ENR notification completed w/State/Locals Shift Manager updates crew -E-Plan entry -Now Site Emergency Director (SEO) 0955 Completes State/Local Notifications Security informs Shift Manager that adversaries have been neutralized
-immediate threat is clear STA validating ERO activation Duck and cover still in effect 0956 Unit 2 CRS makes PA announcement
-SAE STA notifying Generation Plant Dispatch of plant condition status (security event) Both units offline 0957 Shift Manager getting update on plant status from Control Room Supervisor 0958 Unit 1 Control Room Supervisor and Shift Manager discussing plant condition Page 87 of 93 Time 0959 1000 1001 1002 1003 1005 1006 1007 1009 Task Discussion ends Emergency Plan, Rev. 62, Page 290 of 295 On-Shift Staffing Analysis Control Room Supervisor and Shift Techriical Advisor discussinq proqnosis STA and SM reviewinq current conditions prior to contactinq NRC STA initiates NRC 50.72 Notification
-_follow up information CRS updatinq SM -no more mitigating actions are being taken at this time CRS and SM reviewing on-going actions. SM reviewing SPDS/Plant Status Computer Review completed SM and CRS reviewing current status on unit Review completed NRC notification completed
-NRC open line maintained TMS Terminated Page 88 of 93 Emergency Plan, Rev. 62, Page 291 of 295 On-Shift Staffing .Analysis APPENDIX D Function / Responsibility (Task) Analysis Template Event: Control Room Fire w/evacuation (Event #12) Position:
Shift Technical Advisor Line#: T2/L4, T5/L6, T5/L9, T5/L 10, T5/L 13 Function Responsibility (Task) Action Step Duration 1. Notifications 1.1 ERO Notification 1.1.1 STA activities alternate ERO notification 1 minute ~1051 IAW EP-PS-135 1.1.2 STA calls Security to verify ERO activation
(@1052 1.2 Perform State/Local Notification 1.2.1 STA starts ENR notification to PEMA (@1104 3 minutes 1.2.2 Complete PEMA notification
(@1107 1.2.3 STA starts ENR notification to CCEMA 1107 3 minutes 1.2.4 Completes CC EMA notification 1110 1.2.5 STA starts ENR notification to LCEMA 1110 3 minutes 1.2.6 Completes LCEMA notification (cv1113 Total time for State/Local notifications 9 minutes 1.2.7 STA starts ENR notification to PIM (cv1113 4 minutes 1.2.8 Completes PIM notification (cv1117 1.3 Complete NRC Form 1.3.1 STA uses EP-PS-135, Tab 10 as quide N/A 1.4 Perform NRC Notification 1.4.1 STA calls NRC about the Alert classification
<1 minute (cv1123 1.4.2 NRC requests an open line for communications N/A 2. ON/EOP Implementation
 
===2.1 Report===
to OCC/OSC for E-Plan 2.1.1 Shift Manager (SM) and STA travel to 5 minutes Implementation OCC/OSC (@1052 2.1.2 SM and STA arrive at OCC/OSC (@1057 TMS analysis started in the Simulator Control Room until evacuation by Control Room personnel.
Upon evacuation, the Control Room Supervisors and Reactor Operators report to the Remote Shutdown Panels to complete assigned actions. During the TMS these individuals reported to the Remote Shutdown Panels located in the simulator.
Upon evacuation, the Shift Manager and STA report to the OCC/OSC to complete assigned actions. A transit time of 5 minutes from the Control Room to the OCC/OSC has been determined by Susquehanna personnel.
This time was used during this TMS analysis.
To complete the walkthrough activities, the Shift Manager and STA remained in the Simulator Control Room and used only the equipment available in the OCC/OSC to complete notifications (the OCC/OSC has regular phones (i.e., no ringdown phone) and EPIPs available for use as well as computers with access to the plant data system). During this event, the STA primary function is notifications with the Shift Manager maintaining oversight and monitoring plant conditions/status.
ERO notification was initiated prior to Control Room evacuation.
State/Local Notifications were completed within 9 minutes with the NRG notification being initiated 10 minutes afterwards.
Use of the 'Spectra Link' phones in the OCC/OSC enables the STA to maintain continuous communication with the NRG while still monitoring plant conditions/status.
All conflicts were resolved during the TMS. Page 89 of 93 Emergency Plan, Rev. 62, Page 292 of 295 On-Shift Staffing Analysis Control Room Fire with Evacuation and Remote Shutdown (Event #12)
-Timeline Time Task 1048 Control Room (CR) crew has the shift 1050 Simplex Fire alarm in CR on control board 1 C601 -flames & smoke observed CR crew attempts to extinguish fire 1051 PA announcement for CR evacuation, by Unit 1 Control Room Supervisor (CRS) ST A calls Security to inform that the CR is evacuating the CR and moving to the remote Shutdown Panels -CR crew scrams both units 1051 STA activates alternate ERO IAW EP-PS-135 1052 PA announcement for Unit 1 & Unit 2 Rx scrams STA calls Securitv to verify ERO activation 1052 Shift Manager (SM) and STA travel to OCC/OSC to perform their duties 1057 SM and STA arrive at OCC/OSC, discuss E-Plan classification, and start working through their procedures (SAE if fire control not establish in 15 minutes) 1059 Both Unit 1 & Unit 2 CR crews arrive at remote Shutdown panels 1101 SM declares an Alert (EAL OA4) 1102 SM receives call from remote Shutdown panels that they have control of the plant as of 1100 1102 SM hands STA Emernency Notification Report (ENR) for State/Local notifications
* 1104 STA starts ENR notification to PEMA 1107 Complete PEMA notification 1107 STA starts ENR notification to CCEMA 1107 SM receives update from both remote Shutdown panels on plant conditions 1108 Both CRS announce to crews about Alert classification 1110 Completes CCEMA notification 1110 STA starts ENR notification to LCEMA 1113 Completes LCEMA notification 1113 STA starts ENR notification to Public Information Manager (PIM) 1117 Completes PIM notification 1117 STA calls TCC about Rx trips and CR Fire 1117 STA calls Generation Power Dispatch about Rx trips and CR Fire 1117 CRS update SM on plant conditions from Shutdown panels 1118 ST A orooressino throuoh his procedure 1119 STA performs PA announcement for Alert classification 1120 STA reviews SPDS before NRC notification 1121 SM and ST A discuss plant conditions 1123 STA calls NRC about the Alert classification and plant conditions NRC request that STA maintain an open line of communications -with headset, speaker on mute 1129 SM receives update from both Shutdown panels 1133 TMS terminated Page 90 of 93 On-Shift Staffing Analysis APPENDIX D Emergency Plan, Rev. 62, Page 293 of 295 Function/
Responsibility (Task) Analysis Template Event: Station Blackout (Event #13} Position:
Shift Technical Advisor Line #: T2/L4, T5/L6, T5/L9, T5/L 10, T5/L 13 Function Responsibility (Task) Action Step Duration 1. Notifications 1.1 ERO Notification 1.1.1 SRO #2 activates ERO (Emergency Response 1 minute Oroanization)@
0825 IAW EP-PS-135 1.1.2 ERO Pager activation verified by SRO #2  0826 1.2. Perform State/Local Notification 1.2.1 STA initiates State/local Notifications 0823 4 minutes 1.2.2 STA completes State/Local Notifications (8) 0827 1.3. Complete NRG Form 1.3.1 No NRG Form completed based on Shift Manager N/A decision to notify NRG and follow-up later with completed ENS form (using EP-PS-135, Tab 10) 1.4. Perform NRG Notification 1.4.1 SRO #2 notifies NRG -reviews information 11 minutes contained in EP-PS-135 0840 1.4.2 SRO #2 directed by NRG to maintain continuous communication (ci) 0851 2. ON/EOP Implementation
 
===2.1. Contact===
TTC 2.1.1 U2 Control Room Supervisor (SRO #2) contacts 1 minute TCC (Transmission Control Center) 0814 Conflicts for the Shift Technical Advisor were resolved by the Shift Manager assigning ERO and NRG notifications to the U2 Control Room Supervisor (SRO #2) once unit was stabilized.
STA performed State/Local Notifications within 4 minutes c;1nd was available to provide support as directed by the Shift Manager as well as monitoring plant status/conditions.
Page 91 of 93 Emergency Plan, R'ev. 62, Page 294 of 295 On-Shift Staffing Analysis Station Blackout (Event #13) -Timeline Time Task 0809 Control Room Crew has shift 0811 Station BlackouURx Trip (both units) Rx Trip PA Announcement (RO #2) Entering ON/EOP based on low reactor water level and Station Blackout 0812 Shift Manager (SM) directs Shift Technical Advisor (STA) to review E Plan (enter EP-TP-001, ERO Independent Verification Procedure) 0812 U 1 Control Room Supervisor (SRO #1) implementing actions from Reactor Water Low flowchart
-providinQ direction to Plant Control Operators (PCO) as needed 0813 Unit 1 PCO (OATC -RO #1) directed to start Emerqency Diesel Generators (EDGs) RO #1 directs Nuclear Plant Operator (NPO) to manually start all EDGs SRO #1 updates SM on ES Flowchart status 0814 U2 Control Room Supervisor (SRO #2) contacts TCC (Transmission Control Center) concerning loss of offsite power and anticipated return to service -call completed in less than 1 minute 0815 ST A reviewinQ plant conditions SRO #2 updates SRO #1 on securinQ EOG emerqency start loqic -conserve battery 0816 SM determines Emergency Classification, receives concurrence from STA SM starts to complete State/Local Notification Form 0819 Site Area Emergency declared (EAL MS1) 0820 SM completes and approves State/Local Notification Form 0821 STA directed to complete Offsite Aqency notifications (State/Local/NRC) 0823 STA initiates State/local Notifications 0825 SRO #2 activates ERO (Emergency Response Organization) by pressing applicable button.on phone IAW EP-PS-135, NRC Communicator
(<1 minute to complete) 0826 ERO Pager activation verified by SRO #2 0827 STA completes State/Local Notifications 0830 SM and STA reviewinQ current plant status and conditions (oversight) 0833 Sf\/1, STA, SRO #2 discuss EROS capability/activation (in this scenario EROS would not be available to transmit data due to loss of Process Computer -discussed with crew during debrief) 0836 SM determines need to conduct Site Accountability-directs STA to initiate 0837 SRO #2 announces event classification (PA Announcement) 0838 Site Accountability initiated by STA (alarm) and SRO #2 (PA Announcement) 0840 SRO #1 provides crew update -exiting EOP within % minute 0840 SRO #2 notifies NRC -reviews information contained in EP-PS-135, NRC Communicator (no NRC Form completed based on Shift Manager decision to notify NRC and follow-up later with completed form) 0842 Crew Brief initiated 0844 Crew Brief completed 0848 SM and STA review current plant status/conditions 0850 SM updates SRO #2 on current priorities based on NRC request 0851 SRO #2 directed by NRC to maintain continuous communication 0854 TMS Terminated Page 92 of 93 Emergency Plan, Rev. 62, Page 295 of 295 On-Shift Staffing Analysis Phase Ill Time Motion Study Results 1. Design Basis Threat -The identified conflicts for the Shift Technical Advisor were adequately demonstrated during the TMS. 2. Control Room Fire with Evacuation and Remote Shutdown -The identified conflicts for the Shift Technical Advisor were adequately demonstrated during the TMS. 3. Station Blackout -The identified conflicts for the Shift Technical Advisor were adequately demonstrated during the TMS Page 93 of 93 Enclosure 4 to PLA-7758 Associated 10 CFR 50.54(q) Screens and Evaluations Emergency Plan, Rev. 61, Page 1 of 298 SUSQUEHANNA NUCLEAR, LLC SUSQUEHANNA STEAM ELECTRIC STATION EMERGENCY PLAN REVISION M62 DATE: SeptembeF 29, 29'17TBD PORC MEETING: 17 89 26TBD Emergency Plan, Rev. 61, Page 2 of 298 SUSQUEHANNA NUCLEAR, LLC SUSQUEHANNA STEAM ELECTRIC STATION THIS DOCUMENT HAS BEEN UPDATED TO INCLUDE REVISIONS THROUGH 61 DATED: Scpteml1er:
29, 2917TBD ,* i NOTE: Emergency Plan, Rev. 6462, Page 3 of 298 AFFECTED PAGES PPL Susquehanna, LLC was reorganized to Susquehanna Nuclear, LLC. Susquehanna is now a part of parent company Talen instead of PPL. Agreements signed in the past as PPL Susquehanna, LLC will be honored and carried forward by Susquehanna Nuclear, LLC. j. _1. __ Revision e-1---62 of the Emergency Plan takes credit for the ~2018 annual review. Referense the ' fosused self assessment in DI 2Q1 e QQ9e2 for planning standards 1 threugh a and the numereHs ether aotiens listed 13elew. Reference AR 2Q17 QQQ!le an El S2Q17 Q7 Q:3 Q1. 2. Updated "Manager-Emergency Preparedness" with "Manager-Security/Emeregency Preparedness"----*
---{ Formatted:
Indent: Left: O", Hangi~g: 0.38" throughout the document per AR-2018-04646 (S2018-03-28-01)
* 3. Replaced Figures 4.1 and 4.2 per AR-2018-13801. (S2018-10-25-01)
: 4. Replaced "outlines" with "outlined" in second paragraph of section 5.1.4. (S2018-10-25-01)
: 5. Added "(Alert or higher emergency declaration)" after "classification" in Section 6.0. phase II section. /S2018-10-25-01}
: 6. Removed section 6.2.7e from the Security Coordinator responsibility to section 6.2.1.p per AR-2017-09053 and AR-2017-20479. (S2018-10-25-01)
: 7. Combined sections 6.2.5.a with 6.2.5.i in current step 6.2.5.a and renumbered the remaining steps. +-:---{ Formatted:
Indent: Left: O", Hanging: 0.38" (S2018-10-25-01) 1 8. Added steps 6.3.1.1.m and 6.3.1.4.h per AR-2018-13835 (S2018-10-02-01, changes 1.a, 7c and I& 9. Added EOF Techncal Advisor position to Figure 6.4 per AR-2018-13095. (S2018-10-25-01)
: 10. Corrected typo in section 6.3.1.5 (S2018-10-25-01)
: 11. Reordered bullets in bulleted listin section 7.1. (S2018-10-25-01) 12.* Deleted reference to supplemental meteorological tower from section 7.1.1.1 per AR-2017-17969
+-,-~ Formatted:
Left, Indent: Left: O", Hanging: 0.38", Space (S2018-10-29-01/E2018-10-29-03)
' Before: 6 pt, After: 2 pt, Numbered+
Level: 1 + Numbering Style: 1, 2, 3, ... + Start at: 1 + Alignment:
Left + Aligned at: 13. Replaced "wind variability''
with "wind direction variability''
in the first paragraph of section 7.1.1.1. >o_.2_s_"_+_I_nd_e_nt_a_t:_o_._s" __________ (S2018-10-25-01\
______________________________________________
-:-c-~;::F=o=r=m=att=e=d=:=N=ot=H=ig=h=lig=h=t=========~
: 14. Replaced and with when in the seventh paragraph in Section 7.1.1.3. (S2018-10-25-01\
______ ....,; --1 Formatted:
Not Highlight J: 15. Deleted 'To the extent reasonable.
persons with high lifetime cumulative radiation exposure should _; _ ->-F_o_r_m_att_e_d_:_F_on_t:_1_0..;.pt-----------=<
not take part in these actions." from Table 7.2 per AR-2018-13465. (S2018-10-24-01/E2018-10 _: ___ Formatted:
Not Highlight Q.1).--------------------------------------------------------!', ~F-o_r_m-att_e_d_:_F-on-t:_l_O_pt----~~--~~-=( 16. Replaced "-" with empty spaces in Health Effects Associated with Whole Body Absorbed Doses Received Within a Few Hours Table in Table 7.2. (S2018-10-25-01)
: 17. Replaced TSC with CR in the second paragraph of section 8.1.2. (S2018-10-25-01)
' i Formatted:
Not Highlight
: 18. Updated name and sddress for PEMA Headquarters in section 8.3.2 per AR-2018-06092. (S2018-----:-1 Formatted:
Indent: Left: O", Hanging: 0.38" 10-25-01)
: 19. Updated location of the redundant control ANS station in section 8.5.4 per AR-2018-06919. (E2018-* 04-26-01)
; 20. Refined description of the plant computer capabilities in the 5th bullet in Section 8.9.1. (S2018 _ J _ --{ Formatted:
Superscript J : 25-01) * -------'-----'----------~
: 21. Removed the phrase "For Example: Offsite Emergency Calendars}" from section 9.4.4 per DPA-10-Dl-2018-06672. (S2018-10-25-01)
: 22. Updated MOA for heavy equipment in Appendix A per ACT-02-CR-2018-03742 (E2018-10-29-01)
Emergency Plan, Rev. e-1-62, Page 4 of 298 23. Updated Fire Department MOA in Appendix A per ACT-02-CR-2018-12173. (E2017-08-25-01)
: 24. Deleted "EOF Information Coordinator" from Appendix Cper DPA-06-Dl-2018-06672
/S2017-10 Q.11 25. Deleted "OSC Clerk" from Appendix C per AR-2017-20382 (S2017-11-21-01)
: 26. Changed Appendix D Enclosures per AR-2018-04987 (E2018-04-13-01)
: 27. Updated Corporate Policy letter in Appendix E with current CNO signature. (S2018-10-25-01) 2. Taele of Contents UJJElates.
AJJJJenElii<
F shoulEI ee NEI 99 01 Rev e not Rev 4. An omission that was not maEle fer Revision eO. ,O.JljlenElix C was shown as starting on the incerreet jlage. Reference AR 2Q17 Qe22a, AR 2Q17 Q1911 anEI S2Q17 Q7 Q3 Q1. 3. Definitien 82, Section e.1, Sectien e.2, Seetion e.a, Tasle e.1, 7.1.1, 7.1.1.2, 7.3.1, 7.4.2, 8.1.2, 9.1.1.&sect;, Taele 9.1 , /'.JJ13enElix C, A1313enElil<
D 13age 2 ef 1e, Enclesure e te AJJJJenElix D, Enslesure 8 te A1313enElil<
D, A1313enElix J, anEI , 6 ,1313enElix K. Changes the term "l-1ealth Physiss" te "RaEliation Protectien" anEI "l-1P" te 'RP" le refieet the surrent name ef that work &sect;FOUJ3 at SSES. The funetion anEI Eluties ef the werk &sect;rOUJl remain the same. Reference S2Q17 07 Q3 01. 4. Definitien 9Q, Asrenym 2.71, 7.1.1, Fi&sect;ure 8.2, Enslesure
!i te A1313enElix D. Removes reference te the Remele Moniterin&sect; System ! RaElielo&sect;ical Envirenmental Menitorin&sect; System sinse the system 'o\411 ne len&sect;er ee useEI at :OSES. Enslosure a le A1313enElix D was further moElifieEI le Elesi&sect;nate that the eff site filceEI air sam131ing statiens anEI Elireet raEliatien menitor statiens (Desimeters) are asseeiateEI with REMP. Referense DPA 03 DI 2Q17 037:l4, S2017 Q7 Q3 Q1, E2017 07 03 Q1. a. ~lew Aerenym aEIEleEI after 2.137 fer ORO Offsite Res13ense Organizatien sinse that term is states en EAL charts S anEI C. Reference S2Q17 Q7 Q:l Q1. l ! " ''' .. -. +-'.-i Formatted:
Indent: Left: O", Hanging: 0.38" e. /\srenym 2.81, 13age :le Tatile R 1 moniter QCe:lO anEI OCe77 removes, B.1.3.1, Fi&sect;ure 8.2 anEI Enslesure 4 te A1313enElil<
D. RemeveEI reference to ioystem Partisulate, loEline, anEI Neale Gas ; Moniter (SPl~IG) since SPINGs are re13laceEI ey Vent Effluent RaEliation Moniterin&sect; System (VERMS).;
Referenee
/1.R 1748182, DPA Q1 DI 201e 23:le:l, S2017 07 03 Q1 anEI E2Q13 Q9 Q3 Q1 Rev. 1. ' 7. /1.EIEleEI a ~late after ste13 !i.2.11 anEI 13rier le the E/\L taeles that states 'The fellowin&sect; EmeF&sect;ency
/1.stien Level (EAL) Taeles are exeeFJ3ts from the EAL Basis centrollin&sect; 13reeedure anEI sentain Jlage numeer references after each EAL fer the cerresjlenElin&sect; easis seetien. These 13a&sect;e numl3er references are not a13131isable within the EmeF&sect;ensy Plan". Reference S2017 Q7 Q:l Q1. 8. EAL Taeles. AEIEleEI ~late e to Ta13le R anEI easis to slarify that RA3.2 is a13JJlisable if the event that is : causin&sect; elevates raEliation levels oesurreEI in Moses 1 or 2 en 13a&sect;e :le. Referense DI 2017 03038. Cerreeted a ty13o&sect;ra13hisal error en Primary Centainment Barrier Less solumn suesate&sect;ery B. Chan&sect;eEI "EO QOQ 104 Taele F 9" te EO OOQ 104 Table 9" en Jla&sect;e 37. Reference AR 2Q17 11093. Removes '(RCS > 200 &deg;F) from the lower right hanEI cemer ef Taele F unEler l-1ot ConElitiens.
Reference DP/I. 14 DI 201e 233e3. RemeveEI '(RCS > 20Q &deg;F) from the lewer ri&sect;h! hanEI eerner ef Taele 1-1 unEler 1-1et CenElitions en jla&sect;e 38. Referense DP/I. 14 DI 201e 233e3. RemeveEI '(RCS < 2QO &deg;F) from the lewer right hanEI semer ef Ta13le C unEler Cele ConEliliens on 13a&sect;e 41. Reference DP-A 14 DI 2Q1e 233e3. Reference S2017 07 12 Q1 fer all the E/1.Llable shanges. 9. Sestien e.1 anEI Table e.1. Revises to 13reviEle slarity anEI alignment of the On Shift staffin&sect; Elessri13liens sontaineEI in these 13laces anEI the staffing stuEly in A13JJenElix K Altl=lou&sect;h tesl=lnisally serrest, tl=le existin&sect; information
*.vas net easily interweteEI.
Referense AR 2Q17 09!ie1, ACT Q1 CR 2017 1111lll anEI S2017 Q7 03 01. 1 o. Section e.2.2, e.2.11, Table e.1, Fi&sect;ure e.2 anEI Fi&sect;ure ll.2. Removes the 13esitien of SAM CoorElinater.
AEIEleEI ste13 e.2.1.f te tl=le 013erations CoorElinator 13ositian to malce recommenElatiens te tl=le Shift Mana&sect;erwhen SAM 13reseElures are entereEI.
Reference DI 2017 1291313, S2017 Q7 03 01 anEI E2017 07 27 01.
Emergency Plan, Rev. 6462, Page 5 of 298 11. Seotions e.2, e.a, Table e.1, and Figures e.2, e.a and e.4 and Seotion 7.1.1. Revised to provide olarity and alignfflent of the ERO staffing desoriptiens oentained in those plaoes. Referenoes to the applioable Table e.1 (eQ and 9Q Fflinute ooillfflns) along with the applioable figure(s) and position titles were added to the text desoriptions of eaoh position.
The desoriptions of the Non Operations S1ipport Personnel shown on Fig1ire e.a were m<panded and added in the tma desoriptions to olearly delineate the positions listed in Table e.1. /\ltho1igh teohnioally oorreot, the existing inforfflation was not easily interpreted.
Referenoe AR 2Q17 Q9Q2!l and S2Q17 Q7 Qa Q1. 12. Figures e.a. Reffloved the bleak "Engineering Support" bleak sinoe the OSC Engineer position was deleted as part of the ERO streaffllining projeot. Referenoe OP/\ Q1 DI 2Q1 ll 1291 !! and S2Q17 Q1 2{ Q1. 1 a. Seotion ll.2.a. Revised to reITTove the responsibility for the TSC NRG Coff\FflllAioator to initiate sail in preoedures as requested by the ED. Call in's are perforffled by the Centre! Rooff\ ~IRC Coff\ff\Unioator and the TSC /\dfflinistrative CoorElinator.
Referenoe
/\R 2Q17 Q9Q4 4 and S2Q17 Q7 Qa Q1. See ~IRC Coff\Fflllnioator EP PS 1 ae seotion e.2 and TSC Adfflinistrative CeerElinator EPPS 111l seotien e.1.9. 14. Seotion e.2.1 Q, Table ll.1, Fig1ire e.a anEI A~penElix C. Reffloved the position of RaElio Coff\ff\Unioator.
Added step e.2.!l.o to the OSC CoorElinator position to ensure GOFflfflunioations with all in plant teaff\s is FflaintaineEI.
Changeel step a. 1ineler the RP Specialist respensibilities to state detorfflino and Fflaintain 1ip to date status for radiologioal oonditions in tho plant. Added to ll.2.1a /\s designateel, Fflaintain radio GOFflfflUnioalions with in plant teaff\s. Reviseel step 8.1.2 to state that oontrol and dispatoh of these toaff\s is the responsil:Jility of the OSC Coordinator.
Referenoo E2Q17 Q!l 11 Q1. 1 a. Tal:Jle ll.2. Revised tho note that states the /\elfflinistrativo Coordinator ITTaintains the inforITTalion to oontaot appropriate venelors in case of an eff\ergenoy to now state that the inforfflation is maintained in the Emergenoy Telephone lnstrnotions and Oireotory.
Referenoe
/\R 2Q17 Q9Qe4 and S2Q17 Q7 Qa Q1. 1 e. Seotion !l.a.2. Added that the State Emergenoy Center has 24 hour per day ooverage per ~lUREG Qlle4 Rev. 1 Seotion 11./\.1.e.
Referenoe
/\R 2Q17 Q9Qa2 and S2Q17 Q7 Qa Q1. 17. Section !l.e.4. Add "(see Figure !l.4)" since that siren location figure is not referenoed anywhere in the text of the emergenoy plan. Referenoe AR 2Q17 Q9Qe7 and S2Q17 Q7 Qa Q1. 1 !l. Table 9.1. Changed Speoial Offioe of the President:
lnforfflation Servioes Personnel to doint Information Center Personnel.
Revised the note fer the table to olarify the type of training and retraining frequenoies for the applioable work groups. Referenoe
/\R 2Q1e 21!l4!l and S2Q17 Q7 19. Appendix A. Added a note to referenoe a historioal basis as to why the Pennsylvania State Polioe do not need a separate letler of agreeff\ent.
Referenoe AR 2Q17 Q9Qa1 and S2Q17 Q7 Qa Q1. Reff\oved
~lesoopeol<
Afflbulanoe and addeel ~lantisoke EiMS. Referenoe CR 2Q17 14 !l1 Q anel Ei2Q17 gg 2&sect; Q1. 2Q. Appendix C. ReITToved referenoe to the TSC Lead Engineer and the GO Support Engineer.
Referenoe DP/\ Q1 DI 2Q1e 1291!l and S2Q17 Q2 1e Q1 and S2Q1e Ge Qe Q1 respeotively.
: 21. Ei Plan Appendix d page 2 of 1 Q. Revised line item A.1.a to inslude Appendix/\
and Table e.2 whish are assooiated with private seater organizations that are part of the overall response organization.
Reviseel line item /\.1.b to inol1Jele Table e.2 whioh is assoGiateel with conoept of operations fer emergenoy response.
Revised line ileffl 1.d to refflove ll.2, ll.a and e.a.1 sinoe they do not overtly state who is in oharge. Revised line ileffl 1.e to add !l.a.1 and !l.a.2 sinoe they desoribe the 24 hour per day eff\ergenoy response by the Co1inties and the State. Revised line iteffl 4 froffl e.2.e to ll.2.7 sinoe the TSC Seourity Coordinator is the position responsible fer assuring oontimJity of resouroes.
Referenoe
/1.R 2Q17 Q9Qa2 and S2Q17 Q7 Ga Q1. 22. Appenelil<
d line iteffl 0.2 change el Tables M anel Oto S anel Jal respeotively.
An Dfflissien that was not Fflade for Revision eQ is now oorrooted.
Referenoe
/1.R 2Q17 Q4Qll7 and S2Q17 Q7 Qa Q1.
Page 1 of 1 Emergency Plan, Rev. 62, Page 24 of 295 SSES POPULATION CIRCLES pennsyl\iania , MER ENc:iMANi,r;EM.EN
~ceNc:v ~--;i-otal Population
-1 a* Miles =, 52;s12 Total Population 5'Miles'=
1-;i,026-Total Population 2Miles.=-998
-:Population 5 to :i 0-Miles =' 39)86 _ :PoJ)u!atior:i 2 to 5 Mil,;s = 12,028 ,Total EPZ Population=
71;212*_ Population*:outside'10-Mile
* _Biit Inside EPZ = 18,400 " SUSQUEHANNA STEAM ELECTRIC STATION Units 1 and 2 EMERGENCY PLAN MAP OF SSES VICINITY Figure 4.1 Page 1 of 1
* pennsylvania
'"'""'"&deg;'
"'"'"'"'"'
***::-,]: J "'1 '' TleGA POP ULA T I ONS: 10-Mile = 53 , 000 SO-Mil e= 1, 800 , 000 (appro x.) CU B LAND SSES EPZ and Ingestion Zone Emergency Plan, Rev. 62 , Page 25 of 295 Commoowealth ot Penmytvania Pen~s:;,:~:t~:
~~~:::~:a~=:~::
5 ency \ Bureau of StrQtegic and Operational Pl.1nning www.pemo.stJte.pa.us SUSQUEHANNA STEAM ELECTR I C STATION Units 1 and 2 EMERGENCY PLAN MAP OF SSES 50 MILE INGESTION EXPOSURE ZONE Figure 4.1 
*--=:i--==----=
===---Miles 0 1.5 3 6 9 12 Page 1 of 1 Emergency Plan , Rev. 61, Page 26 of 298 SUSQUEHANNA STEAM ELE CTR I C STAT I ON UNITS 1 A ND 2 M AP OF SUSQUEHANNA S E S V I CINITY FIGURE 4.1 SSES 50 Mile Buffer ~Mil es 0 5 10 2 0 30 40 P age 1 of 1 Em er ge n cy P la n , Re v. 61 , P age 27 of 298 S USQUEH ANNA STEAM ELE C TRIC STATION U N I TS 1 AND 2 EME RG E NC Y PLAN MA P O F SUSQUE H AN N A SES 50 MIL E IN GE S T ION E X P OSURE ZONE F igu r e 4.2 5.2 5.1.4 Emergency Plan, Rev. 61, Page 30 of 298 General Emergency Events are in process or have occurred which involve actual or IMMINENT substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility.
Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area. Total activation of the onsite and offsite emergency organizations is requirecl for such events. Actions involving offsite populations are probable.
Conditions that constitute a General Emergency are oot!ifle&-outlined in Tables R, F, S, H and C. The ED or Recovery Manager declares a General Emergency within 15 minutes of having information necessary to make a declaration.
The emergency actions taken by Susquehanna and offsite agencies for a General Emergency are listed in Table 5.2. In general the actions will be similar to the actions taken for a Site Area Emergency with additional resources dedicated to the health and safety of the general public. Additional actions include the initiation of predetermined protective actions for the public. SPECTRUM OF POSTULATED ACCIDENTS The classification and corresponding protective actions relative to significant emergency conditions are based primarily on the resultant or potential radiation doses. Methods are described in this Plan and in EP Procedures for measuring, projecting and evaluating those doses. The discrete accidents addressed in this section are those which are defined in the SSES FSAR as "design basis accidents" resulting in off-site dose consequences and accidents involving the spent fuel storage facility (ISFSI). The following discussion of these postulated accidents and Tables R, F, S, H, E and C identify the instrumentation and other mechanisms for prompt detection and continued assessment, and demonstrates how each accident is encompassed within the emergency classification system of this Plan. When an event also involves elevated off-site radiological consequences or other specific conditions, the event classification will be adjusted to reflect actual conditions.
 
====5.2.1 Control====
Rod Drop Accident This accident is described in FSAR Section 15.4.9 and is postulated to occur with the reactor in hot startup condition, and very conservative calculations indicate failure of fuel rods. The main steam line radiation monitors detect the significant increase in activity and initiate an alarm to alert operations personnel.
Operations personnel would then validate the alarm condition, manually SCRAM the reactor and initiate closure of the main steam isolation valves (MSIV) and isolation of the main condenser.
During the MSIV closing time period, noble gases and radioiodines are transported with the steam to the condenser.
Release of radioactivity to the environment is by way of leakage from the turbine building.
Page 3 of9 Emergency Plan, Rev. 61, Page 51 of 298 Upon activation of Phase II, additional personnel are available, and control of the emergency and dissemination of in-plant teams shifts from the Control Room to the TSC. Phase II -Activation of On-Site ERO -(Reference Table 6.1 and Figures 6.2 and 6.3.) Upon notification by the on-shift organization, the on-call Emergency Director reports to the site/Control Room to assume the role of Emergency Director.
As specified in Figures 6.2 and 6.3, the minimum number of support coordinators and staffs also report to the site. These individuals form the nucleus of the ED's Team and activate the TSC and OSC. The TSC and OSC are fully functional within 60 minutes of event classification (Alert or higher emergency declaration).
As the on-call Emergency Director and his support coordinators arrive, they are briefed and assume responsibility for their particular areas of expertise.
Emergency management activities, including communications, are under the control of the Emergency Director; dose projection and assessment activities are directed by the Radiation Protection Coordinator; technical expertise is directed by the Tech Support Coordinator; the Operations Coordinator oversees Operations activities; and the Damage Control Team Coordinator oversees in-plant damage control actions. The OSC Coordinator supports the operations and damage control team coordinators by managing personnel in the OSC (back up OSC in the event the OSC is not habitable).
The TSC takes over all emergency management and support activities from the on-shift organization, freeing them to devote their efforts towards establishing and maintaining the plant in a safe, stable condition.
The onsite ERO may be further augmented as shown in Figures 6.2 and 6.3 by personnel filling TSC positions and OSC positions not designated as minimum requirements.
Figures 6.2 and 6.3 also designate minimum requirements for the TSC and OSC respectively.
In the event of hazards preventing site access or certain security related events, personnel who normally report to the Technical Support Center and Operations Support Center will report to the , Alternate TSC and OSC at the Emergency Operations Facility.
OSC personnel can be sent to the site to mitigate site damage as soon as the site is secured. The alternate TSC will be activated as : soon as possible to support the site; however, it is recognized that the activation time for the i alternate TSC may exceed 60 minutes. * ' Phase Ill -Activation of Off-site ERO-(Reference Table 6.1 and Figure 6.4.) This organization staffs the Emergency Operations Facility to provide management of the overall emergency response as well as technical support, off-site radiological assessment, and communications.
Staffing of the EOF occurs following an Alert, a Site Area Emergency, or a General Emergency declaration.
The EOF is required to activate following a Site Area Emergency or General Emergency classification and take over management of the emergency from the TSC or Control i Room within 90 minutes of the Site Area Emergency or higher classification.
Activation of the Emergency Operations Facility requires the minimum staff as identified in Figure 6.4. When the initial emergency classification is a Site Area Emergency or higher, the EOF will take over the management of the emergency within 90 minutes of the declaration of a Site Area Emergency.
Due to the site response during a daytime security event that starts at the SAE level, the EOF may not be staffed within 90 minutes. With an event in progress, station personnel may be directed to take cover and therefore be unable to respond to the EOF until cleared by plant security.
At the discretion of the Emergency Director, the EOF can be activated and take over management of the emergency earlier.
* Letter dated February 25, 2002 from Samuel J. Collins, Director, Office of Nuclear Reactor Regulations, to Robert G. Byram, Senior Vice President and Chief Nuclear Officer.
 
==Subject:==
Issuance of Order for Interim Safeguards and Security Compensatory Measures for -Susquehanna Steam Electric Station, Units 1 & 2. Page 2 of 19 Emergency Plan, Rev. 61, Page 54 of 298 c. Assure that appropriate notifications of emergency classification and protective action recommendations to state and local agencies are made within 15 minutes of declaration of an EAL. d. Assure that appropriate notifications and recommendations to the NRC are made immediately after notification to state and local agencies, but not later than one hour after declaration of an emergency classification.
: e. Augment the on-site ERO with duty roster personnel and other available station staff members as dictated by the emergency condition.
: f. Continue reassessment of emergency status and make appropriate recommendations including protective actions to off-site organizations.
: g. Ensure that information released is accurate and released through 1 the proper channels.
: h. Activate Emergency Facilities described in Section 8.0, as required.
: i. Assign a technical liaison to the state EOC when requested.
: j. Communicate with and provide information to the Recovery Manager and the Public Information Manager. k. Authorize issuance of Radioprotective Drugs in accordance with prescribed procedures.
This should include consultation with the Radiation Protection Coordinator and medical consultants.
I. Authorize Emergency dose extensions.
This should include consultation with the Radiation Protection Coordinator.
: m. Authorize taking essential corrective action that may involve the risk of emergency radiation exposure to ERO personnel.
Table 7.2 provides the basic criteria for this decision.
: n. 0. p. Implement RCA and site evacuations as required.
Request Federal assistance to augment ERO capabilities as necessary.
Such requests should be coordinated with PEMA and/or DEP/BRP and are normally done through the Recovery Manager and the EOF staff. Provide personnel and work schedules for relieving emergency personnel.
 
====6.2.2 Operations====
 
Coordinator (Table 6.1 60 Minute Response, Figure 6.2) Responsibilities:
Page 5 of 19 ' , ' i 6.2.3 6.2.4 6.2.5 Page 6 of 19 Emergency Plan, Rev. 61, Page 55 of 298 a. Prepare the TSC for activation if the TSC ED has relieved the Control Room ED of responsibility.
: b. Advise the Shift Manager in directing the Control Room and in-plant operational activities.
: c. Direct activities of the Damage Control Team Coordinator, and TSC Communicator.
: d. Advise the ED on plant operations and conditions.
: e. Establish and set priorities for mitigation with the concurrence of the ED. f. Make recommendations to the Shift Manager for mitigation of the effects of Severe Accidents when Severe Accident Management (SAM) procedures are entered. TSC NRC Communicator (Table 6.1 60 Minute Response, Figure 6.2) Responsibilities:
: a. Maintain communications with the NRC. b. Maintain records during the emergency.
TSC Emergency Plan Communicator (Table 6.1 60 Minute Response, Figurk 6.2) a. b. Make proper notification to off-site organizations.
Function as liaison for emergency-related communications between the ED and on-site and off-site emergency groups. c. Maintain records during the emergency.
\. I I i ' Radiation Protection Coordinator (Table 6.1 60 Minute Response, Figure 6.~) Responsibilities:
: a. Ensures dose projections are performed and results are provided to the to the Dose Assessment Supervisor until relieved by the EOF. b. Provide radiological advice to the ED concerning on-site emergency activities.
: c. Provide protective action recommendations to the ED. d. Maintain communication with and provide information to the EOF Dose Assessment Supervisor.
* e. Maintain communication with and provide radiological information to DEP/BRP until relieved by the EOF. > 'l .,
6.2.6 Page 7 of 19 f. g. h. i. jj. ki. Emergency Plan, Rev. 61, Page 56 of 298 Provide on-site radiation monitoring personnel for effluent release assessment.
Provide radiation monitoring personnel for emergency team efforts. Direct personnel and area contamination control and decontamination activities.
Provide dose projeotions to the Dose Assessment aldpervisor ldntil relieved of that responsibility by the EOF. Perform initial off-site environmental assessment until relieved by the EOF. Ensure radiological data is communicated to the NRC via the Health Physics Network. l.!5.. Advise the Emergency Director and organization on use of Kl and emergency dose extensions.
Technical Support Coordinator (Table 6.1 60 Minute Response, Figure 6.2); Responsibilities:
: a. Analyze mechanical, electrical, and instrument and control problems; determine alternate solutions, design and coordinate the installation of short-term modifications.
: b. Analyze thermo hydraulic and thermodynamic problems and develop solutions.
: c. Assist in the development of procedures necessary for conducting emergency operations and damage control. d. Analyze conditions and develop guidance for the ED and operations personnel.
: e. f. g. Resolve questions concerning Operating License requirements with NRC representatives.
Maintain lead technical responsibility, coordinate technical information with the EOF as appropriate, and request technical support from the EOF or other engineering/technical resources.
Maintain communication with and provide technical information to DEP/BRP Technical, as required, until relieved by the EOF. h. Provide core damage estimates.
: i. Until relieved, provide direction to Chemistry Technician to perform emergency plan actions. I ' ' l' 1* i Emergency Plan, Rev. 61, Page 57 of 298 6.2.7 Security Coordinator (Table 6.1 60 Minute Response, Figure 6.2) Responsibilities:
6.2.8 a. Maintain plant security and institute appropriate contingency measures.
: b. Account for personnel as directed by EP-PS procedures.
: c. Act as liaison with outside groups in providing additional resources such as manpower, equipment, supplies, and transportation.
: d. e. Coordinate provisions for transportation, food, and other logistical support for emergency personnel.
Provide personnel and work sohedules for relieving emergenoy personnel.
OSC Coordinator (Table 6.1 60 Minute Response, Figures 6.2 & 6.3) Responsibilities:
: a. Report to the OSC. b. Organize, brief, dispatch, and direct, as necessary, the onsite damage control teams. c. Coordinate the availability and assignment of personnel supporting activities for the ED and other ERO managers.
: d. Organize and manage emergency response personnel in the OSC. e. Ensure communications with all in-plant teams is maintained.
l I L I l I L*, 1* L .. 6.2.9 Damage Control Team Coordinator (Table 6.1 60 Minute Response, Figure !3.2) ; Page 8 of 19 Responsibilities:
: a. Participate in briefings with the TSC ED and helping to set priorities.
: b. Ensure damage control resources are allocated on the correct priorities by providing priorities to the OSC Coordinator and monitoring INDIA Team assignments.
C. Communicate with Operations Coordinator, the Technical Support Coordinator, and the OSC Coordinator.
j ' ,*:
Page 12 of 19 k. I. m. Emergency Plan, Rev. 61, Page 61 of 298 When requested, send a representative to the State EOC. If conditions result in implementation of the Federal Radiological Emergency Response Plan, assign a representative to the Federal Response Center, to the Federal Radiological Monitoring and Assessment Center, and to the Joint Information Center (most likely the PIM). Authorize issuance of Radioprotective Drugs in accordance with prescribed procedures.
This should include consultation with the Dose Assessment Supervisor and medical consultants.
If necessary, authorize Emergency dose extensions for monitoring field teams members under EOF command and control. This should include consultation with the Dose Assessment Supervisor.
6.3.1.2 Engineering Support Supervisor (Table 6.1 90 Minute Response, Figure 6.4) Responsibilities:
: a. Manage engineering support resources in the EOF. b. Provide technical support to aid in decision making process. c. Keep BRP informed concerning technical status of the plant and any mitigating actions being considered or in progress.
: d. Provide technical information concerning plant status and mitigating actions to the off-site agencies.
l 6.3.1.3 EOF Support Supervisor (Table 6.1 90 Minute Response, Figure 6.4) Responsibilities:
: a. Provide support to the Recovery Manager in review of plant data. b. Oversee formal communications leaving the EOF. c. Oversee proper facility set up. d. Provide administrative support. e. Support the Recovery Manager with off-site agency interface.
6.3.1.4 Dose Assessment Supervisor (Table 6.1 90 Minute Response, Figure 6.4) Responsibilities:
: a. Ensure dose projections are performed.
I.
Page 13 of 19 b. C. d. Emergency Plan, Rev. 61, Page 62 of 298 Evaluate the magnitude and effects of actual or potential radioactive releases from the plant. Recommend appropriate off-site protective measures to the Recovery Manager. Recommend appropriate emergency classifications to the Recovery Manager. e. Communicate with the Radiation Protection Coordinator in,the TSC and with DEP/BRP radiological personnel.
: f. Control field monitoring teams. g. h. Perform off-site environmental assessment.
Advise the Recovery Manger and organization on use of Kl and emergency dose extensions.
if necessary, for the monitoring field team members under EOF command and control. 6.3.1.5 Emergency Plan Communicator (Table 6.1 90 Minute Response, Figure 6.4) Responsibilities:
: a. Assume responsibility from the TSC for off-site notifications (except ENS communications).
: b. Transmit information about the emergency to off-site organizations.
: c. Function as liaison for questions received from other organizations.
: d. Maintain a record of emergency notifications.
6.3.1.6 Radiological Support Staff (Dose Assessment Staffer. Field Team Director. "B" Radiological Monitoring Team) (Table 6.1 90 Minute Response, Figure 6.4) Responsibilities:
: a. Perform dose calculations, as required. (Dose Assessment Staffer) b. Monitor and control field teams. (Field Team Director)
: c. Perform monitoring of areas around the plant as directed.
(''B" Radiological Monitoring Team)
Emergency Plan, Rev. 62, Page 73 of 295 r ;N'&deg;c,~;EE~~N-;
1 1 SUPPORT 1 1 SUPERVISOR*
1 !_ __________
! ENGINEERING SUPPORT EOF ORGANIZATION
~---;OSE ___ i I I 1 ASSESSMENT 1 1 SUPERVISOR' 1 ~----------!
.----------------------, I RECOVERY MANAGER* : I I ~----------
----------~
TECHNICAL ADVISOR .--------------
-----------* I
* EOF SUPPORT a : SUPERVISOR*
: I I ------------
:--EMi;;tN~Y--:
PLAN 1
* DOSE ASSESSMENT
: : STAFFER* : *(RAD Assessment Staff), LIAISON SUPPORT SUPERVISOR
: COMMUNICATOR*:
*-----------*
L*************'
----------------
* I 'FIELD TEAM DIRECTOR*: , (RAD Assessment Staff) , I I
,-----------.
1 "A''RAD I 1 MONITORING
: : TEAM (2)* :
*-----------
1 "B"RAD 1 1 MONITORING
: L-~E~!1_(~):*
__ J ENVIRONMENTAL SAMPLING TEAM ADDITIONAL RAD '--~---I STAFF OFFSITE AGENCY LIAISONS NEP DUTY PLANNER ADMIN. STAFF SECURITY .----------------------------------------------*-----------------
!. '2!::~9Q<!.t!:;~
rnJQi!!1llrr1_
Le~Jr!::'!1~!)~
Ju il~~O!~~llc..e_ I~~I!:; .t 1. f.o! JQ _~i!)~~ !~~o_n,r,~J
* Designates positions required for EOF activation.
PUBLIC INFORMATION MANAGER PUBLIC OFFICIALS CONTACTS ADMIN. STAFF TECHNICAL BRIEFERS NEWS MANAGER Susquehanna Steam Electric Station Units 1 and 2 Emergency Plan ** Not required for activation unless "A" team unavailable.
NOTE: RAD Monitoring Team (2) refers to 1 Team with 2 people. .----------------------------------------------------------------.
EOF ORGANIZATION FIGURE6.4
: Designates minumum requirements in accordance with Table 6.1 for 60 minute response.
: I I Page 3 of 5 Emergency Plan, Rev. 61, Page 75 of 298 *----------* ENGINEERING
: : SUPPORT I I SUPERVISOR*
: L **** ****** ENGINEERING SUPPORT EOF ORGANIZATION
****-------* DOSE : : ASSESSMENT
*
* SUPERVISOR*
: L **** ****** I I : RECOVERY MANAGER* : I I *----------
----------*
--------------.
,----------* I 1 EOF SUPPORT : : SUPERVISOR*
: L **** ****** ------------.
: EMERGENCY 1 : DOSE ASSESSMENT 1 1 STAFFER* : 1 (RAD Assessment Staff)* LIAISON SUPPORT SUPERVISOR PLAN : : COMMUNICATOR**
------------*
*-------------*
***-------------
* I 1FIELD TEAM DIRECTOR*:
1 (RAD Assessment Staff) , L ****** *******' .----------.
1 M;t~:C~~NG
: :.TEAM(2)*
** : :***;:R;;***:
1 MONITORING I L 1:.E:-::1.<:i:
~. ! ENVIRONMENTAL SAMPLING TEAM ADDITIONAL RAD STAFF OFFSITE AGENCY LIAISONS NEPDUTY PLANNER AOMlN. STAFF SECURITY **-------------------------------------------------------------. , Designates minimum ~equirements in accordance w~h Table 6.1 for 90 minute response. ,
* Designates positions required for EOF activation.
PUBLIC INFORMATION MANAGER PUBLIC OFFICIALS CONTACTS ADMIN. STAFF TECHNICAL BRIEFER$ NEWS MANAGER Susquehanna Steam Electric Station Units 1 and 2 Emergency Plan -Not required for activation unless "A" team unavailable.
NQJJ;;: RAD Mon~oring Team (2) refers to 1 Team with 2 people. .----------------------------------------------------------------
EOF ORGANIZATION FIGURE 6.4 : Designates minumum requirements in accordance with Table 6.1 for 60 minute response.
: *---------------------------------------------------------------*
Page 3 of 5 I Emergency Plan, Rev. 61, Page 78 of 298 7.1 ASSESSMENT ACTIONS FOR ALL EMERGENCY CLASSIFICATIONS Provisions are made for assessment through the course of an emergency to ensure effective coordination, direction and upgrading of emergency activities in a timely , . manner. The assessment actions are described in detail in Emergency Plan Position Specific Instructions (EP-PSs).
Continuous assessment of the status of plant systems and radiological conditions is provided by plant instrumentation and is supplemented by routine surveillance functions.
The occurrence of an Unusual Event is recognized by instrument alarms or indications, surveillance results, or other observation of an off-normal condition by an individual at the station. Assessment actions are described below. For a Notification of Unusual Event, one or more of the actions listed below will be initiated; for higher emergency classifications, actions are continued, intensified, and increased in frequency.
Table 7 .1 provides a Summary of Notification
& Response Actions outlined in Section 7 .1. l
* Perform surveillance of in-plant instrumentation.
* Initial and continued observation of off-normal conditions.
* Obtain assistance from off-duty personnel and/or off-site support groups. e Deploy on-site damage control teams.
* Perform reactor coolant sampling and analysis.
* Deploy field radiological monitoring teams to perform direct radiation measurements and air sampling.
* Perform dose calculation activities.
Correlate with field team data.
* Oeploy field radiological monitoring teams to perform direct radiation measurements and air sampling.
* Perform sampling and analysis of environmental media.
* Oeploy on site damage control teams.
* Perform reactor coolant sampling and analysis.
7.1.1 Off-Site Dose Calculations Page 1 of 9 The Emergency Director is responsible for initiating off-site dose calculation and assessment activities.
These activities are performed by Radiation Protection trained personnel who report to the Technical Support Center (TSC) (or the Control Room for all initial entries into the Emergency Plan). Data from *the vent effluent monitors and the Page 2 of 9 Emergency Plan, Rev. 61, Page 79 of 298 meteorological towers serve as inputs for the off-site dose calculation methods. The ED is responsible for calling in personnel to the TSC to perform off-site dose assessment activities.
The Radiation Protection Coordinator reports to the TSC within 60 minutes of notification.
Field monitoring teams are directed to selected monitoring location(s) by either the Radiation Protection Coordinator, Dose Assessment Supervisor, Dose Assessment Staffer, or Field Team Director via radio and/or phone communication.
The results of the teams' surveys are used to update projected doses and dose calculational assumptions.
The initial field monitoring team is staffed within 60 minutes and is dispatched from the vicinity of the plant within 60 minutes. An additional field monitoring team is staffed within 90 minutes and dispatched from the EOF. See Table 6.1 and Figures 6.2 and 6.4. Each radiological monitoring team is supplied with a survey meter and low volume air sampler. TLDs are located at 17 sites around the station to provide early information on accumulated off-site doses. Two sets of TLDs ' are provided at each of these sites; one set for dose accumulation during the period of releases and one set maintained for the normal monitoring period 9r exchanged early at the Dose Assessment Supervisor's discretion to meet information needs. The ED and Recovery Manager recommend appropriate protective actions to PEMA Operations Center, Harrisburg, based upon the results of the off-site dose assessment activities.
7 .1.1.1 Meteorology The SSES on-site meteorological measurement system is based upon an on-site primary meteorological tower located to the east southeast of the station. The primary tower provides measurements of wind speed, wind direction, and wind direction variability at its 10 and 60-meter levels, temperature differential between the 1 O and 60-meter levels, and ambient temperature and dew point at the 10-meter level. Precipitation is measured at ground level. In case of primary tower failure, a 10-meter on-site ' backup meteorological tower will provide measurements of wind speed, wind direction, and wind direction variability.
A permanent supplemental tower is installed in the river valley near the station to provicle aclclitional meteorological clata to more ' accurately moclol the effects of surrouncling terrain on atmospheric clispersion ancl transport.
The tower is located approximately
 
===3.6 miles===
aVI/ of the station off Route 93 just east of Nescopeck.
The tower measures wine! speecl, wind clirection, and sigma theta at the 33 foot level. The tower also measures temperature at a height of approximately 6.6 feet. The meteorologioal clata collected from this tmver is usecl only to support assessment ancl Page 3 of9 Emergency Plan, Rev. 61, Page 80 of 298 restoration efforts in the event there is an aeeidental release of radioactive material from SSES. The meteorological systems are instrumented to provide continuous data to the control room and the Plant Integrated Computer System (PICSY) for utilization in the TSC and EOF. Data that enters PICSY is viewable through various display formats and is also transmitted to the NRG via EROS. Digital dataloggers are present at all of the SSES meteorological towers. All data is stored locally and is available for acquisition by interrogation across telephone lines. Primary and backup tower strip chart recorders are located in the control room. Site specific, meteorological information for emergency dose assessment purposes can also be obtained by contacting either a meteorologist or the National Weather Service Station using the phone numbers provided in the SSES Emergency Telephone Directory.
7 .1.1.2 Radiation Protection Considerations In the event of an unplanned radioactive release from either the reactor building vents, the turbine building vents, or the standby gas treatment vent; continuous gross noble gas readings are available from the vent monitors.
Each monitor is also equipped i
* with in-line iodine and particulate sampling capability.
These in-line samples are periodically removed and analyzed in order to provide iodine and particulate release rate information.
Event declarations are based on Noble Gas readings or iodine and particulate sample results. The following Radiation Protection considerations are taken into account: selection of the accident type to closely approximate the isotopic mix and average gamma energies of the release radioactive decay from time of reactor shutdown, plume
* decay-in-transit and iodine and particulate depletion due to precipitation.
7.1.1.3 Dose Calculations for Airborne Releases A dose calculation model is used to make current, site specific estimates and predictions of atmospheric effluent transport and diffusion during and immediately following an accidental airborne radioactivity release. The purpose of the prediction is to provide an input to the assessment of the consequences of accidental radioactive releases to the atmosphere and to aid in the implementation of emergency response decisions.
Page 4 of9 Emergency Plan, Rev. 61, Page 81 of 298
* The dose calculation model used is a fast running, time-dependent, variable trajectory plume segment "B" model with the following capabilities:
NOTE: A class "B" model is a numerical model that represents the actual spatial and temporal variations of plume distribution.
* Computes atmospheric dispersion at the site based on atmospheric stability as a function of site : specific terrain conditions with 15-minute upgrades of source term and meteorological conditions.
'
* Provides estimates of deposition and relative concentration of radioactivity within the plume exposure and ingestion EPZs for the duration of the release.
* Incorporated in the calculations is wet and dry deposition which enables dose estimates from thr$e pathways -plume, ground shine, and ingestion.
The dose program complies with the "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," (EPA-400), adopting the dose calculation methodology in ICRP #26/30. The accident dose assessments are based on the adult physiology per ;
* EPA 400, except for one case-that is, child thyroid dose conversion factors are used in calculating thyroid COE. However adult physiology is used in calculating thyroid COE for purposes of evaluating the need for a sheltering only PAR afl&-When evaluating*
controlled venting of containment.
Calculations of TEDE are made
* using the (adult) dose factors provided in EPA-400. The following calculational options are available:
* TEDE (Total Effective Dose Equivalent) integrated doses consisting of the sum of external doses from plume shine, 50 year committed effective dose equivalent from inhalation (CEDE), and 4 day ground shine doses.
* EDE and COE dose rates for field team management.
* Fifty year thyroid committed dose (COE), from inhalation of radioactive materials.
* Population dose (person rem) out to 50 miles. i
* Summary print of projected doses for each of four projection tim~s.
* Integrated ground dose for projected times specified by the user. ' I Emergency Plan, Rev. 61, Page 90 of 298 TABLE 7.2 EMERGENCY EXPOSURE CRITERiA Additional General Criteria
* Only volunteers are given planned emergency exposure.
* Attached tables provide information concerning acute and delayed health effects.
* Whenever practical, consideration is given to dividing exposure among as many personnel as possible.
* Potassium Iodide utilization for iodide prophylaxis requires the approval of the Emergency Director or the Recovery Manager in consultation with the Radiation Protection Coordinator or the Dose Assessment Supervisor and medical consultants, if available.
It is recommended that potassium iodide be administered in situations where potential exposure of the thyroid is anticipated to exceed 10 rem or at lower dose levels if judged as needed by the RPC or DASU.
* All reasonable measures must be taken to control contamination and internal exposure.
* Persons performing e*mergency activities should be familiar with exposure consequences.
* Women capable of reproduction should not take part in these actions.
* Retrospective doses are evaluated on an individual case basis.
* To tho extent reasonable, persons with high lifetime cumulative radiation exposure should , not take part in these actions.
* As in the case of normal occupational exposure, doses received under emergency conditions should be maintained as low as reasonably achievable.
Health Effects Associated with Whole Body Absorbed Doses Received Within a Few Hours(a) Whole Body Absorbed Dose Early Fatalities(b)
Prodromal Effects(c) (rad) (percent) (percent affected) 050 -2 100 -15 140 5 -150 -50 200 15 85 250 -98 300 50 -400 85 -460 95 -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 Forewarning symptoms of more serious health effects associated with large doses of radiation.
Page 2 of3 Emergency Plan, Rev. 61, Page 95 of 298 -8.0 ,EMERGENCY FACILITIES AND EQUIPMENT 8.1 ON-SITE EMERGENCY CENTERS 8.1.1 8.1.2 Page 1 of 16 Control Room The Control Room is the primary location for the initial assessment and coordination of corrective actions for all emergency conditions.
The Control Room is equipped with the display and controls for all critical plant systems, radiological and meteorological monitoring systems, and all station communication systems. Reference Appendix D, Enclosure
: 7. ,. ' ! Off-site emergency functions initially served by the Control Room ar~ transfJrred to the TSC or EOF for an Alert, a Site Area Emergency, or a General Emerg'ency as deemed appropriate by the ED. If the TSC and/or EOF are staffed, the :
* functions may also be transferred at the Notification of Unusual Event level. ;The primary consideration is to ensure that the number of personnel involved with the
* emergency in the Control Room shall not impair the safe and orderly shutdown of the reactor or the operation of plant safety systems. ' Operations Support Center The OSC is the primary on-site assembly area for operations support team personnel during an emergency.
There are 2 OSC areas-a primary OSC :. located separate from the TSC and Control Room and a backup OSC located in the Control Structure.
The primary OSC is located on the first floor of the;. South (Administrative)
Building.
The backup OSC occupies 340 square feet adjacent to the Control Room on Elevation 729'-1" of the control structure. ,
* The OSC is utilized initially as the central location for assembly and . . accountability of on-shift emergency team personnel required to perform suc;h functions as: firefighting, first aid, search and rescue, damage control, and : on-site radiation monitoring.
If and when the TSC is activated, all I non-operations support team personnel assemble and are accounted for in 1 the OSC (or+SG-CR if the backup OSC is being utilized.)
TSC personnel 1 assess the need for emergency team personnel and based on this assessment, the OSC dispatches available team personnel and call in additional personnel as needed. The OSC and TSC assembly areas will be! monitored continuously for habitability.
If these areas become uninhabitable, retained personnel will be directed to alternate holding areas. Control and ; dispatch of these teams is the responsibility of the OSC Coordinator.
The 1
* OSC Coordinator manages operations and other support personnel.
' Equipment required for these teams to perform their functions, as outlined iri Appendix D is stored and maintained in the Control Room, Operations Suppprt Center, Radiation Protection access control points and Maintenance tool areas. ,+,'
Emergency Plan, Rev. 61, Page 106 of 298 8.3 COUNTY AND STATE EMERGENCY CENTERS 8.3.1 County Emergency Centers Both LCEMA and CCEMA have EOCs that meet or exceed the minimum Federal criteria for sufficient space, communications, warning systems, self-sufficiency in supplies and accommodations and radiological protection factor. Both counties maintain full-time employees, providing 24-hour per day coverage either at their EOC or their "911" Centers, to coordinate emergency planning and evaluation. "CTN" telephone connections exist between SSES and each County EOC. Location of the county EOCs:
* Luzerne County Emergency Management Building Wilkes-Barre, Pennsylvania
* Columbia County Columbia County Courthouse 911 Annex Bloomsburg, Pennsylvania
 
====8.3.2 State====
Emergency Center The State EOG is losatod at tho PEM/\ hoadquartorsCommonwealth Response Coordination Center (CRCC};-is located at~1310 Elmerton Avenue iD._Harrisburg.
This center has 24 hour per day coverage and is equipped with a reliable communications system that includes "CTN" telephone connections between the eGC-CRCC and SSES, and ties to all area and county EOCs. During an emergency, representatives from , appropriate State agencies will assemble at the State EOCCRCC to manage and support the emergency response activities.
Facilities are also available' at the EOF for PEMA personnel.
 
===8.4 ASSESSMENT===
 
CAPABILITIES
 
====8.4.1 Radiation====
 
Monitoring System This on-site system, consisting of ARMs, CAMs, and process monitors, contributes to personnel protection, equipment monitoring and accident assessment by measuring and recording radiation levels and concentrations at selected locations throughout the station. Reference Appendix D. 8.4.2 Fire Protection Page 12 of 16 Fire protection at SSES is provided by a network of fire detection, suppression, and extinguishing systems. These systems and associated fire alarms are activated by a variety of fire and smoke detection devices throughout the plant. Types of detectors include combustion product, smoke, thermal, and flame. For more detail, reference the SSES Fire Protection Review Report.
Emergency Plan, Rev. 61, Page 108 of 298 8.5.4 Alert Notification System An ANS consisting of sirens with ratings of 121 dB.at 100' exists within the ten-mile EPZ around SSES. Siren location (see Figure 8.4) was determined by a detailed study including field surveys, actual determination of average background noise level, and consideration of population distribution within the 10-mile EPZ. Activation of the ANS is via radio control from either the LCEMA Emergency Operations Center or CCEMA Emergency Operations Center. A back-up satellite system can also activate the sirens from LCEMA or CCEMA. A redundant control station located at SSeS and the EOF has full radio control capabilities, and will be used for the purpose of testing and maintenance activities.
Direct Current (DC) batteries provide a back-up source of power to the normal Alternating Current (AC) supply. The Nuclear Emergency Alert signal is a 3 minute steady tone. Public response to this signal is to proceed indoors and tune their radio or television to the Emergency Alert System Network serving their local area for additional information.
Testing of the system takes place annually and includes verification of the system's ability to alert the general public. 8.6 ADDITIONAL COMMUNICATIONS SYSTEMS 8.6.1 Commercial Telephone System 8.6.2 Two independent telecommunications networks exist to provide primary and backup telephone communications between ERFs and offsite agencies.
These systems are the Centrex Telephone Network (CTN) and Electronic Tandem Network (ETN). CTN extension locations include: Control Room, TSC, EOF, JIC, SEIC, DEP/BRP, PEMA, LCEMA, and CCEMA. This is the primary system for emergency communications.
Plant Emergency Alarm System A plant emergency alarm system provides audible warning of emergency conditions to plant personnel.
The system consists of a multi-tone generator, tone selector switch, area selector switch, and message tape recorder.
The Emergency Alarm System is integral to the PA System and is powered via the Vital AC UPS. The Plant Emergency Alarm System is tested at least weekly. 8.7 ON-SITE FIRST AID AND MEDICAL FACILITIES A first aid treatment facility, equipped with normal industrial first aid supplies, is located on the first floor of the S&A Building.
Standard first aid kits are at designated locations throughout the station. Inventories are performed regularly.
Page 14 of 16 ' . 1 *"
Emergency Plan, Rev. 61, Page 109 of 298 8.8 DAMAGE CONTROL EQUIPMENT Damage control equipment consists of normal and special purpose tools and devices used for maintenance functions throughout the station. The ED has access to keys for maintenance tool cribs, shops and other locations where damage control equipment is stored. Inventories are performed regularly.
 
===8.9 INFORMATION===
 
SYSTEMS 8.9.1 Plant Integrated Computer System l 1 1 1 The PICSY is used for emergency data configuration for the following reasohs: Page 15 of 16
* It contains graphic and trending capabilities.
* It provides for historical data recording and retrieval.
* It has flexibility to permit interfacing to additional 1/0 equipment and other sources of data.
* Its design provides for a high degree of reliability.
* It is capable of scanning and processingdisplayinq and reportinq-alk3f plant tl=ie--{jata needed in the EOF and TSC.
* It is located in a secure area within the control structure.
* It has a redundant system design.
* The EROS and SPDS functions are integrated into its design.
* All of the PICSY data and functions are easily made available at locations remote from SSES. 8.9.1.1 Data Acquisition Data is acquired from 1/0 hardware in the plant as well as over data interfaces to various other plant equipment.
All data is checked for validity and errors before being displayed to the user. Isolation is applied to all safety-related inputs. All data is archived.
Both short term and long term data are available for retrieval at any PICSY SOS. Long term data is available for at least the previous fuel cycle. 8.9.1.2 Data Preparation Display formats needed by the ERF are generated and stored within the PCS using standard proven PICSY software.
A configuration management software system is employed to track changes to all formats and the database itself. Proven system and application software has been developed which performs data display and system security.
The database includes raw data, data converted to engineering units, data checked on a real-time basis, and various types of calculated data. User interaction from the PICSY SOS is independent from each station and controlled by multiple copies of the identical software.
i i 9.1.3 Page 5 of 8 Emergency Plan, Rev. 61, Page 120 of 298 Overall Coordination of Nuclear Emergency Preparedness The Manager EmergenoyManager-Security/Emergency Preparedness is responsible for the overall coordination of all nuclear emergency planning activities.
The Manager EmergenoyManager-Security/Emergency Preparedness is assisted in this effort by: the Plant Manager for activities involving the Susquehanna Site, the General Manager-Nuclear Engineering for engineering issues, the Manager-Nuclear Training for on-site training, the Community Relations Manager-Susquehanna for communications with the public and news media, and the Manager-Nuclear Oversight for audits of Emergency Planning.
The Manager EmergenoyManager-Security/Emerqency Preparedness is
* typically responsible for:
* Revising of the SSES Emergency Plan
* Revising of EP-PSs and other Emergency Planning Administrative procedures
* Conducting of integrated drills and exercises and communication drills
* Defining EP training scope for ERO
* Defining EOF ahd JIC EP Training
* Coordinating EP interface between State and Federal agencies
* Coordinating maintenance and testing of ANS
* Coordinating interface between state, county, municipal, and Susquehanna ERO
* Assuring operational readiness of Emergency Response Facilities
,*, ! 
 
===9.2 Emergency===
 
Plan, Rev. 61, Page 121 of 298 REVIEW AND UPDATING 9.2.1 SSES Emergency Plan 9.2.2 The Manager EmergencyManager-Security/Emergency Preparedness is responsible for the review and revision of the SSES Emergency Plan, ensuring:
* A review of the SSES Emergency Preparedness Program is performed periodically by persons who have no direct responsibility for implementation of the program in accordance with 1 OCFR50.54t.
* Annual review of the SSES Emergency Plan.
* Annual review of Letters of Agreement.
* Recommendation of Emergency Plan changes to PORC.
* PORC review of Emergency Plan changes and submission of changes to NSRB.
* Revisions or a report of change to the Emergency Plan that do not change the effectiveness of the plan are submitted to the NRC within 30 days from the implementation of such change(s).
* Perform an annual review of the Evacuation Time Estimate (ETE) to ensure 1 OCFR50 Appendix E Section IV and NU REG 0654 Element J.8 requirements are maintained.
Update the full ETE should the criteria from Appendix E be met and re-submit the ETE to the NRC. Emergency Plan Procedures The Manager EmergencyManager-Security/Emergency Preparedness is responsible for the review and revision(s) of the Emergency Plan Procedures, ensuring:
* The periodic review is accomplished in accordance with established plant procedures.
* Revisions to procedures are done in accordance with established plant procedures.
* Controlled copies of procedure revisions are issued by station document control programs.
* ERO personnel are briefed on revisions as required.
Page 6 of 8 J /' ;"
9.3 9.4 Emergency Plan, Rev: 61, Page 122 of 298 MAINTENANCE AND INVENTORY OF EMERGENCY EQUIPMENT/SUPPLIES The Manager EmergencyManager-Security/Emergency Preparedness is responsible for periodic inventory and inspection of emergency equipment and supplies, and for periodic testing of emergency communications systems. This testing includes verification of 1 phone numbers that are contained in Emergency Plan procedures.
i*. Equipment, supplies, and parts having limited shelf lives are checked and replaced as ; necessary.
Monthly communications drills and tests are also conducted from Susquehanna.
ERFs and offsite agencies.
; Any deficiencies found during these activities are either cleared immediately or documented for corrective action. PUBLIC EDUCATION AND INFORMATION Under the direction of the Manager EmergencyManager-Security/Emergency Preparedness, the following methods are utilized to ensure that emergency planning information and education is provided and transmitted to residents and transients in the EPZ annually.
 
====9.4.1 Telephone====
 
Directory Inserts 9.4.2 With the cooperation of Pennsylvania Emergency Management Agency, Luzerne County Emergency Management Agency, and Columbia County Emergency Management Agency, emergency information is provided in all telephone directories distributed within the ten mile EPZ. This information includes:
* explanation of Emergency Classifications
* what to do when you hear the sirens
* public Protective Actions
* student pick-up points
* evacuation routes to reception centers
* evacuation Plan Map
* callback number for special needs Programs are Offered to Acquaint the News Media With: ''
* SSES Emergency Plan i
* information concerning radiation l 9.4.3 9.4.4
* points of contact for the release of public information during an emergenby'
* l Educational Training Programs 1 Educational training programs on emergency preparedness are made available to the general public through the staffs of the Susquehanna Energy Information Center and Nuclear Emergency Preparedness.
l, t ~" Other Distributed Publication(s)
{For example: Offsite Emergency Calemlars).
This information includes:
* explanation of Emergency Classifications
*
* what to do when you hear the sirens
* public Protective Actions
* student pick-up points
* evacuation routes to reception centers
* evacuation Plan Map
* callback number for special needs Page 7 of 8 (' i:
Emergency Plan, Rev. 61, Page 127 of 298 Letters of Agreement have been established with those State and Local agencies as well as local and industry support service groups that are responsible to ensure a high level of emergency preparedness for the SSES. These agreements have been established to assure all parties are aware of their commitment to SSES and the public in the vicinity of the SSES during an emergency including a HOSTILE ACTION event. The following list of agencies and support groups have signed letters of agreement:
Agency/Support Group Berwick Ambulance Association Berwick Hospital Center Berwick Volunteer Fire Department Columbia County Commissioners Dan E. Bower. Inc Department of Energy Department of Environmental Protection/Bureau of Radiation Protection Federal Radiation Monitoring and Assessment Center (FRMAC) GE BWR Emergency Support Geisinger Medical Center Hobbie Volunteer Fire Co. -EMS Hunlock Creek Ambulance Association Institute of Nuclear Power Operations Lackawanna County Commissioners Latona Trucking Luzerne County Council Medico Industries Mocanaqua Volunteer Fire Company Nanticoke Ambulance/Medic 25 Nanticoke Fire Department National Weather Service Pennsylvania Emergency Management Agency Pond Hill-Lily Lake Ambulance Association PPL Electric Utilities Salem Township Volunteer Fire Co. ahickshinny Volunteer fire Department Shickshinny Volunteer Ambulance Assoc. Stell Enterprises Summerhill Fire Department Wilkes Barre Scranton International Airport Page 2 of3 Timothy s. Rausch Senior Vice President
& Chief Nuclear Officer April 2, 2018 Attn: Mr. Stephen G. Bower, Vice President Don E. Bower, Inc. 1206 Salem Boulevard Berwick, PA 18603 Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3445 Fax 570.542.1504 Tlmothy.Rausch@talenenergy.com SUSQUEHANNA STEAM ELECTRIC STATION LETTER OF AGREEMENT
-2018 DON E. BOWER, INC. PLE*0026052
 
==Dear Mr. Bower:==
TALEN-~ ENERGY This letter will serve as an agreement between Don E. Bower, Inc. and the Susquehanna Steam Electric Station concerning heavy equipment support operations at the Susquehanna Steam Electric Station. Don E. Bower, Inc. agrees to provide heavy equipment support operations, including personnel and equipment, at the Susquehanna Steam Electric Station as may be required.
Services provided will be at a negotiated rate agreed upon by both parties. The Susquehanna Steam Electric Station agrees to pay for any damages to equipment incurred as a result of the performance of this agreement.
In the event any such equipment cannot be decontaminated; Susquehanna Steam Electric Station will replace it. This agreement will remain in effect indefinitely unless terminated by either party giving thirty (30) days advance written notice of termination to the other party. Please signify acceptance of the provisions of this letter by executing the agreement and returning the original copy in the self-addressed prepaid envelope included in this mailing. You may keep a copy for your files. If you have any questions, please contact Joseph Meter at 570-542-3789.
Thank you fo~ your cooperation in this matter. TSR:db {Continued)
PLE-0026052 an authorized representative of Don E. Bower, Inc., on this Copy: NUC EPian File (Original}
NUCSA4 Pre. s ; [Print} 30 dayof (Title),
Timothy S. Rausch Senior Vice President
& Chief Nuclear Officer August21,2018 Attn: Fire Chief Summerhill Fire Company 422 Summerhill Road Berwick, PA 18603 Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3445 Fax 570.542.1504 Tlmothy.Rausch@talenenergy.com SUSQUEHANNA STEAM ELECTRIC STATION LETTER OF AGREEMENT-2018 SUMMERHILL FIRE DEPARTMENT PLE~ 0026081
 
==Dear Fire Chief:==
TALEN~ ENERGY This letter will serve as an agreement between the Summerhill Fire Company and the Susquehanna Steam Electric Station concerning firefighting assistance at the Susquehanna Steam Electric Station. Summerhill Fire Company agrees to provide firefighting assistance, including personnel and equipment, at the Susquehanna Steam .Electric Station as may be required, fo include response to hostile action based events. Susquehanna Steam Electric Station agrees to pay for any damages to firefighting equipment incurred as a result of in the performance of this agreement.
In the event any such equipment cannot be decontaminated, The Susquehanna Steam Electric Station will replace it. Susquehanna Steam Electric Station also agrees to provide appropriate training for those firefighting personnel designated by an authorized representative of the Summerhill Fire Company. This will include familiarization training involving specific firefighting equipment and systems at the Susquehanna Steam Electric Station. This agreement will remain in effect indefinitely unless terminated by either party giving thirty (30) days advance written notice of termination to the other party. Please signify acceptance of the provisions of this letter by executing the agreement and returning the original copy in the self-addressed prepaid envelope included in this mailing. You may keep a copy for your files. If you have any questions, please contact Megean Srown at 570-542-3601.
Thank you for your cooperation in this matter. Timo y S ausch, Sr. Vice President
& Chief Nuclear Officer Susq anna Steam Electric Station TSR:db (Continued)
PLE-0026081 . 1 _c_**_<-_,--c<'-'j',__<;:_-~_,~'$_4~*-.-
___ (Name) ~{'~ C 1-.; [Print} [Print] (Title), an authorized representatlve of Summerhlll Fire Company on thls ~-"& day of -~-~---.... "'-*-='-:,_.+
_____ , 2018, agree to the provislons contained herein. [Signature]
Copy: NUC EPlan FIie (Original)
NUC 
: j. I Emergency Plan, Rev. 61, Page 128 of 298 j* These letters of agreement provide for:
* Coordination of planning efforts by State and local agencies; industry support groups; fire ambulance and hospital support services; and Susquehanna.
* Appropriate emergency response to assure employee and public safety during an emergency condition at SSES.
* Mutual notification capabilities.
* Appropriate training and exercising of emergency response capabilities.
* Fire, first aid and medical support.
* Environmental monitoring and assessment support.
* Other emergency support services as deemed necessary The Manager EmergenoyManager-Security/Emergency Preparedness is responsible for renewing letters of agreement every year where applicable.
In some instances, where the letter of agreement is for a specified duration longer than 1 year, letters need not be renewed until the end of the specified duration.
Copies are maintained and controlled within Document Control Services to assure appropriate review and updating takes place. NOTE: Page 3 of3 Reference Action Request 1066721 for why separate LOA is not needed for Pennsylvania State Police.
Emergency Plan, Rev. 61, Page 147 of 298 APPENDIXC SSES EMERGENCY PLAN POSITION SPECIFIC PROCEDURES (TYPICAL) j, s,+:\""'+/-Pfc',5,, .XC-,,&#xa3;-"'Ji'&#xa3;"':Tu~ -F ,*,,,h "C,,% :>s,-,: -Qffe,-,Af<-"'Mn'O,vy-m.'~,.,"'
>~ "'"~ ,cw'), ~j'f' ,Ci ,5".-iJA"<<;;, \ "'~'.'-~,)T'"'
~'-YS//Y >1'.' 7A CA, ,c,,,,cs2'i!Y'x-:>"'-"'*
4 "'"'"H "'+c,,c j EMERGENCY PLAN POSITION SPECIFIC PROCEDURES (Response Procedures)
CR Procedures EOF Procedures Emeraency Director Recoverv Manaaer Emeraency Plan Communicator EOF Support Supervisor NRG Communicator NEP Duty Planner EOF Emeraency Plan Communicator TSC Procedures Environmental Samplina Team Emergency Director Radioloaical Monitorina Team TSC Technical Support Coordinator EOF Administrative Assistant TSC Operations Coordinator EOF Liaison Support Supervisor Radiation Protection Coordinator EOF Dose Assessment Staffer TSC Dose Calculator EOF Dose Assessment Supervisor RP Tech I (Oscar) Field Team Director Security Coordinator EOF Environmental Samplina Director TSC Administrative Coordinator EOF Technical Advisor TSC E Plan Communicator eQi::; IAfeFFRatieA GeeFEiiAateF HPN Communicator Enaineerina Support Supervisor RP II Dose Calculator Fuels Lead Engineer/
Core Thermal Hydraulics Enaineer Damaae Control Team Coordinator EOF Systems Lead Enaineer Severe Accident Management Coordinator EOF Support Enaineer TSC NRG Communicator TSC Information Coordinator JIC Procedures Fuels Lead Engineer/
Core Thermal Public Information Manager Hydraulics Enaineer TSC RP Radio Communicator News Manaaer JIG Technical Briefer Support Services Manaaer OSC Procedures Media & Public Officials Contact OSC Coordinator JIG Loakeeper RP Specialist JIG Writer Maintenance Foreman/Field Unit Supervisor JIG Administrative Coordinator Chemistrv Coordinator GSG GleFk OTHER EMERGENCY PLAN RESPONSE PROCEDURES Offsite Oraanization Response to Plant Events Emergency Telephone Instructions and Susquehanna Offsite Organization Response Directory to Plant Events Remote Assembly Area Contamination Control Termination and Restoration Brief Non-Technical Description of EALs EAL Classification Bases SSES MIDAS-NU User Manual Personnel Accountability Page 2 of2 r ' ; ,, ' ' j ' ' i ', ! ; i ! ' ' ' i ' ; ' ''
Emergency Plan, Rev. 61, Page 150 of 298 ENCLOSURE 1 TO APPENDIX D Typical Station Decontamination Area Equipment Decontamination Procedures Cotton Gloves Coveralls (Disposable)
Decontamination Soap Disposable Bath Towels Disposable GlovesPlastic Gloves + Cotton Inserts Frisker Hand Brushes Fland Cream Lotion Skin Cloanor Masking Tape Paper Towels Shoe Covers, paper Spare f'risker Cable Spare f'risker Probe Sponges Typical Damage Control Equipment Storage Box Contents Amprobe Bars, Pry, Large Bars, Pry, Rolling Lead Black Wire, 1/4 lb. Rolls, 16 Gauge Box, Tool, 23" Bucket, 14 quart, Plastic Cable Cutters Clamps, C, Clamps, C, Large Clamps, C, Small Electricians Pouch with Miscellaneous Hand Tools Enerpac, Rescue Unit Flashlight, 5 cell Hammer, Ball Peen, 16 oz. Hammer, Sledge, 10 lb. Hammer, Sledge, 8 lb. Multimeter Nylon Rope, 100' coils, 3/4" Nylon Rope, 25' coils, 3/8" Nylon Rope, 50' coils, 3/8" Nylon Rope, 50' coils, 3/4" Plastic Sheet, 20' X 20', Fire Retardant Pliers, Lineman Pliers, Water Pump Page 3 of 16 Plugs, Wood, 1" & 6" Plugs, Wooden Box, 1", 1Y.', 1%', 2", 2%", 3"; Rubber, Roll 1/16" thick, 10' X 3' Screwdrivers, Large Standard Screwdrivers, Medium Standard Screwdrivers, Phillips, Large i-Screwdrivers, Phillips, Medium String, Ball Twine, Bale Wedges, Wooden Wrench, Adjustable, 12" Wrench, Adjustable, 8" Wrench, Allen Pac 3/16", 7/32", 1/4", 5/16", 3(8" Wrench, Allen Pac .050", 1/16", 5/64", 3/32", l 7/64", 1/8", 9/64", 5/32", 3/16", 7/32" Wrench, Chain Wrench, Hex, #110 Wrench, Hex, #17 Wrench, Hex, 24" Wrench, Pipe, 18" Wrench, Pipe, 14" Emergency Plan, Rev. 61, Page 151 of 298 ENCLOSURE 2 TO APPENDIX D Typical Onsite Search and Rescue/First Aid, Ambulance, and Hospital Radiation Emergency Equipment and Supplies Onsite Search Rescue/First Aid: Adjustable Litter Basket Stretcher (Stokes) First Aid Team Initial Response Kit with Inventory Sheet Ambulance Kit: Masking Tape f8II Miss. PlastisWaste "Rad" Bags Plastic Gloves Cotton Gloves Hospital:
Dosimeter Charger Survey Meter Frisker with Probe Herculite white, green and yellow Lead Container, high activity samples Page 4 of 16 Folding Litter Portable Oxygen-Demand Valve (size D tank j With assorted airways, cannulas, and masks) : Scoop Stretcher
!* Trauma Kit ! Assorted Splinting Devices
* Plastis Shooting, 8' X 20'Herculite Plastis-Shoe Covers Portable Frisker and Probe Sot of Anti sontamination Clothing Lab Coats Self Reading Dosimeters Set of Radiation Signs and Ribbon Stanchions/Pylons Step-off Pad Thermoluminescent Dosimeters, badge type Thermoluminescent Dosimeters, ring type ! \
Emergency Plan, Rev. 61, Page 159 of 298 !:nc::lt)$ure s to Appendix f> (C:ont'd;j 0 ENVIRONMENTAL MONITORING;SYSTEMS
: 2. Typical Radiological Monitoring Team Equipment Emergency Planning and Grid Coordinate Maps Stopwatch, tweezers, masking tape Gamma Survey Meter with current calibration Low Volume Air Sampler and Head Potassium Iodide Tablets Radioactive Material Stickers Particulate Filters, box Silver Zeolite Cartridges Disposable Plastic Gloves Plastic sample bags and labels Flashlight Spare Batteryies and Fuse kit Self Reading DosimetryPortable Frisker with Probe 3. Typical Emergency Environmental Sample Kit Contents Assortment of Sampling Bags Flashlight Grid Coordinate Map Lo11v and High RangeElectronic Dosimeters Pliers Self Reading Dosimetry Page 12 of 16 Rubee!;!Plastic Gloves Sample Containers Sample Labels Scale Scissors Spare Batteries Emergency Plan, Rev. 61, Page 165 of 298 Timothy S. Rausch Sr. VP and CNO SUsq11ehanna Nucloar LLC 769 Salem Boulevard Berwick. PA 16603 Tel. 5"10,542.3445 Tinwthy.Rausct@TaJonEnergy com TALEN~ ENERGY July 17, 2015 SUSQUEHANNA NUCLEAR LLC POLfCY STATEMENT:
SUSQUEHANNA STEAM ELECTRIC STATION EMERGENCY MANAGEMENT Immediate response, assessment, and the implementation of protective and corrective measures pertalnlng to !
* an emergency condition at the Susquehanna Steam Electric station shall be the responsibility of the SSES Emergency Director until relieved of this function by the Recovery Manager. The individuals who shall act in the capacity of SSES Emergency Managers are determined as follows: Immediately upon the occurrence of an emergency, the Shift Manager on duty at the station shall assume the role of SSES Emergency Director, as described in the SSES Emergency Plan, until relieved of that responsibility by the Emergency Di1ectu1 01 Ids desig11ated alternate.
If the emergency requires activation of the Emergency Operations Facility (EOF), the SSES Recovery Manager shall assume responsibility for overall management of the emergency and off-site Protective Action Recommendations:
The SSES Emergency Director retalns responsibility for on-site operations.
* The SSES Emergency Managers.
shall implement applicable portions of the SSES Emergency Plan to.prevent
:
* or mitigate the consequences of emergencies at the Susquehanna Steam Electric Station. They shall have the authority to act on behalf of Susquehanna Nuclear, LLC, in all matters concerning an emergency, at least until
* such time as the scope, severity, and potential radiological consequences have been assessed, and the appropriate protective and corrective actions have been Implemented.
Following that crltlcel period, but still with complete regard for health and safety, !TJajor decisions and Corporate commitments are the responsibility of Susquehanna Nuclear, LLC, Management.
Throughout the course of an emergency condition, all expertise and support available within the Susquehanna Nuclear, LLC organization shall be provided at the request of the SSES Emergency Managers.
Page 2 of 2 ' i }'"' 
~t;id, Berryman sr. Vice President
&.Chief Nucileaf.orficer October 29,.*~0l8
$usquet.ianria
:Nq~l.ear,, LL.&#xa2; ** ,769. Salem Bouievaril Eierwick, PA ,18603 're1.5zo:s42'.2so4
'b[il~.b~rl)'.ri)~ri!'@iaJer~jierdy:c9'111 SUSQUEHANNA NlJCLEARLLCPOLIOY STATEMENT:
TALE'N~' IA ... . .. :ENERGY. :SUSQUEHANNA STEAM ELECTRIC STATION EMERGENCYMANAGEMENT Iintneoia.te
*i:e$pqn~e~
~$.$&#xa2;~$.ine11t)
'aii<l ihe)iriplei:n.q1)tatlon q:fptpt~Qtiv~zMd cotrec.tive:*tti&#xa2;a$!lfes p&#xa2;1ta:iitli.ig .to an.emergency conditi'on.a:t the Susquehanna Steam Efectrfo Station shall be the*responsibility of the ** ss}:.s Emetgency D1r~<>.to,i' u(itif rdiev~d.of thWftinctiofl' l:>y the R~cpy~ry Ma1)age1:.
'rlr~ i!1dividuals.
vfhq slia:11 act jn :th~ capacity of SSES E1rtetgency.
Managers are*deterfninelas foilows; Iinnwd iately upon .th&#xa2; occurl'ei,lce of an (,'lJ11ergenQY, the:.shHf Man~ger *011 dpty ~t,the ,station shall assume the,'role of SSES Enwrg~ncyT)irector, as'.described ih th~ SS_Es* E!liefgen&#xa2;y Pla11, J1ntil hJ"lfoV&#xa2;d of tJ1at,l'eSpcit1.s.ibJiit:y,by the En1~tg&#xa2;noy
* D.irectot or hisdesiinated altei*nate.
* ** If. the eh1etgency t&#xa2;g4it~s a&#xa2;tiva1:Jof1::6fthe E1n&#xa2;fgei1c:Y 0p~r.~ttp11$
Fadlity (EOF), the S~ES:Re.ccrvery MaQl:lgen*all a.ssume respoiisibiiityfor o:yerall management ofthe em~1'.g~n&#xa2;y
&ti.ct off~$ite P:ro.t&#xa2;ctive Act1Qti Re90111m&#xa2;nd~frotj~:
the $.SES Einergency:Director retains re~p6nsibility fot 011-+site operations.
The:SSES Emerg&#xa2;nqy iVJ)tnag~ts .shaU. lhlplement applicable portiofi:s*"<'>.fthe SSE~ Emergency Plai) to pr~y~nt .or 1nitigate.the,consequences ofe1nergencies:atfhe Susquehanna Steam Electric.Station.
They ihaU b~ve th&#xa2; authpdtyJ<:i'actonJ3ehaff qf susqu.eh~nila
'N~icleat, tlif *. i1i,;aH matt~ts:9onc~n1ii\g an ,emergency, at least until such thhe.as'the,scope, severity, and potential radiolqgical conseqlieilces have been_ ?l?Sessed, :and tll&#xa2;*~ppr\:>priate protective and C()lJC~tiye attiqns haye bee11 impl(:me1ited~
Follo:wing that critical perfod,:britstiI1 With coin.plete regard for.health ari4 ~afety~:majol' dedsioi;is an*d Cotporate conunit~~nts 1.1re the responsibjlity,ofS~1squehan11a Nuclear, LLCiManagement, Throughout the .cour:se.ofan emergrncy*
condition~
alLexpe1tise and. support;available
:withiff the. St(S91J~hatina Ni.i~H~l.ll",, J.iLQ 9i'g~hfzamm sh~U he :pro:vid,&#xa2;d
~t tbel~ql,!esiqf the ss~S Ert}ergency Managers.
Attachment A, 1 OCFRS0.54q Screening Form Screening Number: S2018-10-25-01 I Part I. Description of ActiVity Being Reviewed (event or action, or series of actions that may result in a change to the Emergency Plan or affect the implementation of the Emergency Plan). Provide the existing text and the revised text (attaching a mark-up of the existing text with proposed change can be used as an alternative):
: 1. Revision 62 of the Emergency Plan takes credit for the 2018 annual review. 2. Replaced "Manager-Emergency Preparedness" with "Manager-Security/Emergency Preparedness" throughout the document per AR-2018-04646
{$2018-03-28-01)
: 3. 4. 5. 6. Updated Figures 4.1 and 4.2 per AR-2018-13801. (this screening)
Replaced "outlines" with "outlined" in second paragraph of section 5.1.4. (this screening)
Added "(Alert or higher emergency declaration)" after "classification" in Section 6.0, phase II section. (this screening)
Removed section 6.2.7e from the Security Coordinator responsibility to section 6.2.1.p per AR-2017-09053 and AR-2017-20479. (this screening)
: 7. Combined sections 6.2.5.a with 6.2.5.i in current step 6.2.5.a and renumbered the remaining steps. (this screening)
: 8. 9. 10. 11. 12. Added steps 6.3.1.1.m and 6.3.1.4.h per AR-2018-13835 (S2018-10-02-01, changes 1.a, 7c and 7.e). Corrected typo in section 6. 3.1.5 (this screening)
Added EOF Technical Advisor position to Figure 6.4 per AR-2018-13095. (this screening)
Reordered bullets in bulleted list in section 7.1. (this screening)
Deleted reference to supplemental meteorological tower from section 7.1.1.1 per AR-2017-17969 (S2018-10-29-01/E2018-10-29-03)
: 13. Replaced "wind variability" with "wind direction variability" in the first paragraph of section 7.1.1.1. (this screening)
: 14. Replaced and with when in the seventh paragraph in Section 7.1.1.3. (this screening)
: 15. Deleted "To the extent reasonable, persons with high lifetime cumulative radiation exposure should not take part in these actions." from Table 7.2 per AR-2018-13465. (S2018-10-24-01/E2018-10-24-01)
: 16. Replaced"-" with empty spaces in Health Effects Associated with Whole Body Absorbed Doses Received Within a Few Hours Table in Table 7.2. (this screening)
: 17. 18. 19. Replaced TSC with CR in the second paragraph of section 8.1.2. (this screening)
Updated name and address for PEMA Headquarters in section 8.3.2 per AR-2018-06092. (this screening)
Updated location of the redundant control for ANS station in section 8.5.4 per AR-2018-06919. (E2018 26-01) 20. Refined description of the plant computer capabilities in the 5th bullet in Section 8.9.1. (this screening)
: 21. Removed the phrase "For Example: Offsite Emergency Calendars)" from section 9.4.4 per DPA-10-Dl-2018-06672. (this screening)
: 22. 23. 24. 25. 26. 27. Updated MOA for heavy equipment in Appendix A per ACT-02-CR-2018-03742. (E2018-10-29-01)
Updated Fire Department MOA in Appendix A per ACT-02-CR-2018-12173. (E2018-10-29-02)
Deleted "EOF Information Coordinator" from Appendix C per DPA-06-Dl-2018-06672 (S2017-10-25-01
). Deleted "OSC Clerk" from Appendix C per AR-2017-20382 (S2017-11-21-01)
Changed Appendix D Enclosures per AR-2018-04987 (E2018-04-13-01) . 1 Updated Corporate Policy letter in Appendix E with current~ signature. (this screening)
'{)"Jll (2. 1r0/r0
* CNO This screening addresses only changes 1, 3, 4, 5, 6, 7, 9, 10, 11, 13, 14, 16, 17, 18, 20, 21 and 27. All the other changes were addressed by separate 10CFR50.54(q) screening and evaluations indicated in the parenthesis.
All chanQes are shown in Attachment
: 1. Electronic Form EP-102-1, Rev. 4, Page 1 of 4 Part II. Activity a Change per Section 3.1.3? DYES (gl NO Does the activity constitute a change per definition 3.1.3 -An action that Continue to next part 10 CFR 50.54(q) results in modification or addition to, or removal from the SSES Evaluation is NOT Emergency Plan, OR the resources, capabilities and methods identified in required.
Enter justification and the plan? complete Part VI. Justification:
Change 1, 3, 18 and 27 are administrative changes concerning up-revving the SSES Emergency Plan Rev 61 (E-Plan} to rev 62 to account for the annual review and updating old maps and FEMA EOG address or m i2 /r0/10 updating MOA with current~ signature without changing any content. J C fV(:) . Changes 5, 7, 10, 13, 20 and 21 are enhancements that do not change the intent of, or affect the resources, capabilities and methods in the E-Plan. In particular, change 10 updates the EOF Organization chart with EOF Tech Advisor position that is part of the EOF organization since 2003. Note that this position is not considered a key position, has an administrative 90 minute requirement to report to EOF after receiving a pager but is not reflected in Table 6.1 of the E-Plan. This position is the equivalent of TSC Operations Coordinator who is permanently on line with the Shift Manager and, if EOF is in control of emergency, will readily communicate and advise the Recovery Manager on plant status. This change just aligns the E-Plan with the current EOF operations since 2003 and anchors this position in the E-Plan. Changes 4, 9, 14 and 17 corrected typos. In particular, change 17 corrects the location of the backup TSC that, being in the Shift Manager office, is closer to the CR than TSC. Change 6 aligns responsibilities of TSC Emergency Director (ED), TSC Security Coordinator and TSC Administrative Coordinator in the E-Plan with SSES operations since at least 1999. Per EP-PS procedures for which documentation could be found (at least since 1999), the TSC ED is responsible for ensuring next shift through the TSC Administrative Coordinator not through the TSC Security Coordinator.
No training is necessary for thins change since the TSC is operating that way per their procedures since at least 1999. This change merely aligns the responsibilities in the E-Plan with those delineated in the implementing EP-PS procedures.
Changes 11 and 16 are formatting changes. None of the applicable changes of this screening described above alter any E-Plan commitments or constitute a change per 3.1.3 of EP-102 procedure.
Part Ill. Activity Previously Reviewed?
DYES ONO Is this activity fully bounded by an NRC approved 10 CFR 50.90 submittal 10 CFR 50.54{q) Continue to next part or Alert and Notification System Design Report (44 CFR 350.14)? Evaluation is NOT required.
Enter If YES, identify bounding source document number/approval reference justification and and ensure the basis for concluding the source document fully bounds the complete Part VI. proposed change is documented below: Justification:
D Bounding document attached (optional)
Electronic Form EP-102-1, Rev. 4, Page 2 of 4 Part IV. Editorial Change DYES ONO Is this activity an editorial or typographical change such as formatting, paragraph 1 O CFR 50.54(q) Continue to numbering, spelling, or punctuation that does not change intent per definition
.3.1.4? Evaluation is NOT next part required.
Enter justification and complete Part VI. ' Justification:
Part V. Emergency Planning Element/Function Screen (Associated 10 CFR 50.47(b) planning standard function identified in brackets.)
If this activity affects any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II, then place a check in the aooropriate box. 1. Responsibility for emergency response is assigned.
[1] D 2. The response organization has the staff to respond and to augment staff on a continuing basis (24/7 D staffing) in accordance with the Emergency Plan. [1] 3. The process ensures that on shift emergency response responsibilities are staffed and assigned.
[2] D 4. The process for timely augmentation of on-shift staff is established and maintained.
[21 D 5. Arrangements for requesting and using off site assistance have been made. [3] D 6. State and local staff can be accommodated at the EOF in accordance with the Emergency Plan. [3] D 7. A standard scheme of emergency classification and action levels is In use. [4] (RSPS) D 8. Procedures for notification of State and local governmental agencies are capable of alerting them of the declared emergency within 15 minutes after declaration of an emergency and providing follow-up D notifications.
f51 (RSPS) Electronic Form EP-102-1, Rev. 4, Page 3 of 4 Attachment A, 1 OCFR50.54q Screening Form, Continued Part V. Emergency Planning Element/Function Screen (cont.) (Associated 10 CFR 50.47(b) planning standard identified in brackets.)
If this activity affects any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II, then place a check in the aooropriate box. "9. Administrative and physical means have been established for alerting and providing prompt D instructions to the public within the plume exposure pathway. [5] (RSPS) 10. The public ANS meets the design requirements of FEMA-REP-10, Guide for Evaluation of Alert and Notification Systems for Nuclear Power Plants, or compiles with the licensee's FEMA-approved ANS D desi~:m report and supportinQ FEMA aoProval letter. T51 (RSPS) 11. Systems are established for prompt communication among principal emergency response D orQanizations.
[6] 12. Systems are established for prompt communication to emergency response personnel.
[6] D 13. Emergency preparedness information is made available to the public on a periodic basis within the D plume exposure pathwav EmerQencv Plannini:i Zone (EPZ). f71 14. Coordinated dissemination of public information during emergencies is established.
[7] D 15. Adequate facilities are maintained to support emergency response.
[8] D 16. Adequate equipment is maintained to support emergency response.
[8] D 17. Methods, systems, and equipment for assessment of radioactive releases are in use. [9] (RSPS) D 18. A range of public PARs is available for implementation during emergencies.
[1 O] (RSPS) D 19. Evacuation time estimates for the population located in the plume exposure pathway EPZ are available to support the formulation of PARs and have been provided to State and local governmental D authorities.
[10] (RSPS) 20. Kl is available for implementation as a protective action recommendation in those jurisdictions that D chose to provide Kl to the public f 1 Ol 21. A range of protective actions is available for plant emergency workers duriri'g emergencies, including D those for hostile action events.[1 OJ 22. The resources for controlling radiological exposures for emergency workers are established.
(11] D 23. Arrangements are made for medical services for contaminated, injured individuals.
[12] D 24. Plans for recovery and reentry are developed.
[13] D 25. A drill and exercise program (including radiological, medical, health physics and other program areas) D is established.
[14] 26. Drills, exercises, & training evolutions that provide performance opportunities to develop, maintain, & D demonstrate kev skills are assessed via a formal critique process in order to identify weaknesses.
f141 27. Identified weaknesses are corrected.
[141 D 28. Training is provided to emergency responders.
[15] D 29. Responsibility for Emergency Plan development and review is established.
[16] D 30. Planners responsible for Emergency Plan development and maintenance are properly trained. [16] D APPLICABILITY CONCLUSION If no Part V criteria are checked, a 10 CFR 50.54(q) Evaluation is NOT required; complete Part VI. D If any Part V criteria are checked, complete Part VI and perform a 10 CFR 50.54(a) Evaluation.
Part VI. Signatures:
-:;J~ Adrian Miron 10/25/18 Preparer Name (Print) (JFG EP109) (Cj~"~ Date -:JO(;,,-/Vlt-ref( u/2/1~ Reviewer Name (Print) (JFG EP109) * /Aeft.1ewetf$ignature Date 1 f V I/ Electronic Form EP-102-1, Rev. 4, Page 4 of 4 Attachment A, 10CFR50.54q Screening Form Screening Number: S2017-10-25-01 I Part I. Description of Activity Being Reviewed (event or action, or series of actions that may result in a change to the Emergency Plan or affect the implementation of the Emergency Plan). Provide the existing text and the revised text (attaching a mark-up of the existing text with proposed change can be used as an alternative):
EP-PS-207 Rev 26 Changes 1. Added EOF Information Coordinator duties of WebEOC to procedure since the EOF Information Coordinator position is being removed. Created Attachment A, Added sections 5.6 to 5.9 2. Updated the name of Logkeeping Instructions to Logkeeping Instruction and paper Jog forms (AR-2017-27157) EP-PS-252 Rev 5 Changes 1. This procedure is being deleted due to the ERO Position of EOF Information Coordinator being removed from the Susquehanna Nuclear, LLC ERO. EOF Information Coordinator duties listed in this procedure have been relocated to EP-PS-207 as needed. Part II. Activity a Change per Section 3.1.3? Does the activity constitute a change per definition 3.1.3 -An action that results in modification or addition to, or removal from the SSES Emergency Plan, OR the resources, capabilities and methods identified in the plan? Justification:
Removing the EOF Information Coordinator (EP-PS-252) and placing their duties into the EOF Support Supervisor (EP-PS-207) is in alignment with Rev 61 of the EPlan. There is no mention in EPLan Rev 61 of the EOF Information Coordinator or WebEOC. Adding WebEOC to the EOF Support Supervisor aligns with their existing duties in the EPlan Rev 61, section 6.3.1.3 of 'Provide support to the Recovery Manager in review of plant data'. Changing their duties from maintaining their own WebEOC entries to the maintaining the overall EOF WebEOC entries is not an additional burden to the positon. Item 2 of EP-PS-207 is an editorial change. None of the changes above result in modification or addition to, or removal from the SSES Emergency Plan or the resources capabilities and methods identified in the plan. Part Ill. Activity Previously Reviewed?
Is this activity fully bounded by an NRC approved 1 O CFR 50.90 submittal or Alert and Notification System Design Report (44 CFR 350.14)? If YES, identify bounding source document number/approval reference and ensure the basis for concluding the source document fully bounds the proposed change is documented below: Justification:
D Boundini:i document attached (optional)
Part IV. Editorial Change Is this activity an editorial or typographical change such as formatting, paragraph numbering, spelling, or punctuation that does not change intent per definition 3.1.4? Justification:
DYES Jg] NO Continue to next part 10 CFR 50.54(q) Evaluation is NOT required.
Enter Justification and complete Part VI. DYES 10 CFR 50.54(q) Evaluation is NOT required.
Enter justification and complete Part VJ. DYES ONO Continue to next part ONO 10 CFR 50.54(q) Continue to Evaluation is NOT next part required.
Enter justification and complete Part VI. Part V. Emergency Planning Element/Function Screen (Associated 10 CFR 50.47(b) planning standard function identified in brackets.)
If this activity affects any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II, then place a check in the aooropriate box. Electronic Form EP-102-1, Rev. 4, Page 1 of 3 
: 1. Responsibility for emergency response is assigned.
[1] D 2. The response organization has the staff to respond and to augment staff on a continuing basis (24/7 D staffing) in accordance with the Emergency Plan. f11 3. The process ensures that on shift emergency response responsibilities are staffed and assigned.
[2] D 4. The process for timely augmentation of on-shift staff is established and maintained.
[2J D 5. Arrangements for requesting and using off site assistance have been made. [3J D 6. State and local staff can be accommodated at the EOF in accordance with the Emergency Plan. [3] D 7. A standard scheme of emergency classification and action levels is in use. [4] (RSPS) D 8. Procedures for notification of State and local governmental agencies are capable of alerting them of the declared emergency within 15 minutes after declaration of an emergency and providing follow-up D notifications.
f 51 (RSPS) Attachment A, 1 OCFR50.54q Screening Form, Continued Part V. Emergency Planning Element/Function Screen (cont.) (Associated 10 CFR 50.47(b) planning standard identified in brackets.)
If this activity affects any of the following, including program elements from NUREG-0654/FEMA REP-1 Section 11, then place a check in the aooropriate box. 9. Administrative and physical means have been established for alerting and providing prompt D instructions to the public within the plume exposure pathway. [5] (RSPS) 10. The public ANS meets the design requirements of FEMA-REP-10, Guide for Evaluation of Alert and Notification Systems for Nuclear Power Plants, or complies with the licensee's FEMA-approved ANS D design report and supportlno FEMA approval letter. rs1 (RSPS) 11. Systems are established for prompt communication among principal emergency response D oroanizations.
[61 12. Systems are established for prompt communication to emergency response personnel.
[61 D 13. Emergency preparedness information is made available to the public on a periodic basis within the D plume exposure pathway Emergencv Planning Zone (EPZ}. [71 14. Coordinated dissemination of public information during emergencies is established.
[7] D 15. Adequate facilities are maintained to support emergency response.
[BJ D 16. Adequate equipment is maintained to support emergency response.
[8] D 17. Methods, systems, and equipment for assessment of radioactive releases are in use. [9] {RSPS) D 18. A range of public PARs is available for implementation during emergencies.
[10] (RSPS) D 19. Evacuation time estimates for the population located in the plume exposure pathway EPZ are available to support the formulation of PARs and have been provided to State and local governmental D authorities.
[1 OJ (RSPS} 20. Kl is available for implementation as a protective action recommendation in those jurisdictions that D chose to provide Kl to the public [1 O] 21. A range of protective actions Is available for plant emergency workers during emergencies, including D those for hostile action events.[10]
: 22. The resources for controlling radiological exposures for emergency workers are established.
[11} D 23. Arrangements are made for medical services for contaminated, injured individuals.
[12] D 24. Plans for recovery and reentry are developed.
[13] D 25. A drill and exercise program (including radiological, medical, health physics and other program areas) D is established.
[14] 26. Drills, exercises, & training evolutions that provide performance opportunities to develop, maintain, & D demonstrate key skills are assessed via a formal critique process In order to identify weaknesses.
[14] 27. Identified weaknesses are corrected.
[14] D 28. Training is provided to emergency responders.
[15] D 29. Responsibility for Emergency Plan development and review is established.
[16] D 30. Planners responsible for Emergency Plan development and maintenance are properly trained. [16] D APPLICABILITY CONCLUSION D If no Part V criteria are checked, a 10 CFR 50.54(q) Evaluation is NOT required; complete Part VI. Electronic Form EP-102-1, Rev. 4, Page 2 of 3 D lf an Part V criteria are checked, com lete Part VI and erform a 10 CFR 50.54 q) Evaluation.
Part VI. Signatures:
Jacob Garcia Preparer .Name (Print) (JFG EP109) Date ' Q1 J H,\rlf)/J (0 26 ( 7 Date Electronic Form EP-102-1, Rev. 4, Page 3 of 3 Attachment A, 10CFR50.54q Screening Form Screening Number: S2017-11-21-01 I Part I. Description of Activity Being Reviewe~ (event or action, or series of actions that may result in a change to the Emergency Plan or affect the implementation of the Emergency Plan). Provide the existing text and the revised text (attaching a mark-up of the existing text with proposed change can be used as an alternative):
Removing all Clerical support from the Emergency Response Organization (ERO). In addition, delete the OSC Clerk procedure EP-PS-120.
Part II. Activity a Change per Section 3.1.3? Does the activity constitute a change per definition 3.1.3 -An action that results in modification or addition to, or removal from the SSES Emergency Plan, OR the resources, capabilities and methods identified in the plan? Justification:
A review of the Emergency Plan Rev 61 shows no listing of clerical support other than in attachment C of the EPlan for the OSC Clerk position which is listed as a 'typical' position.
-The OSC Clerk, and the other clerical positions perform the administrative tasks of making copies, taking notes, taking phone calls or faxing information to other facilities.
Having the OSC responders perform those functions on their own was tested during the Aug 1 2017 Full Scale drill which was very involved with the OSC. In addition, the TSC, EOF and JIG were tested without their clerical support during the Aug 1 Full Scale drill as well. There was no reduction in capability of the TSC, OSC, EOF or JIG to perform their roles based on this change. Rev 42 of the Emergency Plan, which is SSES SER in regards to staffing does not mention the OSC Clerk nor other clerical support in any place other than 'typical' procedures listed in attachment C. Removing clerical support is not a reduction to SSsS implementation of the emergency plan. Therefore, removing the clerical support from the ERO is not a modification or addition to, or removal from the SSES Emergency Plan, OR the resources, capabilities and methods identified in the plan. Part Ill. Activity Pr~viously Reviewed?
Is this activity fully bounded by an NRG.approved 10 CFR 50.90 submittal or Alert and Notification System Design Report (44 CFR 350.14)? If YES, identify bounding source document number/approval reference and ensure the basis for concluding the source document fully bounds the proposed change is documented below: Justification:
D Bounding document attached (ootional)
Part IV. Editorial Change Is this activity an editorial or typographical change such as formatting, paragraph numbering, spelling, or punctuation that does not change intent per definition 3.1.4? Justification:
Electronic Form EP-102-1, Rev. 4, Page 1 of 3 DYES lgJ NO Continue to next part 1 O CFR 50.54(q) Evaluation ls NOT required.
Enter justification and complete Part VI. DYES 10 CFR 50.54(q) Evaluation is NOT required.
Enter justification and complete Part VJ. DYES ONO Continue to next part ONO 10 CFR 50.54(q) Continue to Evaluation is NOT next part required.
Enter justification and complete Part VI.
Part V. Emergency Planning Element/Function Screen (Associated 10 CFR 50.47(b) planning standard function identified in brackets.)
If this activity affects any of the following, including program elements from NUREG-0654/FEMA REP-1 Section IJ, then place a check in the aooroprlate box. 1. Responsibility for emergency response is assigned.
[1J D 2. The response organization has the staff to respond and to augment staff on a continuing basis (24/7 D staffing) in accordance with the Emergency Plan. [11 3. The process ensures that on shift emergency response responsibilities are staffed and assigned.
[2] D 4. The process for timely augmentation of on-shift staff is established and maintained.
[2J D 5. Arrangements for requesting and using off site assistance have been made. [3J D 6. State and local staff can be accommodated at the EOF in accordance with the Emergency Plan. [3J D 7. A standard scheme of emergency classification and action levels is in use. [41 (RSPS) D 8. Procedures for notification of State and local governmental agencies are capable of alerting them of the declared emergency within 15 minutes after declaration of an emergency and providing follow-up D notifications.
[5J (RSPS) Electronic Form EP-102-1, Rev. 4, Page 2 of 3 Attachment A, 1 OCFR50.54q
*screening Form, Continued Part V. Emergency Planning Element/Function Screen (cont.) (Associated 1 O CFR 50.47(b) planning standard identified in brackets.)
If this activity affects any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II, then place a check in the appropriate box. ' 9. Administrative and physical means have been established for alerting and providing prompt D instructions to the public within the plume exposure pathway. [5] (RSPS) 10. The public ANS meets the design requirements of FEMA-REP-10, Gulde for Evaluation of Alert and Notification Systems for Nuclear Power Plants, or complies with the licensee's FEMA-approved ANS D design report and surmortinq FEMA aooroval letter. rs1 (RSPS) 11. Systems are established for prompt communication among principaf emergency response D oraanizations.
f6l 12. Systems are established for prompt communication to emergency response personnel.
[6] D 13. Emergency preparedness information is made available to the public on a periodic basis within the D plume exposure pathwav Emeraencv Planning Zone (EPZ). [7] 14. Coordinated dissemination of public information during emergencies is established.
[7] D 15. Adequate facilities are maintained to support emergency response.
[81 D 16. Adequate equipment is maintained to support emergency response.
[8J D 17. Methods, systems, and equipment for assessment of radioactive releases are in use. [9J (RSPS) D 18. A range of public PARs is available for implementation during emergencies.
[1 OJ (RSPS) D 19. Evacuation time estimates for the population located in the plume exposure pathway EPZ are available to support the formulation of PARs and have been provided to State and local governmental D authorities.'
r1 Ol (RSPS) 20. Kl is available for implementation as a protective action recommendation.
in those jurisdictions that D chose to provide Kl to the public [1 OJ 21. A range of protective actions is available for plant emergency workers during emergencies, Including D those for hostile action events.[10J
* 22. The resources for controlling radiological exposures for emergency*workers are established.
[11] D 23.
* Arrangements are made for medical services for contaminated, injured individuals.
[12] D 24. Plans for recovery and reentry are developed.
[13] D 25. A drill and exercise program Oncluding radiological, medical, health physics and other program areas) D is established.
[14] 26. Drills, exercises, & training evolutions that provide performance opportunities to develop, maintain, & D demonstrate kev skills are assessed via a .formal critique process in order to identifv weaknesses.
[14J 27. Identified weaknesses are corrected.
[14] D 28. Training is provided to emergency responders.
[15] D 29. Responsibility for Emergency Plan development and review is established.
[16] L J 30. Planners responsible for Emergency Plan development and maintenance are properly trained. [16] D APPLICABILITY CONCLUSION D If no Part V criteria are checked, a 1 O CFR 5D.54{q) Evaluation is NOT required; complete Part VI. D If anv Part V criteria are checked, complete Part VI and perform a 10 CFR 50.54(q) Evaluation*.
Part VI. Signatures:
~~u&~z--Jacob Garcia 11/21/2017 Preparer Name (Print) (JFG EP109) .? Preparer Signature Date Jot-M0l:;R.. ~J. (l/JJt~ 11/11 /;7 Re.viewer Name (Print) (JFG EP109) fi'Rey{ewer Sigbature
-Date I . /I -(/ Electronic Forni EP-102-1, Rev. 4, Page 3 of 3 Attachment A, 10CFR50.54q Screening Form ScreeninQ Number: S2018-03-28-01 I Part I. Description of Activity Being Reviewed (event or action, or series of actions that may result in a change to the Emergency Plan or affect the implementation of the Emergency Plan). Provide the existing text and the revised text (attaching a mark-up of the existing text with proposed change can be used as an alternative):
The attached current organization chart and DLAP article describe the changes that are being made to the SSES organizational structure.
These changes are being made by SSES Senior Management to streamline the organization.
Part II. Activity a Change per Section 3.1.3? Does the activity constit&#xb5;te a change per definition
: 3. .3 -An action that results in modification or addition to, or removal from the SSES Emergency Plan, QB the resqurces, capabilities and methods identified in the plan? Justification:
See Part IV Part Ill. Activity Previously Reviewed'?
Is this activity fully bounded by an NRC approved 10 CFR 50.90 submittal or Alert and Notification System Design Report (44 CFR 350.14)? If YES, identify bounding source document number/approval reference and ensure the*basis for concluding the source document fully bounds the proposed change is documented below:
* Justification:
D Boundina document attached (ootional)
(:'art IV. Editorial Change Is this activity an editorial or typographical change such as formatting, paragraph numbering, spelling, or punctuation that does not change intent per definition 3..1.4? Electronic Form EP-102-1, Rev. 4, Page 1 of 3 [8J YES Continue to next part DYES 10 CFR 50.54(q) Evaluation is NOT required.
Enter justification and complete Part VI. l2J YES ONO 10 CFR 50.54(q) Evaluation is NOT required.
Enter justification and complete Part VI. fgJ NO Continue to next part ONO 10 CFR 50.54(q) Continue to Evaluation is NOT next part required.
* Enter justification and complete Part VI.
Justification:Definition
 
====3.1.4 states====
in part -Change to position titles when no responsibilities for that position have changed. The changes described in the attached DLAP do not affect the SSES Emergency Response Organization (ERO). Instead they are-changes to titles and reporting relationships within the SSES normal operating organization.
These changes do not reduce or eliminate the responsibilities, activities or duties that are conducted by ERO. The changes also do not affect the function or description of Organization Control that is described in sections 4.2.2, 6.1, 6.2, 6.3, and Table 6.1, or the responsibilities of the Manager -Emergency Preparedness in sections 9.2, 9.3, 9.4 and Appendix A of the SSES Emergency Plan Revision 61. The changes do affect the reporting path for the Emergency Preparedness (EP) group; however this change only affects the organizational position to which the EP group reports directly.
This group had reported to the Site Vice President via the Plant Manager via the GM -Support via the Manager -Emergency Preparedness.
The EP group will now report to the Site Vice President via the Manager -Security/Emergency Preparedness.
This change will increase the organizational accessibility of the EP group to the Sr. Vice President and CNO. All of the current requirements for the Manager -Emergency Preparedness will be excuted or deligated as appropriate by the Manager -Security/Emergency Preparedness.
This change is organizational in nature and does not affect the SSES Emergency Plan commitments or the resources available to meet those commitments.
In addition, these changes do not affect the ability to staff the required on-call ERO positions or t~e EP group. AR-2018-04646 will track the need to change the Manager -Emergency Preparedness to Manager -Security /Emergency Preparedness in the Emergency Plan. Part V. Emergency Planning Element/Function Screen (Associated 10 CFR 50.47(b) planning standard function identified in brackets.)
If this activity affects any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II, then place a check in the aoorooriate box. 1. Responsibility for emergency response is assigned.
[1] D 2. The response organization has the staff to respond and to augment staff on a continuing basis (24/7 D staffino) in accordance with the Emeraencv Plan. r11 3. The process ensures that on shift emergency response responsibilities are staffed and assigned.
[2] D 4. The process for timely augmentation of on-shift staff is established and maintained.
[2] D 5. Arrangements for requesting and using off site assistance have been made. [3] D 6. State and local staff can be accommodated at the EOF in accordance with the Emergency Plan. [3] D 7. A standard scheme of emergency classification and action levels is in use. [4] (RSPS) D 8. Procedures for notification of State and local governmental agencies are capable ofalerting them of the declared emergency within 15 minutes after declaration of an emergency and providing follow-up D notifications.
[51 (RSPS) Electronic Form EP-102-1, Rev. 4, Page 2 of 3 Attachment A, 1 OCFR50.54q Screening Form, Continued Part V. Emergency Planning Elemen~Function Screen (cont.) (Associated 10 CFR50.47(b) planning standard identified in brackets.)
If this activity affects any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II, then Place a check in the aooropriate box. 9. Administrative and physical means have been established for alerting and providing prompt D instructions to the oublic within the olume exoosure oathwav. rs1 (RSPS) 10. The public ANS meets the design requirements of FEMA-REP-10, Guide for Evaluation of Alert and Notification Systems for Nuclear Power Plants, or complies with the licensee's FEMA-approved ANS D design report and supporting FEMA aooroval letter. [51 {RSPS) 11. Systems are established for prompt communication among principal emergency response D oraanizations.
rs1 . 12. Systems are established for prompt communication to emergency response personnel.
[6] D 13. Emergency preparedness information is made available to the public on a periodic basis within the D plume exposure pathwav Emergencv Plannina Zone (EPZ). f7] 14. Coordinated dissemination of public information during emergencies is established.
[7J D 15. Adequate facilities are maintained to support emergency response.
[8] D . 16. Adequate equipment is maintained to support emergency response.
[8] D 17. Methods, s~stems, and equipment for assessment of radioactive releases are in use. f9J {RSPS) D 18. A range of public PARs is available for implementation during emergencies.
[10] (RSPS) D 19. *Evacuation time estimates for the population located in the plume exposure pathway EPZ are available to support the formulation of PARs and have been provided to State and local governmental D authorities.
r1 Ol (RSPS) 20. Kl is available for implementation as a protective action recommendation in those jurisdictions that D chose to orovide Kl to the oublic r101 21. A range of prote9tive actions is available for plant emergency workers during emergencies, including D those for hostile action eventsJ101
: 22. The resources for controlling radiological exposures for emergency workers are established.
[11] D 23. Arrangements are made for medical services for contaminated, injured individuals.
(12] D 24. Plans for recovery and reentry are developed.
[13] D 25. A drill and exercise program (including radiological, medical, health physics and other program areas) D is established.
r141 26. Drills, exercises, & training evolutions that provide performance opportunities to develop, maintain, & D demonstrate kev skills are assessed via a formal critiaue orocess in order to identifv weaknesses.
r14l 27. Identified weaknesses are corrected.
[14] D 28. Training is provided to emergency respond~rs.
[15] D 29. Responsibility for Emergency Plan development and review is established.
[16] D 30. Planners responsible for Emergency Plan development and maintenance are properly trained. [16] D APPLICABILITY CONCLUSION D If no Part V criteria are checked, a 10 CFR 50.54(q) Evaluation is NOT required; complete Part VI. D If anv Part V criteria are checked, comolete Part VI and perform a 10 CFR 50.54(q) Evaluation.
Part VI. Signatures:
(1~0~ 3/[).'};jh~
Joe Meter Preparer Name (Print) (JFG EP109) /I Pre(>arefflignature Date Ron Remsky n_ ,~a!Jird:e" F-()1( R-RG/1s"r::v 1 /dg/19 Reviewer Name {Print) (JFG EP109) I/ U Revf ewer Sianature VII} -r~w Dat'e ( V Electronic Form EP-102-1, Rev. 4, Page 3 of 3 TALEN~ ENERGY Susquehanna Nuclear Oiganization Revision Date: 03-07-2018 Jim Gorman, who recently served as interim Programs General Manager, has accepted the role of Manager, Nuclear Security and Emergency Preparedness
{EP), helping Susquehanna to become more efficient and provide a span of control and tested leadership for these areas. Jim reports to Site VP Brad Berryman effective today, Weds . ., Mar. 28., 2018. Other organizational changes that provide a strategic fit for the Station clude Nuclear Regulatory Affairs (NRA) and Performance Improvement (Pl), led by Manager Jason Jennings, will now report to Site Vice President Brad Berryman.
Projects and Document Control Services (DCS) will report to Divisional Chief Financial Officer Dustin Wertheimer.
For Projects, this alignment allows for improved accountability for spending, planning and more. DCS wrn not only gain an outside perspective, it will rececve leadership to drive improvement and innovation within that organization.
The Procedure Group will benefit from a new reporting structure to Plant Manager Derek Jones. "These organizational changes are just another step on our journey to ar excellence at Susquehanna Station," said Site Vice President Brad Berry~ man. "With Jim's proven leadership to these crucial Station organizations, a new reporting relationship for Regulatory Affairs and Performance provement, Dustin lending financial and strategic insight to Projects and DCS, and Procedures now reporting directly to Derek, I expect we'll all help each of them excel in their own ways." As for Nuclear Security and EP, Jim helped both of these organizations to prove rapidly when he led them earlier in his career. For EP, Jim helped lead them into the upper quartiles of nuclear performance in short order. As clear Security Manager, their tactical performance became legend as they successfully defended the Station on multiple occasions during the U.S. clear Regulatory Commission"s Force-On-Force Drill in 2014. Jim served as EP Manager for Susquehanna beginning in 2015, not only sponsible for the oversight of the EP program and its team of nine., but as Senior EP Liaison to the Federal Emergency Management Agency., the NRC Projects and DCS will now report to Divisional CFO Dustin Wertheimer, and the Pennsylvania Emergency Management Agency. From 2011 through 2015., Jim served as quehanna's Nuclear Security Manager, responsible fo,r. oversight of the physical security, access thorization, fitness for duty, medical servcces and security traintng programs.
You are encouraged to assist and *support these organizations as they settle into their new reporting roles.and these leaders as they provide new and tested direction to their teams. i,t\ ..... * ,;,,
* Team Susquehannaf Simplification.
Engagem~nt.
*.Teamwo_rk.
*: -i,_, *. ,. , . .,. . ,. ,.,.~* 'l."., '" '. ,..., ~* -** ,;*~,1-:
Talking Points/Key Messaging for Supervisors re Organizational Changes March 2018 Draft v2 SupervisorTalklng Points Re: Organizational Changes in March 2018 March 27, 2018 What's Important to Know: 1. In light of Susquehanna's pursuit of Simplification, Engagement and Teamwork, rather than simply fill an open position with another qualified candidate from inside or outside Team Susquehanna, the Senlor Leadership Team (SLT} thoughtfully reconfigured and merged the roles of Nuclear Security Manager and Emergency Planning Manager, to fit an internal candidate who will more than satisfy both of those roles. 2. Today, the SLT announced that the newly formed Nuclear Security and Emergency Planning Manager position will be led by Statfon veteran Jim Gorman, who will provide experienced, fa.miliar leadership to departments which he's successfully led in the past. 3. Jim's effective date is today, Wednesday, March 28, 2018, and he will report to Site Vice President Brad Berryman.
This move will help the Station become more efficient, providing these organizations with a strong leader, and will also give Jim a span of control in these areas. 4. Nuclear Regulatory Affairs (NRA)/Performance Improvement (Pl}, led by Jason Jennings, will
* report to Site Vice President Brad Berryman.
: 5. Projects and Document Control Services '{oCS) wilf report to Divisional Chief.Financial Officer Dusttn Wertheimer.
For Projects, this alignment allows improved accountability for spending, planning and more. For DCS 1 they'll not only gain an outside perspective, they will receive leadership to drive improvement and innovation within their organization.
: 6. The Procedure Group will benefit from a "new reporting structure to Plant Manager Derek Jones. 
,, (_ ... * ( ....... Attachment B, 1 OCFR50.54q Evaluation Checklist Evaluation Number: E2018-04-13-01 Screen Number: S not applicable Part I. Description of Proposed Change (Copy applicable information from 50.54(q) screen form Part I or attach a mark-up of the existing text with the proposed change can be used as an alternative):
See Attachment Part II. Evaluation*
of the Proposed Change for Compliance with the requirements of 10 CFR 50.47(b) and 10 CFR 50 .Appendix E: See Attachment Part Ill. Evaluation of Emergency Planning Functions, Elements, and Commitments affected by the Proposed Change and the Licensing Basis for those Functions, Elements, and Commitments:
See Attachment
* Part IV. Evaluation of the Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:
*see Attachment Part V. Evaluation Conclusion rgJYES ONO 2. Does the proposed change maintain the effectiveness of the Emergency Plan (Le., no rgi YES D NO reduction in effectiveness)?
: 3. Does the proposed chan e constitute an emer enc action level scheme chan e? D YES IX! NO If questions 1 or 2 are answered NO, or question 3 answered YES, obtain prior NRG approval under provisions of 10 CFR 50.90. If questions 1 and 2 are c1nswered YES, and question 3 answered NO, implement applicable change rocess es. Part VI. Signatures:
Jacob Garcia Preparer Name (Print) (JFG EP109)
* _ o t fl1 G-r&A Reviewer Name (Print) (JFG EP109) Electronic Form EP-102-2, Rev. 4, Page 1 of 1 I 111 I I I l 1 . i 
{"" \ ( "*-PLANNING STANDARD 8 TEMPLATE -EMERGENCY FACILITIES AND EQUIPMENT Change information highlighted in yellow for applicable situation.
Consider NRC finding examples in INSPECTION MANUAL CHAPTER 0609, APPENDIX B (9/22(15) when performing evaluation.
Background and Scope: E2018-04-13-01 Attachment EP-00-006 Rev 6 changes: 1. Attachment E, changed AC/P to AP/C {Dl-2015-29572)
: 2. Attachment X, changed Bloomsburg Servlce Center to Susquehanna Environmental Lab (AR-2016-08585)
: 3. Attachment H, changed note 1 from Located in the HP Instrument Office to Located at Unit 2 HP Control Point, removed note 2 and changed note 3 to be note 2 {AR-2016-05912), changed protective gloves to disposable gloves, changed Tape, roll to Masking Tape, replaced portable frisker with probe to be portable frisker and probe, changed Sets of Anti-Contamination Clothing to Anti-Contamination Clothing {Coveralls, shoe covers, hoods) 4. 5. 6. 7. 8. Updated DS001 through DS006 to be DS003 through DS006 in Attachments P, Q and U. Added SAG-1/2 to replace DS001 and DS002. Removed Attachment CC, Quarterly ERMS Checks (DPA-02-Dl-2017-15922)
Attachment H, changed Survey Instrument Check Source-to Gamma Survey Meter Check Source, removed the spare frisker cable Attachment J, Changed PC's to be more specific in quantity; 1 case of coveralls is now 12, Plastic and Cotton Gloves are now 24, Shoe Covers and Hoods are now 12 Attachment T, removed Electronic Dosimetry PDA and Spare batteries, removed frisker 110v power cord, changed plastic bags sizes to be just plastic bags count 100, changed Portable Filters to be Particulate Filters 9. Attachment C, changed plastic bags sizes to be just plastic bags count 100, removed frisker 11 Ov power cord, changed Portable Filters to be Particulate Filters 10. Attachment I, Changed Floor covering Material to Herculite and updated count to be as sufficient, added Shoe Covers with a count of 4 11. Attachment K, changed NDAP-QA-0672-2 Forms to be entire procedure 1 copy, added a copy of the entire procedures HP-TP-510 NDAP-QA-0627 SP-OQ'.-308, updated PC clothing to be 6 (Goveralls, Shoe Covers, Hoods) and gloves to be 12 pair, removed box from paper towels (now paper towels 3 rolls) , removed Spare frisker probe and cable 12. Attachment G, removed SP-00-308-1, NDAP-QA-0627-2 and SP-00-308 Forms, removed second frisker, removed colors from hercultite, removed 2" from masking tape 13. Attachment F, removed SP-00-308-1, NDAP-QA-0627-2 and SP-00-308 Forms, removed second frisker, removed colors from hercultite, removed 2" from masking tape Page 1 of 7 c..* .... * ( \. ( \ .. 14. Removed C batteries throughout the procedure 15.-Attachment D, removed spare frisker power cord Attachment W, removed procedure counts (example 2 each after the procedure number is now blank) Items 1, 2, and *3 are editorial.
Item 4 is due to DS001 and DS002 Damage Support Boards that were replaced by the SAG-1/2 boards respectively and is an administrative change. Item 5 was to align procedure with recent EPlan Rev 61 which removed ERMS (reference eval E2017-07-03-01}. . Item 6: changing the name of Survey Instrument Check Source to Gamma Survey Meter Check is editorial; removing the spare frisker cable does not impact the ability of the frisker and is an editorial change. . Item 7 is being more specific on quantifies for P~otective Clothing and is an administrative change. Item 8: electronic dosimetry PDA and spare batteries are not required -6 electronic dosimetry will remain for dose*tracking; removing friskers 110v power cord does not impact frisker relia.bility and is an administrative change; changing specific plastic bag sizes to just be plastic bags count 100 still ensures plastic bags are available and is an administrative change; changing portable filters to glass fiber filters is an editorial change. Item 9: changing specific plastic bag sizes to just be plastic bags count 100 still ensures plastic bags are available and is an administrative change; changing Portable Filters to be Particulate Filters is an editorial change. Item 1 O: changing floor covering material to Herculite is an editorial change, changing the amountto as sufficient from 1 set is an administrative change. Adding Shoe Covers with *a count of 4 is an administrative change; changing Portable Filters to be Particulate Filters is an editorial change.
* Item 11: changing NDAP-QA-0672-2 Forms to be entire procedure 1 copy is an administrative change; adding a copy of the entire procedures HP-TP-510 NDAP-QA-0627 SP-00-308 is an administrative change; updating PC clothing/glove count is an administrative change; removing box from paper towels (now paper towels 3 rolls) is an administrative change; removing Spare frisker probe and cable is an administrative change. Items 12&13: removing SP-00-308~1, NDAP~QA-0627-2 and SP-00-308 Forms is an administrative change; removing second frisker still ensures one frisker is available and is an administrative change, removing specific colors from Herculite still ensures Herculite is available and is an administrative change; removing 2" from masking tape still ensures masking tape is available and is an administrative change. Item 14: is an administrative change, no equipment uses C batteries Item 15: removing spare frisker power cord is an administrative change
* Page 2of 7 I I Item 16: removing specific procedure counts still ensures that at least one copy of the procedure is available and is an administrative change. Items 3 and 6 -16 are the result of RP input. RP provided input for these changes and that work group is most knowledgeable with respect to the equipment needed for response to a radiological emergency.
Changes to the Emergency Plan Rev 61 will also need to occur to align with these changes above. See attached mark up for the EPlan changes. AR-2018-04987 generatedto make this administrative changes next EPlan revision.
* Part JI. Evaluation of the Proposed Change for Compliance with the requirements of 10 CFR 50.47(b) ahd 10 CFR 50 Appendix E: Evaluation of 10CFR50.47(b) requirements associated with Emergency Planning Standard [81:
* 1 O CFR 5Q.47(b)(8)
-Adequate emergency facilities and equipment to support the emergency response are provided and maintained.
Items 1-16 still ensure that adequate emergency facilities and equipment will still be provided and maintained.
Friskers will still be available and calibrated, Protective Clothing will still be available, electronic dosimetry wifl still be available, plastic bags are still available for samples and floor covering material (Herculite) is still available.
The changes to the EPlan are administrative in nature and still ensure that adequate emergency facilities and equipment will still be provided and maintained.
Friskers will still be available and calibrated,
* Protective Clothing will still be available, electronic dosimetry will still be available, plastic bags are still available for samples and floor covering material (Herculite) is still available.
Evaluation of Sections JV.E. 1-4, IV.E.B, and JV. G of 1 OCFR50 Appendix E requirements associated with Emergency Plannlng Standard [81:
* JV.E.1-4 Adequate provisions shall be made and described for emergency facilities and equipment, including:
: 1. Equipment at the site for personnel monitoring;
: 2. Equipment for determining the magnitude of and for continuously assessing the impact of the release of radioactive materials to the environment;
: 3. Facilities and supplies at the site for decontamination of on site individuals;
: 4. Facilities and medical supplies at the site for appropriate emergency first aid treatment.
: a. (0 A licensee onsite technical support center and an emerge(Jcy operations facility from which effective
,, direction can be given and effective control can be exercised during an emergency; (ii) For nuclear power reactor licensees, a licensee onsite operational support center; b. For a nuclear power reactor licensee's emergency operations facility re_quired by paragraph
: 8. a of this section, either a facility located between 10 miles and 25 miles of the nuclear power reactor site(s), or a Page 3 of 7 
,, \ { '(. primary facility located less than 10 miles from the nuclear power reactor site(s) and a backup facility located between 10 miles and 25 miles of the nuclear power reactor site(s). An emergency operations facility may serve more than one nuclear power reactor site. A licensee desiring to locate an emergency operations facility more than 25 miles from a nuclear power reactor site shaJ/ request prior Commission approval by submitting an application for an amendment to its license. For an emergency operations facility located more than 25 miles from a nuclear power reactor {lite, provisions must be made for locating NRG and offsite responders closer to the nuclear power reactor site so that NRG and offsite responders can interact face-to-face with emergency response personnel entering and leaving the nuclear power reactor site. Provisions for locating NRG and offsite responders closer to a nuclear power reactor site that is more than 25 miles from the emergency operations facility must include the following:
(1) Space for members of an NRG site team and Federal, State, and local responders; (2) Additional space for conducting briefings with emergency response personnel; (3) Communication with other licensee and offsite emergency response facilities; (4) Access to plant data and radiological information; and (5) Access to copying equipment and office supplies;
: c. By June 20, 2012, for a nuclear power reactor licensee's emergency operations facility required by paragraph 8.a of this section, a facility having the following capabilities:
(1) The capability for obtaining and displaying plant data and radiological in.formation for each reactor at a nuclear power reactor site and for each nuclear power reactor site that the facility serves; (2) The capability to analyze plant technical information and provide technical briefings on event conditions and prognosis to licensee and offsite response organizations for each reactor at a nuclear power reactor site and for each nuclear power reactor site that the_ facility serves; and (3) The capability to support response to events occurring simultaneously at more than one nuclear power reactor site if the emergency operations facility serves more than one site; and d. For nuclear power reactor licensees, an alternative facility (or facilities) that would be accessible even if the site is under threat of or experiencing hostile action, to function as a staging area for augmentation of emergency response staff and collectively having the following characteristics:
the capability for communication with the emergency operations facility, control room, and plant security; the capability to perform offsite notifications; and the capability for engineering assessment activities, including damage control team planning and preparation, for use when onsite emergency facilities cannot be safely accessed during hostile action. The requirements in this paragraph 8.d must be implemented no later than December 23, 2014, with the exception of the capability for staging emergency response organization personnel at the alternative facility (or facilities) and the capability for communications with the emergency operations facility, control room, and plant security, which must be implemented no later than June 20, 2012. e. A licensee shall not be subject to the requirements of paragraph
: 8. b of this section for an existing emergency operations facility approved as of December 23, 2011; Provisions to be employed to ensure that the emergency plan, its implementing procedures, and emergency equipment and supplies are maintained up to date shall be described.
Items 1-16-still ensure that adequate emergency facilities and equipment will still be provided and maintained.
Friskers will still be available and calibrated, Protective Clothing will still be available, electronic dosimetry will still be available, plastic bags are still available for samples and fl.oar covering material (Herculite) is still available.
Page 4 of 7 J 
,,-** (;: _____ . The changes to the EPlan are administrative in nature and still ensure that adequate emergency facilities and equipment will still be provided and maintained.
Friskers will still be available and calibrated, Protective Clothing will still be available, electronic dosimetry will still be available, plastic bags are still available for samples and flpor covering material (Herculite) is still available.
Part Ill. Evaluation of Emergency Planning Functions, Elements, and Commitments affected by the Proposed Change and the Licensing Basis for those Functions, Elements, and Commitments:
Emergencv Planning Functions
[81 from 1 OCFRSO. 54(q) Screening Form:
* Adequate facilities are maintained to support emergency response.
* Adequate equipment is maintained to support emergency response.
Items 1-16 still ensure that adequate emergency facilities and equipment will still be provided and maintained.
Friskers will still be available and calibrated, Protective Clothing will still be available, electronic dosimetry will still be available, plastic bags are still available for samples and floor covering material (Herculite) is still available.
The changes to the EPlan are administrative in nature and still ensure that adequate emergency facilities and equipment will still be provided and maintained.
Friskers will still be available and calibrated, Protective Clothing will still be available, electronic dosimetry will still be available, plastic bags are still available for samples and floor covering material (Herculite) is still available.
NUREG-0654 Section 1/.H Program Elements associated with the above Emergency Planning Standard [81:
* Each licensee shall ~stablish a Technical Support Center and an onsite operations support center (assembly area) in accordance with NUREG-0696, Revision 1.
* Each licensee shall establish an Emergency Operations Facility from which evaluation and* coordination of all licensee activities related to an emergency is to be carried out and from which the licensee shall provide information to Federal, State and local authorities responding to radiological emergencies in accordance with NUREG-0696, Revision 1.
* Each organization shall establish an emergency operations center for use in directing and controlling response functions.
* Each organization shall provide for timely activation and staffing of the facilities and centers described in the plan. *
* Each licensee shall identify and establish onsite monitoring systems that are to be used to initiate emergency measures in accordance with Appendix 1, as well as those to be used for conducting assessment.
The equipment shall include: a. geophysical phenomena monitors, (e.g., meteorological, hydrologic, seismic);
: b. radiological monitors, (e.g., process, area, emergency, effluent, wound and portable monitors and sampling equipment);
: c. process monitors, (e.g., reactor coolant system pressure and temperature, ontainment pressure and temperature, liquid levels, flow rates, status or lineup of equipment components);
and d. fire and combustion products detectors.
* Each licensee shall make provision to acquire data from or for emergency access to offsite monitoring and analysis equipment including:
: a. geophysical phenomena monitors, (e.g., meteorological, hydrologic, seismic);
: b. radiological monitors including ratemeters and sampling devices. Dosimetry shall be Page 5 of 7 
[-*. ~-.. ***-' / t. provided and shall meet, as a minimum, the NRG Radiological Assessment Branch Technical Position for the Environmental Radiological Mon! taring Program; and c. laboratory facilities, fixed or mobile.
* Each organization, where appropriate, shall provide for offsite radiological monitoring equipment in the vicinity of the nuclear facility.
* Each licensee shall provide meteorological instrumentation and procedures which satisfy the criteria in Appendix 2, and provisions to obtain representative current meteorological information from other sources.
* Each licensee shall provide for an onsite operations support center (assembly area) which shall have adequate capacity, and supplies, including, for example, respiratory protection, protective clothing, portable fighting, portable radiation monitoring equipment, cameras and communications equipment for personnel present in the assembly area.
* Each organization shall make provisions to inspect, inventory and operationally check emergency equ;pmentlinstruments at feast once each calendar quarter and after each use. There shall be sufficient reserves of instruments/equipment to replace those which are removed from emergency kits for calibration or repair. Calibration of equipment shall be at intervals recommended by the supplier of the equipment.
* Each plan shall, in an appendix, include identification of emergency kits by general category (protective equipment, communications equipment, radiological monitoring equipment and emergency supplies).
* Each organization shall establish a central point (preferably associated with the licensee's near-site Emergency Operations Facility), for the receipt and analysis of all field monitoring data and coordination of sample media.
* REFERENCE NSIRIDPR-JSG-01 SECTION I.D EMERGENCY RESPONSE ORGANIZATION AUGMENTATION AT ALTERNATE FACILITY (HOSTILE ACTION). Items 1-16 still ensure that adequate emergency facilities and equipment will still be provided and maintained.
Friskers will still be available and calibrated, Protective Clothing will still be available, electronic dosimetry will still be available, plastic bags are still available for samples and floor covering material (Herculite) is still available.
The changes to the EPlan are administrative in nature and still ensure that adequate emergency facilities and equipment will still be provided and maintained.
Friskers will still be available and calibrated, Protective Clothing will still be available, electronic dosimetry will still be available, plastic bags are still available for samples and floor covering material (Herculite) is still available.
Applicable sections of the Emergency Plan associated with NUREG-0654 Sections 11.H Program Elements:
: 1. Chapter 8, Sections 8.1.2.1, 8.1.1.2, 8.1.3 2. Chapter 8, Section 8.1.2.2 4. Chapter 6, Sections Phase I, Phase II, Phase Ill 5. Appendix D, Enclosures 3, 4, 5, 7 5.a. Appendix D, Enclosure 3 5.b. Appendix D, Enclosure 4 5.c. Appendix D, Enclosures 4, 7 5.d. Appendix D, Enclosure 7 6.a., b. Chapter 7, Section 7.~, 7.1.1 Page 6 of 7-6.c. Appendix C, Position Specific Instructions for:
* Chemistry Coordinator
* Field Team Director Table6.2 7. Appendix D, Enclosures.4, 5 8. Chapter 7, Section 7.1.1.1, Appendix D; Enclqsure 3 9. Chapter 8, Section 8.1.2 ;; 10. Chapter 9, Section 9.3 11. Appendix D ,, 12. Chapter 6, Sections 6.2.4f), 6.3.1.4f)
Part IV. Evaluation of the Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions*and Commitments:
There is no negative impact of the proposed change on the effectiveness of the Emergency Plan Functions for the reasons stated above. There is no negative impact of tl)e proposed change to commitments for the following reasons. Reg. Guide 1.219 Revision 1 section 4.8 was reviewed for examples of changes that could require prior NRG approval and none were found to be applicable.
* Per the g&#xb5;idance in EP-102 Attachments F and G, this change does not con~titute a sch~me change. The proposed change is not a reduction in effectiveness of the Emergency Plan and therefore does not
* require prior NRC approval.
Page 7 of 7 t It lJ. 1i ii I. I !l ir
* i! I ! ! I ! . 1 I ! ! I I ! I l i I I 11 !. ! ! !, ! 
( \ ~-.. ~. Emergency Plan, Rev. 61, Page 148 of 296 ENCLOSURE 1 TO APPENDIX D Typical Station Decontamination Area Equipment Decontamination Procedures Gottol'l Gloves Coveralls (Qispgsaele-}
Decontamination Soap Disposable Bath Towels ~,OJa.s.:,;c G1ov@-.J.,..cc,+.JrN, F. k ;.,.ser-lJ ns er Hand Brushes Ha11d eream Lotion Skin e1ear1e1 Masking Tape Paper Towels Shoe Covers .. Si;are Frisker eat;lle .~r-e--Ffisker.Probe~~~4,.b+(-*'
Spongej Typical Damage Control Equipment Storage Box Contents Amprobe Bars, Pry, Large Bars, Pry, Roliing Lead Black Wire, 1/4 lb. Rolls, 16 Gauge Box, Tool, 23" Bucket, 14 quart, Plastic Cable Cutters c1a*mps, C, Medium Clamps, C, Large Clamps, C, Small Electricians Pouch with Miscellaneous Hand Tools Enerpac, Rescue Unit Fla_shlight, 5 cell Hammer, Ball Peen, 16 oz. Hammer, Sledge, 1 O lb.
* Hammer, Sledge, 8 lb. Multimeter
* Nylon Rope, 100' coils, 3/4" Nylon Rope, 25' coils, 3/8" Nylon *Rope, 50' coils, 3/8" Nylon Rope, 50' coils, 3/4" Plastic Sheet, 20' X 20', Fire Retardant Pliers, Lineman Pliers, Water Pump . . Page 3 of 16 Plugs, Wood, 1" & ff' Plugs, Wooden Box, 1", 11/.i', 1%', 2", 2%", 3" .. Rubber, Roll 1/16" thick, 10' X 3' Screwdrivers, Large Standard Screwdrivers, Medium Standard Screwdrivers, Phillips, Large Screwdrivers, Phillips, Medium String, Ball Twine, Bale Wedges,Wooden Wrench, Adjustable, 12" Wrench, Adjustable, 8" Wrench, Allen Pac 3/16", 7/32", 1/4", 5/16", 3/8" Wrench, Allen Pac .050", 1/16", 5/64", 3/32", 7/64", 1/8", 9/64", 5/32", 3/16", 7/32" Wrench, Chain Wrench, Hex, #11 O Wrench, Hex, #17 Wrench, Hex, 24" Wrench, Pipe, 18" Wrench, Pipe, 14" I ! I' [ l 1! r II j I i i I . . J I' '. I 
/.,., .. \;:::-*:.*
*: _.( (" ' ~' .... , .... Emergency Plan, Rev. 61, Page 149 of 296 ENCLOSURE 2 TO APPENDIX D Typical Onsite Search and Rescue/First Aid, Ambulance, and Hospital Radiation Emergency Equipment and Supplies Onsite Search Rescue/First Aid: Adjustable Litter Basket Stretcher (Stokes) Fjrst Aid Team Initial Response Kit with Inventory Sheet Ambulance Kit: :fape ref!, l&deg;l181$IC;
'"'/I '1"4-p,E!.
Miss l?lastie Qa9s-W"'1i,~e \,&#xb5;~ I/~.,..,)
Plastic Gloves CcA-11,,n.
G-tc-,,-4 .S Hospital:
Dosimeter Charger Survey Meter Frisker with Probe Herculite
~its, emaR aRQ yeltei,11 Lead Container, high activity samples Page 4 of 16 Folding Litter Portable Oxygen-Demand Valve (size D tank With assorted airways, cannulas, and masks)
* Scoop Stretcher Trauma Kit Assorted Splinting Devices Plastie Sheetifls,'
B' X:zeL 11e_rcw1,'t-<e._ .Ph!soo Shoe Covers
* Portable Frisker and Probe Set-ufA11ti eo11ta1,ilna~
Ltt~ Oo"lrf-.5 ,~ *., Self Reading Dosimeters Set of Radiation Signs and Ribbon Stanchions/
p tit"' J Step-off Pad Thermoluminescent Dosimet~rs, *badge type Thermoluminescent Dosimeters, ring type Emergency Plan, Rev. 61, Page 157 of 296 2. Typical Radiological Monitoring Team Equipment
(. ~t~.s) Emergency Planning and Grid Coordinate Maps Stopwatch, tweezers, masking tape l.::rlli""1'l G\.. Survey Meter with current calibration Low Volume Air Sampler and Head Potassium Iodide Tablets Radioactive Material Stickers Particulate Filters/'t>ox-Silver Zeolite Cartridges Disposable Plastic Gloves Plastic sample bags and labels Flashlight
* $p4,.,e oti--t-lEll"i 0 t!J -i)'vf)a~*
~;A,'., ~n,.-J ,.,A t) -&elf~ *-,v*r T ..-, ,._v o-*v"' {,v11II~)
(/}IJ.V1 (Ud -#' i:;{7/tVJ
'r<"/ J:;,,i-/'lr 0-?7' ( \., .. 3. Typical Emergency Environmental Sample Kit Contents Assortment of Sampling Bags Flashlight Grid Coordinate Map Dosimeters Pliers ~f~@a~by Page 12 of 16 ~Plastic Gloves Sample Containers Sample Labels Scale Scissors Spare Batteries l ,, I ,. Emergency Plan, Rev. 61, Page 158 of 296 ENCLOSURE 6 TO APPENDIX D Typical Radiation Protection Van Radiation Emergency Monitoring Equipment Survey Meter with current calibration . Portable Frisker with probe Low Volume Air Sampler with head (AC powered) Low Volume Air Sampler with DC power plug ~13are Ffielrer Cable DC to AC Inverter VHF mobile radio Respirators Iodine Canister Potassium Iodide Tablets Sets of Anti-contamination Clothing f.), 7?"~ .. 1,ge Proteotive-gloves Calculator Eme1gu1ey PlaRl'lil'I&sect; f,i~ Check source Silver Zeolite cartridges Particulate Filters Tweezers S t>l!1/ ce... ~--, Ji,,,,-vtt7 ,viut; ~(,, Page 13 of 16 Stopwat~h
'.Fape /A4r,,~-:-
... y "Tt!i.,p(...
Surve~
Microfiber Wipes Smear Papers Plastic bags for samples Extension cord Work light Flashlight First Aid Kit Spare batteries S13are4Yoo&.foi;.Ai1 Oam~ler Safety Vests C Emergency Plan, Rev. 61, Page 160 of 296 ENCLOSURE 8 TO APPENDIX D Typical Emergency Equipment for Initial Incident Response Portable frisker with probe Low volume Air Sample with Head R-Veh 1me l\ir s~u'l'IJ*Elf-&#xa5;.!itt;i
* 1 lead Survey Meter eparevmsk..ei:..eaele ar1d p1 obe Particulate t+~rwr *r*\ ru1..,.:5 SilvetZeolite Cartridges Spare Batteries a1*1.ftra@s.i Portable Worklight
-&#xa3;xteRSi0fl Csf'Et-Self Reading Dosimetry' Potassium Iodine Tablets Anti-contamination Clothing Full face Respirator Iodine Filter Canisters SCBA Equipment .
* Emergency Plan Emergency Plan Position Specific Instructions Emergency Planning' Map with offsite sampling locations Onsite Monitoring Locations Map
* Fil st Ai El Kit -Keys'.'te
* RadtatienP1 oleetiol'l-\hm tll'lo~eRey Pla!'l l<eys * . Food and potable water adequqte to support 10 people for 5 days. ~ailael&-at ooc al%! at RP eo11trel1}'0int te*tAe* RCA.:"' , Typical Technical Support Center Equipment Plant Technical Specifications*
Operating Procedures Manual Emergency Operating Procedure Manual Final. Safety Analysis Report EP and EP-PSs Safety Procedure Manual . Offsite Dose Calculation Manual Plant as built drawings Emergency Phone Directory*
Copy Machine and Telecopier Page 15 of 16 Attachment B, 1 OCFR50.54q Evaluation Checklist Evaluation Number: E2018-04~26-01 Screen Number: Snot applicable Part I. Description of Proposed Change (Copy applicable information from 50.54(q) screen form Part I or
* attach a mark-up of the existing text with the proposed change can be used as an alternative):
See Attachment Part II. Evaluation of the Proposed Change for Compliance with the requirements of 1 O CFR 50.47(b) and 10 CFR 50 Appendix E: See Attachment Part Ill. Evaluation of Emergency Planning Functions, Elements, and Commitments affected by the Proposed Change and the Licensing Basis for those Functions, Elements, and Commitments:
See Attachment Part N. Evaluation of the Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:
* See Attachment Part V. Evaluation Conclus.ion
~YES0NO 2. Does the proposed change maintain the. effectiveness of the Emergency Plan (i.e., no YES D NO reduction in effectiveness)?
: 3. 0YES~NO If questions 1 or 2 are answered NO, or question 3 answered YES, obtain prior NRC approval under provisions of 1 o CFR 50. 90. If questions 1 and 2 are answered YES, and question 3 answered NO, implement applicable change rocess es. , Part VI. Signatures:
Jacob Garcia Preparer Name (Print) (JFG EP109) Electronic Form EP-102-2, Rev. 4, Page 1 of 1 ! ..
PLANNING STANDARD 5 TEMPLATE -EMERGENCY NOTIFICATIONS E2018-04-26-01 Background and Scope: Remove the redundant Alert Notification System (siren) control station located at SSES. EPlan Rev 61 8.5.4 states "A redundant control station located at SSES and the EOF has full radio control .capabilities, and will be used for the purpose of testing and maintenance activities." It will be changed to read "A redundant control station, lqcated at the EDF, has full radio control capabilities,*
and will be used for the purpose of testing and maintenance activities.
EPlan History Rev. 6 -NRC. SER version 2 control stations, 1 at Luzerne and 1 at Columbia No redundant testing and maintenance stations From Rev 6 Section 6.6 Public Notification System "Activation of the Siren System is via radio control from Luzerne County Civil Defense and Columbia County Emergency Management Agency EOC. Activation by either County EOG will a_ctivate t~e entire siren system." . . Rev. 51 -No prior NRC Approval -2 control stations, 1 at Luzerne and 1 at Columbia 2 redundant control stations for testing and maintenance at SSES and SFC From Rev 51 Section. 8.5.4 Public.Notification System "Activation of the PNS is via radio control 'from . either the LC EMA Emergency Operations Center or CCDPS Emergency Operations Center. Redundant control stations located at PPL Susqueh.=lm:1a LLC and the System Facility Center (SFC) have full capabilities and will be used for the purpose of testing and maintenance activities."
* Rev. 58 -No prior NRC Approval . 2 control stations, 1 at Luzerne and 1 at Columbia 2 redundant control station~ for testing and maintenance at SSES and EOF
* From Rev 58.Section
 
====8.5.4 Public====
Notification System "Actiyation of the ANS is via radio control from either the LCEMA Emergency Operations Center or CCEMA Emergency Operations Center. A back-up satellite system can also activate the sirens from LCEMA or CCEMA. A redunda'nt control st;3tioh located at SSES and the EDF has full-radio control capabilities, and will be used for the purpose of. testing and maintenance activities." Part n. Evaluation of the Proposed Change for Compliance with the requirements of 1 o CFR 50.47(b) and 10 CFR 50 Appendix E: Evaluation of 10CFR50.47(b) requirements associated with Emergency Planning Standard [5l"
* 10 CFR 50.47(b)(5)
-1'Procedureshave been established for notification, by the licensee; of State and local response organizations and for notification of emergency personnel by all organizations; the content of initial and folfowup messages to response organizations and the* public has been established; and means to provide early notification and clear instructio_n to the populace within the plume exposure pathway Emergency PlanningZone have been established." There is lio change to activation of the siren system. Luzerne and Columbia Counties will continue to have their own control stations to activate the siren system to provide early notification and clear instruction to the populace within the plume exposure pathway Emergency Planning Zone.
Evaluation of Sections IV.D. 1 and /V.D.3 of 1 OCFR50 Appendix E requirements associated with Emergency Planning Standard f 51: 1. Administrative and physical means for notifying local, State, and Federal officials and agencies and agreements reached with these officials and agencies for the prompt notification of the public and for public evacuation or other protecilve measures, should they become necessary, shall be described.
Th.is description shall include identification of the appropriate officials, by title and agency, of the State and focal government agencies within the EPZs.
* 3. A licensee shall have the capability to notify responsible State and local governmental agencies within 15 minutes after declaring an emergency.
The licensee shall demonstrate that the appropriate governmental authorities have the capability to make a public alerting and notification decision promptly on being informed by the licensee of an emergency condition.
Prior to initial operation greater than 5 percent of rated thermal power of the first reactor at a site, each nuclear power reactor licensee shall demonstrate that administrative and physical ineans have been established for alerting-and providing prompt instructions to the public within the plume
* exposure pathway EPZ. The design objective of the prompt public alert and notification system shall be to have the capability to essentially complete the initial alerting and initiate notification of the public within the plume exposure pathway EPZ within about 15 minutes. The use of this
* alerting and notification capabl1ity will range from immediate alerting and notification of the public (within 15 minutes of the time that State and local officials are notified that a situation exists requiring urgent action) to the more likely events where there is substantial time available for the appropriate governmental authorities to make a judgment whether or not to activate the public alert and notification system . .The alerting and notification capability shall additionally include administrative and physical means for a backup method of public alerting and notification capable of being used in the event the primary method c,f alerting and notification is unavailable during_ an emergency to alert or notify all or portions of the plume exposure pathway EPZ population.
The backup method shall have the capability to alert and.notify the public within the plume exp,asure pathway EPZ, but does not need to meet the 15~minute design objective for the primary prompt public alert and notification system. When there is a decision to activate the alert and notification
* system, the appropriate goveminehtal authorities will determine whether to activate the entire alert and notification system simultaneously or in a graduated or staged manner. The responsibility for activating such a public alert and notificailon system shall remain with the appropriate governmental authorities There is no change to activation of the siren system. Luzerne and Columbia Counties will continue to have their own control stations to activate the siren system. No change to the backup method of rotJte , al$rting for sectors that may experience a siren failure. Part Ill. Evaluation of Emergency Planning Functions, Elements, and Commitments affected by the Proposed Change and the Licensing Basis* for those Functions, Elements, and Commitments:
Emergency Planning Functions
[5Tfrom 10CFR50.54(q)
Screening Form:.
* Procedures for notification of State and local governmental agencies are capable of alerting them of the declared emergency within 15 minutes after declaration of an emergency and providing follow-up notifications.
* Administrative and physical means have been established for alerting and providing prompt instructions to the public within the plume exposure pathway.
* The public ANS meets the design requirements of FEMA-REP-10, "Guide for Evaluation of Alert and Notification Systems for Nuclear Power Plants" (Ref. 16), or is compliant with the licensee's FEMA-approved ANS design report and supporting FEMA approval letter.
There is no change to activation of the siren system. Luzerne and Columbia Counties will continue to have their own control stations to activate the siren system. The FEMA Approved Design report, dated Nov 7 2008, was reviewed.
There is no nienflon of specific control stations.
The FEMA Satellite Enhancement Approval dated Feb 3 2011 was also reviewed.
There is no mention of specific control stations.
NUREG"0654 Section 11.E Program Elements and Appendix 3 assodated with the above Emergency Planning Standard [51: *
* Each organization shall establish procedures which describe mutually agreeable bases for notification or response organizations consistent with the emergency classification and action level scheme set forth in Appendix 1. These procedures shall.include means for verification-of messages.
The specific d~tails of verification need not be included in the plan.
* Each organization shaff. establish procedures for alerting, notifying and mobilizing emergency .response personnel.
* The licensee in conjunction with State and local organizations shall establish the content of the initial emergency messages to be sent .from the plant. These measures shall contain information about the .class of emergency, whether a release is taking place, potentially affected populations and areas, and whether protective actions.may be necessary.
* Each licensee shall make provisions for follow up messages from the facility to offsite authorities which shall contain the following inform~tion ifit is known and appropriate:
o Location of incident and name and telephone number (or communications channel identification) of caller;
* o Date/time of incident; o Class of emergency; o Type of actual or projected release (airborne, waterborn.e, surface spilO, and estimated duration/impact times; * *. . o .Estimate of quantity of radioactive material released or being released and the points and heights of releases;*
o Chemical and physical form of released material, including estimates*
of the relative quantities and concentrations of noble gases, iodines and particulates; o Meteorological conditions at appropriate levels (wind speed, direction (to and from), indicator of stability, precipitation, if any); *
* o Actual or projected dose rates at site boundary; projected integrated dose at site boundary; . o Projected dose rates and integrated dose at the projected peak and at 2, 5, and 10 miles, including sector(s) affected;
* o Estimate of any surface radioactive contamination in plant, onsite, or offsite; o Licensee emergency response actions underway; o Recommended emergency actions, including protective measures; o Request for any needed offsite support by offsite organizations; and o Prognosis for worsening or termination of event based on plant information
* Each organization shall establish administrative and physical means, and the time required for notifying and providing prompt instructions to the public within the plume exposure pathway Emergency Planning Zone (See Appendix 3 of NUREG 0654.) ft shall be the licensee's responsibility to demonstrate that such means exist, regardless of who implements this requirement.
It shall be the responsibility of the State and local governments to activate such a system.
* Each organization shall provide written messages intended for the public, consistent with the licensee's classification scheme.' In particular, draft messages to the public giving instructions with regards to specific protective actions to be taken by occupants of affected areas shall be prepared and included as part of the State and local plans. Such messages should include the appropriate aspects of sheltering, ad hoc, respiratory protection, e.g., handkerchief over mouth, thyroid blocking or evacuation.
The role of the licensee is to provide supporting information for the messages.
For ad hoc respiratory protection see "Respiratory Protective devices Manual" American Industrial Hygiene Association, 1963 pp. 123-126.
* REFERENCE NSIR!DPR-ISG-01 SECTION JV.J BACKUP MEANS FOR ALERT AND NOT/FICA TIONS SYSTEMS There is no change to activation of the siren system. Luzerne and Columbia Counties will continue to. have their own control stations to activate the siren system. No change to backup method of route alerting requirements in NSAI/DPR-ISG-01 Section IV.J are not affected.
The FEMA-approved ANS design report is associated with the above Emergency Planning Function [fil;. Because the performance of an ANS is an offsite concern, FEMA has the primary responsibility and authority for evaluating the design of an ANS, including primary and backup means. If the licensee has assumed responsibility for the installation and maintenance of the ANS on behalf of the State or local government, the licensee will have prepared a site-specific ANS design report. The State would submit this report to FEMA for its review. The ANS design report defines the design of the ANS, including the alerting system (e.g., sirens, tone alert radio, and route alert) and the notification system. The ANS design report identifies commitments for testing and maintenance.
The NRG considers the approved ANS design report to be part of the facility's licensing basis because it establishes the basis of the NRC's determination that the licensee has complied with Section IV.D.3 of Appendix E to 10 CFR Part 50. Changes to the licensee's commitments documented in the approved ANS design report are evaluated against the criteria of 44 CFR 350.14, "Amendments to State Plans." If warranted, the responsible State official must submit the proposed changes to FEMA for review and approval in accordance with 44 CFR 350.14. There is no change to activation of the.siren system. Luzerne and Columbia Counties will continue to have their own control stations to activate the siren system. The FEMA Approved Design report, dated Nov 7 2008, was reviewed.
There is no mention of specific control stations.
The FEMA Satellite Enhancement Approval dated Feb 3 2011 was also reviewed.
There is no mention of specific control stations.
Local EP Procedures were reviewed.
EP-108, EP-109, and EP-110. There is no mention of the on-site control station. Applicable sections of the Emergency Plan associated with NUREG-0654 Section 11.E Program Elements: 
: 1. Chapter 6, Figure 6. 7 Appendix C, Position Specific Instructions for:
* Control Room Emergency Plan Communicator
* TSC Emergency Plan Communicator
* EOF Communicator
* Radiation Protection Coordinator
* Technical Support Coordinator
' Recovery Manager *
* Dose Assessment Supervisor
: 2. Appendix C, Position Specific Instructions for:
* Emergency Director
* Control Room Emergency Plan Communicator
* TSC Emergency Plan Communicator
* Security Coordinator
: 3. Appendix C, Position Specific Instructions for:
* Control Room Emergency Plan Communicator
* TSC Emergency Plan Communicator
* EOF Communicator 4.a., b., c., k., n. Appendix C, Position Specific Instructions for:
* Control Room Emergency Plan Communicator
* TSC Emergency Plan Communicator
* EOF Communicator 4.d., e., f., g., h., i., j., I. Appendix C, Position Specific Instructions for:
* Radiation Protection Coordinator
* Dose Assessment Supervisor 4.m. Appendix C, Position Specific Instructions for:
* Control Room Emergency Plan Communicator
* TSC Emergency Plan Communicator
* EOF Communicator
: 6. Chapter 6, Sections 6. 2. 1, 6. 3.1. 1 Chapter 7, Sections 7 .1.1, 7 .3.2 Chapter 8, Section 8.5.4 7. Chapter 6, Sections 6.2, 6.2.1, 6.2.3, 6.3.1.1, 6.3.1.5 Chapter 7, Section 7.3.2, Table 7.3 EPlan Rev 61 8.5.4 states "A redundant control station located at SSES and the EOF has full radio control capabilities, and will be used for the purpose of testing and maintenance activities." It will be changed to read "A redundant control station, located at the EOF, has full radio control capabilities, and will be used for the purpose of testing and maintenance activities.
Part IV. Evaluation of the Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions and Commitments:
There is no negative impact of the proposed change on the effectiveness of the Emergency Plan Functions for the reasons stated above. There is no negative impact of the proposed change to commitments for the reasons that all required functions stated in the NRG SER Version Rev 6 are maintained.
Reg. Guide 1.219 Revision 1 section 4.5 was reviewed for examples of changes that could require prior NRC approval and none were found to be applicable.
Per the guidance in EP-102 Attachments F and G, this change does not constitute a scheme change. The proposed change is not a reduction in effectiveness of the Emergency Plan and therefore does not require prior NRC approval.
Attachment A, 10CFR50.54q Screening Form Screening Number: S2018-10-02-01 I Part I. Description of Activity Being Reviewed (event or action, or series of actions that may result in a change to the Emergency Plan or affect the implementation of the Emergency Plan). Provide the existing text and the revised text (attaching a mark-up of the existing text with proposed change can be used as an alternative):
The following changes were considered for the EP-PS-001, Rev 16 procedure:
: 1) Performed following changes to EP-PS-001-3 form: a. Added Note before the approval line per AR-2018-12575.
: b. Replaced "or 0.4 rem (TEDE) for a woman who has declared that she is pregnant''
with "Women capable of reproduction should not take part in these actions" in note 1 per AR-2016-27032.
: c. Deleted everything after "4 rem TEDE" in note 2 and replaced with "Women capable of reproduction should not take part in these actions" per AR-2016-27032.
: 2) Performed following changes to EP-PS-001-11 form per AR-2018-10701:
: a. Removed items 4 and 8 (82016-10-18-01
/ E2016-10-18-01 and 82014-09-29-01
/ E2014-09-29-01, respectively).
* b. Replaced "Chronology of' with "EOF Significant" in item 9 (current item 7). (S2013-01-14-01)
: c. Added FNR to item 6 (current item 5) and replaced ENR with FNR in item ?(current item 6). (S2016-10 / E2016-10-18-01)
: 3) Added "Priority" field to EP-PS-001-14 forr;n per DPA-06-Dl-2017-20364.
: 4) Added Scanning and Emailing instructions under step 1 in "ENR/FOLLOWUP NOTIFICATION REPORT TRANSMITTAL INSTRUCTIONS" in EP-PS-001-34 per AR-2018-03176.
: 5) Performed following changes to EP-PS-0()1-41 form: a. C.orrected steps to obtain VMLD2 computer point trends in step A.4. (technical review comment) b. Added "A." in note below "Plant Computer Meteorological Data Point Identifiers" table AR 2018 11831. 6) Deleted "RMS" from EP-PS-001-42 form per AR-2018-10704. (E2017-07-03-01)
: 7) Performed following changes to EP-PS-001-45 form: a. Added "not" before "permissible" in step 1.1.2 and deleted everything after "permissible" per AR-2016-27032). b. Removed "such as shellfish" from step 3.1.12.b and c. c. Moved* note within Step 4 in Emergency Exposure Extensions section before step 4. Added examples after second and third sentence in note per AR-2018-12575.
: d. Removed first row of the table in step 4 in Emergency Exposure Extensions section per AR-2016-27032
: e. Removed "or RM" from last row of the table in step 4 in Emergency Exposure Extensions section per AR-2018-12575.
: f. Removed "or 0.4 rem (TEDE) for a woman who has declared that she is pregnant" and "(and, for the woman who has declared that she is pregnant, risks to the embryo/fetus)" in step 5 in Emergency Exposure Extensions section per AR-2016-27032.
: g. Removed "(0.4 rem to declared pregnant woman)" from note before step 1.3.2 in RADIATION PROTECTION AND ALARA CONSIDERATIONS DURING EMERGENCIES section per AR-2016-27032.
Electronic Form EP-102-1, Rev. 4, Page 1 of 5 Part II. Activity a Change per Section 3.1.3? DYES IZI NO Does the activity constitute a change per definition 3.1.3 -An action that Continue to next part 10 CFR 50.54(q) results in modification or addition to, or removal from the SSES Evaluation is NOT Emergency Plan, OR the resources, capabilities and methods identified in required.
Enter justification and the plan? complete Part VI. Justification:
EP-PS-001 procedures provides forms and supplementary instructions for the On-shift staff and Emergency Response Organization (ERO) personnel.
The Emergency Plan Position Specific (EP-PS) procedures provide guidance on how Station personnel implement specific actions described in SSES Emergency Plan Rev 61 (E-Plan) Sections 6 and 7. All EP-PS procedures refer to one or multiple forms or special instructions in EP-PS-001.
Changes 1.a, 7.c and 7.e -E-Plan sections 6.2.1.1 and 6.2.5.1 state that Emergency Director (ED) and Radiation Protection Coordinator (RPG) approve dose extensions.
Section 6.3. 1.1 for the Recovery Manager (RM) does not list a responsibility for approving dose extensions.
The note added before the approval lines on forms EP-PS-001-3 (Emergency Exposure Extension Request) states that ED/RPG continue to approve in-plant (INDIA) team dose extensions even after EOF took over the management of the emergency since I NOIA teams always remain under command and control of the TSC, while Recovery Manger (RM) and Dose Assessment Supervisors (DASU) in the EOF approve dose extension only on the team members (ex. field monitoring teams) that are under their command and control. The duties of the ED and RM mirror each other with respect to classification, notification and protective actions (PARs and Kl to emergency workers).
This change allows the EOF operation (RM/DASU) to mirror TSC operation (ED/RPC) for dose exposure extension for team members under their command and control for an improved efficiency in obtaining the dose extensions to allow emergency workers to better protect the health and safety of the public. Dose extensions
> 25000 mrem TEDE are not plausible for field monitoring teams since they are moved out of very high dose fields and therefore RM approval is not needed in this situation. (change 7.e). AR-2018-13835 was generated to align the E-Plan with this operation and add instructions in sections 6.3.1.1 and 6.3.1.4 in the Emergency Plan for the Recovery Manager and Dose Assessment Supervisor to process and approve dose extensions for field monitoring teams, if necessary and if EOF is in control of emergency.
Electronic Form EP-102-1.
Rev. 4. Page 2 of 5 Changes 1.b, 1.c and 7.a, 7.d, 7.f and 7.g-These sections had been aligned with NDAP-QA-0625 on limits of occupational exposure for pregnant women. While NDAP-QA-0625 refers to occupational exposure, the E-Plan is slient about this limit; it just mentions in a Note at the bottom of the first Table in Table 7 .2 that the Emergency limits apply to "non-pregnant adults". E-Plan Table 7.2, Emergency Exposure Criteria, states that "women capable of reproduction should not take part in these actions".
Therefore, changes align procedure with the E-Plan statement and exclude women capable of reproduction from consideration for dose extensions.
Changes 2 and 6 -aligned the procedure with previously analyzed changes and added additional details on the procedural step. Changes 3, 4 and 5.a -are enhancements*that do not modify the technical content of the procedure and change 5.b is editorial.
Change 7.b -aligned the procedure with the latest FDA guidance that "A seafood or shellfish allergy does not necessarily mean that you are allergic or hypersensitive to iodine." (Question 7 in Frequently Asked Questions on Potassium Iodide (Kl) on httg_s://www.fda.gov/drugs/emergencyg_reg_aredness/bioterrorismanddrugg reparedness/ucm072265.htm; Kl in Radiation Emergencies-Questions and Answers Guidance for Industry (2002) and Potassium Iodide as a Thyroid Blocking Agent in Radiation Emergencies Guidance (2001)). Therefore, this change eliminated shellfish as a potential allergen for Kl administration.
Changes proposed in Part I were either analyzed previously and screened out or found not to decrease the effectiveness of the E-Plan, and thus are alignment changes, are editorial in nature or enhanced procedures by adding additional directions that do not change the technical content or challenge any commitments in the E-Plan. Therefore, changes in Revision 16 to EP-PS-001 did not constitute a change per definition 3.1.3 of EP-102 procedure and did not affect any of the requirements specified in the E-Plan. Thus, the changes were implemented and the procedure was up-revved to Rev 17. Part Ill. Activity Previously Reviewed?
DYES ONO Is this activity fully bounded by an NRC approved 10 CFR 50.90 submittal 10 CFR 50.54(q) Continue to next part or Alert and Notification System Design Report (44 CFR 350.14)? Evaluation is NOT required.
Enter If YES, identify bounding source document number/approval reference Justification and and ensure the basis for concluding the source document fully bounds the complete Part VJ. proposed change is documented below: Justification:
D Bounding document attached (optional)
Electronic Form EP-102-1, Rev. 4, Page 3 of 5 Part IV. Editorial Change DYES ONO Is this activity an editorial or typographical change such as formatting, paragraph 10 CFR 50.54(q) Continue to numbering, spelling, or punctuation that does not change intent per definition 3.1.4? Evaluation is NOT next part required.
Enter justification and complete Part VI. Justification:
Part V. Emergency Planning Element/Function Screen (Associated 10 CFR 50.47(b) planning standard function identified in brackets.)
If this activity affects any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II, then olace a check in the aoorooriate box. 1. Responsibility for emergency response is assigned.
[1] D 2. The response organization has the staff to respond and to augment staff on a continuing basis (24/7 D staffini:i) in accordance with the Emeri:iency Plan. [11 3. The process ensures that on shift emergency response responsibilities are staffed and assigned.
[2] D 4. The process for timely augmentation of on-shift staff is established and maintained.
[2] D 5. Arrangements for requesting and using off site assistance have been made. [3] D 6. State and local staff can .be accommodated at the EOF in accordance with the Emergency Plan. [3] D 7. A standard scheme of emergency classification and action levels is in use. [4] (RSPS) D 8. Procedures for notification of State and local governmental agencies are capable of alerting them of the declared emergency within 15 minutes after declaration of an emergency and providing follow-up D notifications.
f51 (RSPS) 9. Administrative and physical means have been established for alerting and providing prompt D instructions to the public within the plume exposure pathway, f51 (RSPS) 10. The public ANS meets the design requirements of FEMA-REP-1 o, Guide for Evaluation of Alert and Notification Systems for Nuclear Power Plants, or complies with the licensee's FEMA-approved ANS D desian report and sunnortino FEMA approval letter. f51 (RSPS) 11. Systems are established for prompt communication among principal emergency response D orcianizations.
T61 12. Systems are established for prompt communication to emergency response personnel.
[6] D 13. Emergency preparedness information is made available to the public on a periodic basis within the D olume exposure pathway Emeroencv Plannini:i Zone (EPZ}. [71 14. Coordinated dissemination of public information during emergencies is established.
[7] D 15. Adequate facilities are maintained to support .emergency response.
[8] D 1 \3. Adequate equipment is maintained to support emergency response.
[8] D 17. Methods, systems, and equipment for assessment of radioactive releases are in use. [9) (RSPS) D 18. A range of public PARs is available for implementation during emergencies.
[1 OJ (RSPS) D 19. Evacuation time estimates for the population located in the plume exposure pathway EPZ are available to support the formulation of PARs and have been provided to State and local governmental D authorities.
r101 (RSPS) 20. Kl is available for implementation as a protective action recommendation in those jurisdictions that D chose to provide Kl to the public f101 21. A range of protective actions is available for plant emergency workers during emergencies, including D those for hostile action events.[1 Ol 22. The resources for controlling radiological exposures for emergency workers are established.
[11] D 23. Arrangements are made for medical services for contaminated, injured individuals.
[12] D 24. Plans for recovery and reentry are developed.
[13J D 25. A drill and exercise program (including radiological, medical, health physics and other program areas) D is established.
[141 26. Drills, exercises, & training evolutions that provide performance opportunities to develop, maintain, & D demonstrate kev skills are assessed via a formal critique process in order to identify weaknesses.
[141 27. Identified weaknesses are corrected.
[14] D 28. Training is provided to emergency responders.
[15J D 29. Responsibility for Emergency Plan development and review is established.
[16] D Electronic Form EP-102-1, Rev. 4, Page 4 of 5 
: 30. Planners responsible for Emergency Plan development and maintenance are properly trained. [16] D APPLICABILITY CONCLUSION D If no Part V criteria are checked, a 10 CFR 50.54(q) Evaluation is NOT required; complete Part VI. D If an Part V criteria are checked, com lete Part.VI 9"11d erform a 10 CFR 50.54 Evaluation.
Part VI. Signatures:
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l)ci,l,*ayaila_bl~, THEN iNITI.A.tis:one t6e:fonowirw bai;k,:upmelhods.
&deg;El, <;\'>nf.~re,nc;e brriige **q~$" OR, b: Individual agency-telephone numbers:*
{1)' PEMA:*717,651-2001*or717-651,2148 (AskfotWa_\\;11 Office!r~
czi L&#xa2;~MA:,:~'~eoo-e:z.1~~f1~:
* (3) QQEMA:.570-$,S.:!3,;-_57.2Q 4:. JDE;NTIFY yourself as*e~ch_ agency answers. 5, As a~enc\es answer,'sTAiE.the Cali siaius (Drill orAcluafEmer$Eiflcy}
ancl'ihefolfowini{:
;'This isBLi'stjuehariha Nuctear St~ti&sect;~ l(l(ilh.,a.~,Ernefge~~cy
~&sect;l!fli:~tiP.h,,&sect;i.l~qi{e~a,,dnaMs
... * <:1(9!~J~~,~~}?.J~W.
91.J.R~,Et'!_T
~Mf&sect;~~E~~Y 91{-&sect;SIFl<;:ATIQ~
~i?V,li;!,:), P;le~.s~ .verify th.at yo&#xb5; !J&sect;l.Ve rece1vedtli\'l Ern.erg~rn;;y Ngtrfj9.qt1or:i.8ep:qrt aria i,lancjbyfor,tran.srmtt~I
.. E?; 'WHEN Ili'leneiep
~h~: 9nJ!ne, TRAN~Mit ENR. ANb, R,!:QJjl:fs.trepeafback fo:m1 one a~ency, ,COG tbeJirn~Jb,e
.. &#xa3;;:Jne.~~ep.cy'.!::;1a.ssificaifon
'Levei was*cwnrnunfcated
:cf<:, e-ach*a~:te*ncv,1myour t?ositionJog (for."ENRonlX!*
;.il(Inaeiifi:ett.
:ci)-N~riibere~
t ~E{vei:'1*.f , .. , 2, *3,,.r, +-~~~t: 1 4:.Ang~~ent,:
Wt+, ;<;;,,_._,~== .for~atteil:
ile~~ing~,I~~en~:.
~eii;: '1,Q6",_Dj,n't~~ep y,itl). _next 
. . -.. EMERGENCY PLANNING FORMS.AND SUPPLEMENTARY INSTRUCTIONS:
Atfacllm.eht BB 'i3J;t.p3'.,(f()1 . :R~9i'iloti 17 Pgge :av *of 1"9.9 lJ.nif ,Q s. Hihe Prfrrfary rviElt. Tower &r d~ta'ls .not avaft:abie, deformine'.*the
:wind :~p~ed oe>rrectei:I stabllitY
:cl~iss as follows./'
.. -,a:, .t>.et$tniine th'e'Jriiffo1.:(t.mtotre.cf~d)
&sect;fa.blfiW ci:ass ustngthe measure'9'v~li.te of $igma 'theta a:ncl the>Supplemehtal' Meteorologkar Information Table:'1 (ot page Q ofthe: RS'S~screeh).
J>, m.et'~r:minJ:i lh~:.winq 1~pe$d :corretfed st~b]Jity cl$s$.[fi&#xa2;ci'tlpo o~in,g; the rn'iti"a:f c,,li:i$sif19ati:on 1 *,the measured wind speed; .a:nd, as appro.prfate_.eithef' Tal:iile:2 or Table 3. *4' i{tb.&sect; Rr~~ipit~f.i\'.:>.n Ra:fo il.aJaJrQm
'&#xa2;Otn.Pl!fer,poirit RAfNINHR _i_s' nPhwail$pl~:or riot)~Gclir_a.t~, *determlhe.PrecipitationRate:fr'din ,comp.uter'pointVML02: (lnstruhiehth:inge is 0~1 incq).. *,;1._ -CH&#xa2;k th~ G~owp OisJ5l@Y,~ou,ftqr,iSele'd
.. ''.Trends'j:*fr9m the :P$$ Maitdvlenu, 1.) unaeYtasulai<Disp1av*nends;,*se1ect-1 1:1*ref.ia,.1::Sele.cf .l~e.'Taoiilaf_Gt~.yp.:Disp1:gy qut!.Qn, . '2) _ Click in ~\Pt **1 :'.' whitedieltLSeleot
:a.'b!ock to .aad a;polnt ,3) :Undet''RdlntS9.arch, ie._xt\,enter ,i\ZMLd:ziiseiect
>i[V1L:0'2,#om:tfte;ii~b
-4) Sel~9\AJ;)g'OKt0,displa1tiselected:dafa:
,5:) Under: start:time; enter.:a Bate:*and*tlmeJ:lsintdheJormaf.sliown'forthetrend,of lnteresf '?can .make~*wider trencfof"'!1'5.
minutes'~
in'1 IArcHive.:Sample,Rate" andtheflseled
... :specific:timl:l if rilesiredj.
{enff'tlmeis cferaultecflo.cu*rrent).~liql<_QKto*tlJsplay the* .selecfed*.data. . .. ' . ' . . . . . .. ' -. c , < 0 ej Wlth:trend
'.disolayed,J~llck and-ho fol whiie dra&sect;ging vertlcal ffme line, fo.;date*
I time ;of :rntere~nwliiter box): o&i1a~i&~vamed*s
'disptayea
:for t~is'.,dat~
ana time' ihtfie:\&fiite.Hox , 7},. r&e,cord:R~c1aing,:2:o1~t cur~ent time ,~.n~: !Readi~g 1,af*1:s rriin~te~.
eEtt,lle~.
NOTE
* Time'beMe:en Riaading 2:and,Rs~ding
:f:.ls '15:mir1utes., lhstfliment dumps: the water at 1 inch. -5 .. Tne P.S.SQUALITY .coo.ES.fc>"rthe displ~y colc>:rs ate.J1sfollows:
Yt.;P-PW:
~l=D: MAGENTA: :wHfif ...
EMERG_ENCY PU\NNIN<:;
f PRM~j\Ntl 9UPJ='.P::MENTARY 1N~TRUCJipN$
At!ach,inei,t BB ~P-PS::001 Reyision *1e, Page .92 .of'200 l:JrjitO PLANT'COIVIPUT-ER METEOROLOG'ibAL DATA POU\IT IOENTIFl~RS METEOROLOGICAL
-PARAMETER POINT 10* UNITS PRIMARY TOWER -eastofthe plant, 300' lilgh iedlwhitetower.
10iJi\l\ijndDirecti_on*
vma03 .aegr&#xa2;ei;.
foin Wind Speed' vma06 mph Delta T''A'' 'vmacfr &deg;C/50m Delta T"E\'' vma02 &deg;C/50m 6bm \/Yjnd Direction vma04 _dEcigre(;lll 60m ~ind Speed vma07 mph
* 10fll _5)gnw l)et;a Wi1a10 degrees ,6Qrnip!g_n:i!!
T1;iet1;1 vmx24 degrees l;'recJpitatiqnB,a\e RAININHF.{'"*
iiiitir* AmbieritJemperature.
vmf08b *i= BACKUP TOWER-acrossfr&sect;m the S.SES Learnlng'Ceritef.
10mWiiid Direction vma05 degrees 10ni \_Nind:Spee~
vnjaQ~ mph. *10m.Sioma Theta -vma12 demees DOWNRIVER TOWER-'tiii Routlf93 just eastof Nescopeck; 10inWlnd'Direclion vmxoeb* degrees 1bm Wind Speed' vmsosb fnp_h :1dm Sigma Theta vmx1ob degrees AVERAGING . . . pi:fR.IOD
*15**111iiiutes 15 min'utes ls'nWnutes 15minuies 15 minutes 15:hiinutes l5 )Tlin&#xb5;t~s 15 min*utes -1'tfn\1~utes
* 111oui *1 frmiiiutes 15rri"inutes fs:minutes 2-minutes**'
2 rilintites**
2*min'utes-
* Letters*are given .h~re .in l<>W(li' c~se to differentiate the letter o from the !li.JiTib~r, Q. * ** Data from cotnp4ter pointVML02 may be used in plac~ pftfiiltfrom RAININHR.
.(See*s~ep AAin this ih~trtjction)
* ** FORM'EP-PS-001-41, Rev. 4, Page 7 of 12 r 'E.MJ::RElENt:X PLANNJ&G F:P)~MS A&t:U3.0P*~tgr0i=Nf ARY 1f!siRU<'.::noNs . ti;t~To 6 jc~F Revis/on 1a Pa e 9B"of,2oo
'.LJ.bhr****-*--. ryj~I~ tp;pipj~9!@.'p,c.tj)'ijj:l1ittsdn
~~@1/j a)W,ays 9e, Rerf&sect;frriI=lffofl;(=/6,'..(RP!,1,!]Il&sect;w)'
c[os~ )-~tes aJ'.id ;9SC::f<BJ~c~li.9~,t!2.~r:i
~iit~~-, If Q~RAKL~.l,lf)a.ya,ilpbl~I 9,Sl;l.~i.e!c!1Ja,m(~)*d9~,e.r,;ite~
ancj Q$(llAR ., Jqcation~, If !~cl1ati,op;?Pnd1b9-n5.tor:OSCAR are*!90,h1g~;
r~l91<a\\3 0SCAR.*;1Jo 2 mile$ away fron:i,tfJe
;plant*and perform fielcUo~pro1ecbon;measurementon'th1s data, /\, 'ijE'&#xa3;1!=,l/VriiQst;recebJ\(c:p)l~gt~i;i.w\tljirith$Jij~j;1/?
ljo~r)'Q$.CA[tq<jt~.
<ti\UT!Q.f'f Ail dose* rate reports di:itainable*under'"More
'Reports" ;show the dose rate. '.rmmed'iateiy priott<i,tfJ~:goseproiecJi9n ti[!1.e(Q,2q, ~. 2., 2(16,fJqyts),~ele,~!.ecJ..toJ:i!fP
.. E!iEic!: 1hll MIDAS.DoseAssessmentsumfria
*** sfieiefshoWs the c1ose*.rate imme* f ** *riorto "*''-"'"*";***O*J,*,."'"*'*,****"''>"'*
** .. .,,c,[Y, >., .. * *"\*""*< .. ,,.v,:cc**C*.,*;,*
: 0. ; ""' C .Y,J:l,,.,:.
*:.* tl'.l~
c9:?~-1@.tr~.ii~~,pf.9i~&#xa3;!ipr*11m<?*
.. rn~9,y@i~~
uwt th!!ir~}~i1 rn11~flik~!Y 1J:Yw111J19n i:i!'l.lYJFl\:,n*ll:l.~!1m~
WhJ=ln tt,~ o~cM.~r-~~i:t;~t9~199:BM&9i:!19 wa~ .. sonect~d.;~ng:(heJim~Jatwl'.lich ttie' proj~cted dtJse *rate,f_Qform~tiqpJs;;a Ju}ly'yati~.
., '!snapfihot" .ofaose:rates. ,Since.the pritnary'pUrp*ose
*or the,MIDAS Field T:o:Projection Dose.eomparison is:to'ictenHty an unh1onitated release path, ifisimportahttotompare*
theFiela Monitdr R~a'din ''.with -afra 'r6 riaie MIDAS 'ri:f~'cieci do&sect;e'.f~ie'in'brd&'fto
.*, d~t~rff\1fi~*if?'tl3J~'.~~~*i_~io'.t.n90Jl?r/l*P
...*... , ... P ... L ...................
' ' .. :'fi: measured data: were*collecte'd more'.!han'o:2siiours:at'tedfie start:ofiiie reiease, ustNhe ' lo*ecteif dose.tate informationfrom'More Re *orts for 1111:nime.
*erioct fnosf.closel
*
* 1 f~p}~{~~'.t!figitfi~
tfiM a:l'.w11)9iffi'i~j~t)\-~ci 4~1f ~t,/g"o1i~9t~'&#xa5; P *" ** * * * * *** "" Y *( T.9:~Mc.itnJfie:c:qrrwm<>JJ.di.ng
*pr9jecti<>n,~lita,~
iimEiy h~.n~pessary~o.re*r~.n
.. ;ex:a~t/y:.the'same:MIDA~;;NU case:and change *projection times:at the begjrinihg
*ofthe*nin lo tliiHime*
of interest.gjverr bytne'fieid data~ * * 'RECOGNJZEthat radioactive deca to tne selected time leads tci aismau u certaint * .in :1ii'~l~tiq)s(ti)e1s&#xb5;r~cff9::(pr6f~~iM*J[)~*c1irie:'ra1f
* *** *** ** * ** * ** * ** ** n: *** Y * * )~e:v1ei,y.
the MibAS:EDE bose Rate.Report(qrth!;!
c;9f(E;1sppndiilg rel~.as.e:tj111e andise*cfor, .. ... ' ' . . t. "* *:I. if i:on:irviiPA$:NCf gr.apo1c output f!C(e.en :~6owing*map*,and plume/SELECT*'EDE tab . *.1ocatec!
l!itbottom:'ofscreen*, ' * * * '2, *SELECT tali with .exposure, tim/3:of ili\erest.
'.&sect;:: :5.E.LJ:~Tta\>.l~tiib;
.4, ~~E.l,,E(?T 9i;,hfjjiij't~9.,
D l:.1 EI\IIER<3ENC'{,PERS<JN_NEL'D.0SE ASSESSMENT AND .... '". . . *P*Roi;ec;fi.vi:Ac_rioN GiJtDE .......... . Attach"ment:HH ,t=f-p~;p0,1 . Hevision 17 P?9 e 124 ~r 201 !Ji\it_'O
'Doses will.be maintaiiledwithirloccu atiafial.dose lirfiltsto the extenr* racticable
:~fo'tfig
-~m,ef!~~'.6si~s,=''
$t{sgbJin~n~tfri~*:@ffeger~(g9{~nifiieijt}e~p:,i,z~.
hg~~Y.~f .. :tl:lcitpo.hf61JI1a!lce-with.
reguf;;ition~.deye_lop_e_d{or norr:n~l,opeir;;itfi:ms*shp1,lld npt lirri it . . ~i,t1ons ryecessary fp.r-1~e;pr9.teclion,o(heallh anci safety. '.A~,dtrected'by OQFR.50j, :susquehanrya-uses 'the'EnvironmentahProte&#xa2;tkm Agahcfgtlidarice;on*
dos*eHitnits for* Workers*perfdrmihg
'ehlargeifoy services:
such as* Jifesaving'o(itlaffi!airiihi;Fbo"f1firlemeilt' Jif\a?;li<;!~ctNiffiiate.ri_ali( * * * * .. ' * *.. * ,.. * . -~-Dqs,e.s. IQ ?JI .\if6j-l<er~~dllfi,Q9
:eliietgerjci~~, sj1oufp,:to'tj1f)
~~t~ilt .prai;:tic.~bl.e, be l(n,ited t.o:~ re_r:n, jJ,pse_Jo,Jhe_~Qlbryo./fetus"of Deci~r~d P.regqt;11)!'\f\!oman
'ibPVV; see 'N_BAPc<:llA 0 0625);shotlld, to,tli'e exteh!practicable, !:le limited, tci '0.4.te'rn:
Planneddosev;;nld, woiitdtesuli.in ine''embry xceedirig.,0~4 tern '. ';*~P~tm!~.~:~:'r'.::::*
... '.:;:_::;:,;:
:;;~i~-~r1*~~g:tl;:#;.~!t~ti~~~v;,~-~~ . th6fe.is RQ,f3Fiil@tisal al!OfA~li~'Q:ay:ailabJe:-' . . . . .. . Tt\e dm;e limit forwernhers ofoffsl!e:support:'
groups*provklfng emergen&#xa2;y (e:g,,JireJfgfiting or ambUlafic~)
servkesio~-the . susquelianrfa:'sife bufolitside'ofth'e pto\egied are~,'.: rigg,~ dE1cl,a(eq e~n'i_e(ge,_n~t
.. e,Y~~t,)l~~l~t;&sect;r~:tn (P,;4te.iiitci~-.Y
****
* sY~*cpiis d~gt~f.?d.:
:t~at;3h,~
!$ P!~Qn,a11t), ab~!:3,ntaO!ryq_rgafrp11 fqr:an "rrergency ,Ei<pos&#xb5;re1; E~temsip!), Ttli.s lim~*js s1:,_t;recog1,1itiDQ Jb.attbe offsite s&#xb5;ppgrtgro.up personnel
'tJ!l,VE:l
*r,ecE1ivecl radipl9gi~-!1J eme1rnepcyresr,ons~\rainiri_g
*from, ,Qovernmenqmd/or ficens*ee instructors:
Further;.
the' ptbvisicih of** support services (e.g,; radiation Jlfotection; se;~u_rity;
?,!'i~ *emerge~sY
/iffllJ:i:O:tjse'fi:@:ia&sect;~m~'@
!ci tryfq,ffsi!~
~~Pti&ij:
gt6&#xb5;p}l~ri~hh:~!
*. PUt$.isf~
Jhf f:lr&deg;R!J:i.Qt$5/
ar,e,fi, 't9 ma.intain;aq)les,;inlomi:>!ign<;:~ ,Witn ./:lJo_y,,et ctqse, Umi\, i~,,:i\it FPn~i~terei;CpxE1.cti9~~/~;
}hi~'.i$,*.cl~_(;1(9Jtie.;.1J~ed}or ihe,~1;1 .. !5.\Jf:?po.r;t p~rsp[)ne,I to .be .P.rol(rding o.ther,service!5'in5.ideJheprotected' arei!idireq(ly relatea to rrianagerrient-ofthe'a.eclarea emergehcy*event
:ana 'specifical!ytotJie,pro.tec!ion
*9f publli;~~;d.,w_ot~Elr
.~~-aJtt(~~1fsar&#xa2;ty, l l Etvll;RGE~py Pl;'i\@ING i;t5RM$iA~Q
*s.w_ppLEMEN.t AJt((N!?JRiJ&#xa2;T)QN$
Att119h~,~rjf 8B .. ,EP,PS~001 ReJ/iio11
: 11. .Rage 121,ar20:r
:.W,Qi_t,;t('
.. . .... El'iifER~ENGY.e;'~$qNN~~
D,O,~!;:A:$S:g~:sMe'r~t.ANo PROTECTIVE ACTION GUIDE 111.sumn'fa
*, FDAu "derstands'.that a Kl*admihisfratiiin r *Y,ttam, ti7at'sels'.
afweterii
** 'r6;iic1ed-f1r
'rolc1;r'a&Taac1\'ve P .,.9 .... , , ...... " ............. , .... ,, P ",L ..........
.'/ ... ". ,. ,. ..*. , .. ,.7 ** -~xp_qs,4re:tlires_f),Qlq&sect;fo(tr~al[llerifofqiff$[enJ popyl,aticin gro,pp~ rnaY.,b~ l~&Jistical]Y'irnpr:ac!Jr;al.
to'iir!plein~rit
-. :during.<:\ ,rad1ologu:;al .emE1rgency, ffemergencyplanners
'reacl'ithis con'clusion,
* FEJAre*comme"nds th'at Kl be :~dr(linJ!lte.reJJto aJ1:a#&#xb5;lt&sect;\-riwar:fl!~!:($
of!\g( l;h~ R~ti'n~yjy,r;i~iapep@fueht
,9flje?!Itn tii'i1>;il&#xa2;og!WJ~g:
tJi~U((lyc1,9e.;w.p*q is* n9t:atf,e.mi~Jq.;f29jrie.!;ar:JH~~e;K1,.
JaKen:in:tpe,<ipse recornm~hcfed, Kl is,relativefysafe and :fi'ei/ _ofsfde effects; except:tot people who are alierciicto, *ioaiae. * * ** * * * ** ** *
* Declaration.ofifG
* al Emefr *enc
* is'.indicative'ot hint 'c6'i:laitions' that '"feiftc?re'sQrl~
sr*'nitcii"rii:
* P. * * * * ,..,* ' .... ,., ..*. ' ' "-~---*. ,., ............
g_ .... , .. ***.c ' . * '.~ifl:/.qrr(e t~i:!JqacUyi\y.
KL1>1i.<?l_!l9 t;let qffegid lo U~tl?}tiR!~nt teams. ~od ~ield Tep.ms {OSQAR, A~PHf.l; ~nd BRAVO} Uri.Jess ff,js dear !hii! fhere.[s'-no*,iuhstantilif'radioiodhie'
*comportelitttfihifatmo~phe1re*tliefwill be eliJerihq, .3;-hZ ~! ~!iqUJ~ .n~t 1;5~ ac!f!!iri!stefeq t{i' ~ny*ernefg~n*cy w~rk~tW~o, a. q6~1>Ju:it&sect;:ibcufwi~!1 i!~ .lfs~,c &#xa2;f 6.,. :c, .. '.hc!~}a krjoytn*aJlerg,c rea&#xa2;tron to)9~1ne ,an.qlor foods .1,onfairiing
* ic,cliiJe'S\ls~l:i$llhsk or, has been dite.cied oy:the'irP,hysician ot.Phaitnadstto ,avoid 1nge.stionofi6dine,and/offciods containing*i<;>dine(~Uc;!i'.as\, 1HY~!!~~-ij.
.. . . *. " . 
.I *AkARAREVlEW AND APPLY '.EMEFfoENcfrEXR@SuM*'
_ -* *,cor::tsT6EMf10Ns*:
* ALL'OF-A~Q.~1:
ANP:,~foE~iNG.. ,ONRISKS
* _I;ME8_(:31=N&#xa2;~(pi.:ANN1NG FORM$ANE?
s.L!PPI.EMENT:ARY 1NstRvct10Ns; Att~c,~rn~ri.t HH :EP-PS,001 Revision 17 PEJtie.1 of2Q1 q~it'Q 5. 6. lfihe Emergengy Exi)osute*Extehsicih
\s fot,gteaterthan 4 rem (TEDE):of44-fem (TE,DE)_ fl>r; *c1:W6"rnah
'Aiffci has desl_ar"ed t1-1at sf{e is ~i:egfiarit, h*aiie'tlie vcilunt~et:sign the EMERGENCY E~l:!q~u"~1:.
~EQlJ~sT i=9fm,~<::K~il~leggi,6il ifi~t ifigy.are a yoi~~i~~r)iriii 9 re f&#xb5;Jly .1lY:t?fEl qf the-~EJc:l!p!pg,c?t fl~~s of 1:19yte .. arq d.\"ll!lyed effecti,~d.
f9r tne \'lf)fnBRW.Q?,has, ae$.ii:e~t s_he. _IS RF.egnarit:
nsksJp:the;em~o/o#etus)..
* * -*
* Upon'ccimplefion-obhe activi\y requirin~
the Emerii!&#xa2;ncy Exposure perform*ihe foiiowintt P qoJl~ct process, and evai11afe per,sonneldosimetry-qevfoes,when-lechriic;aily appropriate..
*
* _D irwestigaielhe i,ircumsti,mces;ofail emergency expc:isures,;;ind c_orifirm*the.dose.
rece1vetL
* D N<:itify.
the.NRG otemer_gen<::y_exposure.asfollows:
Immediate notification of the NRGeis-required fcir: lt 1::~pos11rei':oft_he whole b.ody qfgreaf~r tn~n 25 fof)l (Tl,;DE)i:or.
: p. E~pos~re*_9(tr:i*e skiJ:i of th$.-~ho_lgi;J;>ody pf gre~tef,)hiiff 1 ;i.D iei)l J$Qi;:);\or c, Expp_suif ofthe exfre[JJiti~l>:9f.gr_eali;!r th_~r,-~75 rem ($OE). i'Jotific;~tion ofth.e NRG ~ithin .Z4 h9llr? is {equired Jor, a. Exposure ohhe whole body o(weater than 5rem :(TEDE); cw b, Exposure*of the skir'f ofthe.whole body of~_teater',thalfc~O r~i;n (S.DE); qr c; Exposure of tjle exlrefriiJties cifgie~ier_tt:icin 79 rem (SPE;). D Assess*ihe heaiih consequences ofallenfergency exposures.
Cons*ul\With a physici~n tc, i;l$termine*th~
ri~ea t 9 t a~a. :e.xteint of pijysical an:aJ;iiochernJc?I examinations:
0 Wtible body greater than 25 'rein :(TEDE) should r'e~u.1\jn a'1fe_x:1>mii]*i_lidH
()f !h_e exposed per~_on~y"a p~ysicia,ri.. . D _lf_int~rn~l~xpcisure.(s s,~s~ect.e~;_cjlf~QJ[\~i)i_e._n:ie_asr~~-~r:its S~?Ul~ ~e mili;1$ ils so6rf a~ ~ea~qnaply fea~1~le *. :B.1qas~ays are re_q&#xb5;,red basi;!d on th.e:follo_wmg_::
,. Na~al smf!ar:or facial cqntarrr'i11atiqn 9rec1ter fha!l j';oo:ct.<::PIJ:r above b;;i_ck~roun:d.
* C3reaier thc1n 4* bAC-HRS in a day or less,-or 20 DAC~HRS*in*aweek orless: FORM EP"PS 0 001~,f5: Rev.-3/Pa~e f<i*of 18 EMERGENQ::(RLANNING FORMS*~NQ SUPPLEMEhn:AR?'INSTRUCT!ONS Ati~i;;h111,e11t H8 EP-PS:001 Revision 16. P~ge 137 of 200 Upi!O Cf!EckD 1,0 Evaluat~ rac;liologica).coildjtiops.
 
===1.1 Qbtain===
detailed s&#xb5;r,ieycfata to al!certaln:
f 1.1 B~ta-'Gamma radiation ieyeis 1 :1 ;2 Neeq for neutron measurements 1d .3 *contamination levels and protective cloth in~ reql!irements 1'.1.4 Airl:i.ome radioactive.
materials
't.1,5 Vafia6ility .of coni:litioris.over space,and time 1,2 Eval&#xb5;ate pers*onr:iel's'tat).1s.
1 ,2.1 Determine a11ailab1e:dqse{1naer normal c1dmfnistrative dose_ obje~tJyes.
1:2.2 .l~es;;e_ntial,.pbtai1J.appro.11.?lfrmn RADl~TION PROTECTION . C_OORDINAJQR/EMERQE~yY*DIRE~T()~
fpr,persons expectect*to*
exceed aaniinistrative objectives. . 1:2.3 Follow criteti_a,if)
E!fiergenqy Per.~pi']n~I
(?,o,Se_Ai;sess!l)ent ,mg Protective.Action Guide in this attachment when emergency exposures
*are deefoe<;l
~ppropriaie by EME~GEr:ic:y PIREc'ro'R. . . , . . . . 1.2.4 Assess individual's liistory of el<pqsure to. airbpme materials:
1,2,5 Assess individual's'skills:in relation 'to,prqposed task. 1:2.6 Assess individual's lifetime exposure history, 1.$ Det 7 rn:iine propectype ar:id*placerilent*_ofqosh'neters.
1 ,3.1 Evalu~te need'for, a~ai!ionaLWh9le bqqy dosiJ!lf;)Jeir~.
NOTE For emergen_cy E!_Xposures al>ove 4 re!J:1.(-0.4 re_m_to a~G!ared~Rafft WOOJa.nh the:pta<;:e*meri~
o.f se,ver~I ~~sillietets
.~n;~ij iridiv!dual js rec9mmendEid t<> ,deter!llli1'e spatial dis(ributi9n c;>f dose, FORM EP 0 Plfcich-45, Rev. 3, Page 15of 17 Attachment A, 10CFR50.54q Screening Form Screening Number: S2018-10-24-01 I Part I. Description of Activity Being Reviewed (event or action, or series of actions that may result in a change to the Emergency Plan or affect the implementation of the Emergency Plan). Provide the existing text and the revised text (attaching a mark-up of the existing text with proposed change can be used as an alternative):
Remove "To the extent reasonable, persons with high lifetime cumulative radiation exposure should not take part in these actions." from Table 7.2, Emergency Exposure Criteria, Additional General Criteria Section and all applicable EP implementing procedures (ex. EP-PS-001)
Part II. Activity a Change per Section 3.1.3? 18] YES ONO Does the activity constitute a change per definition 3.1.3 -An action that Continue to next part 10 CFR 50.54(q) results in modification or addition to, or removal from the SSES Evaluation is NOT Emergency Plan, OR the resources, capabilities and methods identified in required.
Enter justification and the plan? complete Part VJ. Justification:
Part Ill. Activity Previously Reviewed?
DYES 12! NO Is this activity fully bounded by an NRC approved 10 CFR 50.90 submittal 10 CFR 50.54(q) Continue to next part or Alert and Notification System Design Report (44 CFR 350.14)? Evaluation is NOT required.
Enter If YES, identify bounding source document number/approval reference justification and and ensure the basis for concluding the source document fully bounds the complete Part VJ. proposed change is documented below: Justification:
D Boundino document attached (optional)
Part IV. Editorial Change DYES 0NO Is this activity an editorial or typographical change such as formatting, paragraph 10 CFR 50.54(q) Continue to numbering, speUing, or punctuation that does not change intent per defini_t_ion 3.1.4? Evaluation is NOT next part required.
Enter justification and complete Part VJ. Justification:
Part V. Emergency Planning Element/Function Screen (Associated 10 CFR 50.47(b) planning standard function identified in brackets.)
lfthis activity affects any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II, then place a check in the appropriate box. 1. Responsibility for emergency response is assigned.
[1] D 2. The response organization has the staff to respond and to augment staff on a continuing basis (24/7 D staffinq) in accordance with the Emen:1ency Plan. r11 3. The process ensures that on shift emergency response responsibilities are staffed and assigned.
[2] D 4. The process for timely augmentation of on~shift staff is established and maintained.
[2] D 5. Arrangements for requesting and using off site assistance have been made. [3] D 6. State and local staff can be accommodated at the EOF in accordance with the Emergency Plan. [3] D 7. A standard scheme of emergency classification and action levels is in use. [4] (RSPS) D 8. Procedures for notification of State and local governmental agencies are capable of alerting them of the declared emergency within 15 minutes after declaration of an emergency and providing follow-up D notifications.
[SJ (RSPS) Electronic Form EP-102-1, Rev. 4, Page 1 of 2 Attachment A, 10CFR50.54q Screening Form, Continued Part V. Emergency Planning Element/Function Screen (cont.) (Associated 10 CFR 50.47(b) planning standard identified in brackets.)
If this activity affects any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II, then place a. check in the annropriate box. 9. Administrative and physical means have been established for alerting and providing prompt D instructions to the public within the plume exposure pathway. [5] (RSPS) 10. The public ANS meets the design requirements of FEMA-REP-10, Guide for Evaluation of Alert and Notification Systems for Nuclear Power Plants, or complies with the licensee's FEMA-approved ANS D desion report and sunoortino FEMA anoroval letter. rs1 (RSPS) 11. Systems are established for prompt communication among principal emergency response D oroanizations.
[61 12. Systems are established for prompt communication to emergency response personnel.
[6] D 13. Emergency preparedness information is made available to the public on a periodic basis within the D plume exposure pathway Emen:1encv Plannino Zone (EPZ). 171 14. Coordinated dissemination of public information during emergencies is established.
[7] D 15. Adequate facilities are maintained to support emergency response.
[8] D 16. Adequate equipment is maintained to support emergency response.
[8] D 17. Methods, systems, and equipment for assessment of radioactive releases are in use. [9] (RSPS) D .18. A range of public PARs is available for implementation during emergencies.
[1 OJ (RSPS) D 19. Evacuation time estimates for the population located in the plume exposure pathway EPZ are available to support the formulation of PARs and have been provided to State and local governmental D authorities.
[1 OJ (RSPS) 20. Kl is available for implementation as a protective action recommendation in those jurisdictions that D chose to provide Kl to the public [101 21. A range of protective actions is available for plant emergency workers during emergencies, including 181 those for hostile action events.r1 Dl 22. The resources for controlling radiological exposures for emergency workers are established.
[11] 181 23. Arrangements are made for medical services for contaminated, injured individuals.
[12} D 24. Plans for recovery and reentry are developed.
[13] D 25. A drill and exercise program (including radiological, medical, health physics and other program areas) D Is established.
[14] 26. Drills, exercises, & training evolutions that provide performance opportunities to develop, maintain, & D demonstrate key skills are assessed via a formal critique process in order to identifv weaknesses.
f141 27. Identified weaknesses are corrected.
[14] D 28. Training is provided to emergency responders.
[15] D 29. Responsibility for Emergency Plan development and review is established.
[16] D 30. Planners responsible for Emergency Plan development and maintenance are properly trained. [16] D APPLICABILITY CONCLUSION D If no Part V criteria are checked, a 1 O CFR 50. 54( q) Evaluation is NOT required; complete Part VI. 181 If anv Part V criteria are checked, complete Part VI and perform a 10 CFR 50.54(a) Evaluation.
Part VI. Signatures: Adrian Miron I . 10/24/18 Preparer Name (Print) (JFG EP109) r[::i_()iJif:-*
Date f}O}j.., /v111Y'(/fl/?.
fl) 1~{);~ Reviewer Name (Print) (JFG EP109) )'7~)flew&#xa2;j;.1:,iQnature Date 1 /I (/ Electronic Form EP-102-1, Rev. 4, Page 2 of 2 Attachment B, 1 OCFR50.54q Evaluation Checklist Evaluation Number: E2018-10-24-01 I Screen Number: S2018-10-24-01 Part I. Description of Proposed Change (Copy applicable information from 50.54(q) screen form Part I or attach a mark-up of the existing text with the proposed change can be used as an alternative):
Remove "To the extent reasonable, persons with high lifetime cumulative radiation exposure should not take part in these actions." from Table 7.2, Emergency Exposure Criteria, Additional General Criteria Section and all applicable EP implementing procedures (ex. EP-PS-001)
S2018-10-24-01 identified 2 Emergency Planning Elements/Functions potentially associated to this change: e 21. A range of protective actions is available for plant emergency workers during emergencies, including those for hostile action events.[10]
* 22. The resources for controlling radiological exposures for emergency workers are established.
[11] These are associated with 10CFR50.47.b(10) and 10CFR50.47.b(11) requirements, respectively.
Background information on the change:
* SSES Emergency Plan Rev 6 (E-Plan) issued on 11/2/82 is the original SER version of the E-Plan and included a range of protective actions for plant emergency workers for controlling radiological exposures in Table 6.2. The E-Plan was approved by NRC on 10/31/83.
At that time, the sentence above was not included in Table 6.2.
* SSES Emergency Plan Rev 10 (E-Plan) issued on 1/14/87 added a section and therefore, Table 6.2 became Table 7.2. The change was processed-without NRC approval.
The sentence above was not included in Table 7.2 of the E-Plan.
* The sentence was added in Table 7.2 of the SSES Emergency Plan Rev 18 (E-Plan) issued on 5/20/93. The change was processed without NRG approval and the reason for addition was not documented.
Subsequently, the sentence is present in Table 7.2 in all E-Plan reviews up to current rev 61.
* No other NRC SERs were sought on Table 7.2 up to this date. Part II. Evaluation of the Proposed Change for Compliance with the requirements of 10 CFR 50.47(b) and 10 CFR 50 Appendix E: 10 CFR 50.47(b)(10) -A range of protective actions has been developed for the plume exposure pathway EPZ for emergency workers and the public. In developing this range of actions, consideration has been given to evacuation, sheltering, and, as a RG-1.219, Rev. 1, Page 30 supplement to these, the prophylactic use of potassium iodide (Kl), as appropriate.
Evacuation time estimates have been developed by applicants and licensees.
Licensees shall update the evacuation time estimates on a periodic basis. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway EPZ appropriate to the locale have been developed.
There are no 1 OCFRSO Appendix E requirements associated with Emergency Planning Standard [1 OJ. The change described in Part I is not applicable to this requirement.
10 CFR 50.47(b)(11)
-Means for controlling radiological exposures, in an emergency, are established for emergency workers. The means for controlling radiological exposures shall include exposure guidelines consistent with EPA Emergency Worker and Lifesaving Activity Protective Action Guides. The change described in Part I is applicable to this requirement; however, as discussed in Part Ill, the guidance proposed for deletion is not applicable to EPA-400-R-92-01, Manual for Protective Action Guides and Protective Actions for Nuclear Incidents, that SSES is committed to and means for controling radiological exposure are still in place with this change. Electronic Form EP-102-2, Rev. 4, Page 1 of 5 
\ Sections IV. E. 1 of 1 OCFR50 Appendix E requirements associated with Emergency Planning Standard [11]: Equipment at the site for personnel monitoring.
* The change described in Part I is not applicable to this requirement.
Therefore, deleting "To the extent reasonable, persons with high lifetime cumulative radiation exposure should . not take part in these actions." from Table 7.2, Emergency Exposure Criteria, Additional General Criteria Section from E-Plan and* all applicable EP implementing procedures does not affect the requirements in 10CFR50.47(b) and Appendix E to 10CFR Part 50. . Part Ill. Evaluation of Emergency Planning Functions, Elements, and Commitments affected by the Proposed Change and the Licensing Basis for those Functions, Elements, and Commitments:
Emergency Planning Standards (Function) for 1 O CFR 50.47{b)(10) that are applicaqle to this change is: A range of protective actions is available for plant emergency workers during emergencies; including those for hostile action events A range of prc;>tective actions for emergency workers are considE3red in Table 7.2 of the SSES 'Emergency Plan rev 61 and applicable implementing EP procedures.
As stated in the first paragraph, "Planned exposure to the whole body and/or specific organs should not exceed the following recommendations of the National Council on Radiation Protection and Measurements and the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA 400)." The statement proposed for deletion is just one guidance among a host of other guidance from EPA 400 that is applicable only to dose .extensions over 25 rem. As wili be discussed below, this guidance is not included in the EPA 400 PAG manual to which $SES.is committed to. No applicable Program Elements from NUREG-0654.Sections II.J.1-8 and Section.11.J.10 associated with the*. Emergency Planning Function [1 OJ Were found applicable to the change described in Part I. Emergency planning Standards (Function) for 10 CFR 50.47(b){11) that are applicable to the change described in part I is: The resources for controlling radiological exposures for emergency workers are* established.
* . A range of protective actions for controlling radiological exposures are considered in Table 7.2.of the SSES Emergency Plan rev 61 and applicable implementing EP procedures.
As stated .in the first paragraph, "Planned exposure to the whole bo.dy andlor specific organs should not exceed the following.
* *recommendations of the National Council on Radiation Protection and Measurements and the Manual of . Protective Action Guides and Protective Actions for Nuclear Incidents (EPA 400)." The statement proposed for deletion is just one guidance among a host of other guidance from EPA 400 that is applicable only to dose extensions over 25 reni. As will be discussed below in the section on EPA 400, this guidance is not included in the.EPA 400 manual to which SSES is committed to. * *
* Applicable Program Elements from NUREG-0654 Sections 11.K associated with the Emergency Planning Function [11] are: *
* Each licensee shall establish onsite exposure guidelines consistent with EPA Emergency Worker and Lifesaving Activity Protective Actions .Guides (EPA 520/1-75/001) for: a. removal of injured persons; b .. undertaking corrective actions; c. performing assessment actions;
* d. providing first aid; e. performing personnel decontamination;
* f. providing ambulance seNice; and g. providing medical treatment seNices. Electrbnic Form EP-102-2, Rev. 4, Page 2 of 5 / 
\
* Each licensee shall provide an onsite radiation protection program to be implemented during emergencies, including methods to implement exposure guidelines.
The plan shall identify individual(s), by position or title, who can authorize emergency workers to receive doses in excess of 10 CFR Part 20 limits. Procedures shall be worked out in advance for permitting onsite volunteers to receive radiation exposures in the course of carrying out lifesaving and other emergency activities.
These procedures shall include expeditious decision making and a ,.. reascmable consideration of relative risks. The statement proposed for deletion described in Part I does not apply to any of the applicable NU REG 0654 guidance listed above. NSIR/DPR-ISG-01 Section IV.F Protective Actions For Onsite. Personnel (Hostile Action) was reviewed and found to be not applicable to the change described.in Part I.
* Reg. Guide 1.219 Revision 1 sections 4.10 and 4.11 were reviewed for examples of changes that could require prior NRG approval and none were found to be applicable for the change described in Part I. As discussed above, SSES is committed to EPA-400-R,,;92-01, Manual for Protective Action Guides and Protective Actions for Nuclear Incidents.
Applicable guidance for establishing protective actions for controlling radiological exposures for emergency workers are as follows: Guidance on dose limits for workers performing emergency seNices is summarized in Table 2-2. These limits apply to doses incurred over the duration of an emergency.
That is, in contrast to the PA Gs, where , only the future dose that can be avoided by a specific protective action is considered, all doses received during an emergency are included in the limit. Further, the dose to workers performing emergency services may be treated as a once-in-a lifetime exposure, and not added to occupational exposure accumulated under nonemergency conditions for the purpose of ascertaining conformance to normal occupational limits, if this is necessary.
However, any radiation exposure of workers that is associated with an incident,.
but accrued during nonemergency operations, should be limited in accordance with relevant occupational limits for normal situations.
Federal Radiation Protection Guidance for occupational exposure recommends an. upper bound of five rem per year for adults and one tenth this value for minors and.
* the unborn (EP-87). We recommend use of this same value.here for the case of exposures during an emergency.
To assure adequate protection of minors and the unborn during emergencies, the performance of emergency services should be limited to nonpregnant adults. As in the case of normal. occupational exposure, doses received under emergency.conditions should also be maintained as low as reasonably achievable (e.g., use of stable iodine, where approptiate, as a prophylaxis to reduce thyroid dose from inhalation of radioiodines and use of rotation of workers).
* Doses to all workers during emergencies should, to the extent practicable, be limited to 5 rem. There are some emergency situations, however, for which higher exposure limits may be justified.
Justification of any such exposure must include the presence of conditions that prevent the rotation ofwo_rkers or other commonly-used dose reduction methods. Except as noted below, the dose resulting from such emergency exposure should be limited to 1 O rem for protecting valuable properly, .. and to 25 rem for life saving activities and the protection of large populations.
In the context of this guidance, exposure of workers that is incurred for the protection of large populations may be considered justified for situations in which the collective dose avoided by the emergency operation is significantly larger than that Incurred by the_ workers involved.
* Situations may also rarely occur in which a dose in excess of 25 rem for emergency exposure would be unavoidable in order 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 the Jives
* of others. However, persons underlaking any emergency operation in which the dose will exceed 25 rem to the whole body 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. Electronic Form EP-102-2, Rev. 4, Page 3 of 5 Tables 2-3 and 2-4 provide some general information that may be useful in advising emergency workers of risks of acute and delayed health effects associated with large doses of radiation.
Table 2-3 presents estimated risks of early fatalities and moderately severe prodromal (forewarning) effects that are likely to occur shortly after exposure to a wide range of whole body radiation doses. Estimated average cancer mortality risks for emergency workers corresponding to a whole-body dose equivalent of 25 rem are given in Table 2-4, as a function of age at the time of exposure.
To estimate average cancer mortality for moderately higher doses the results in Table 2-4 may be increased linearly.
These values were calculated using a life table analysis that assumes the period of risk continues for *the duration of the worker's lifetime.
Somewhat smaller risks of serious genetic effects (if gonadal tissue is exposed) and of nonfatal cancer would also be incurred.
An expanded discussion of health effects from radiation dose is provided in Appendix B. Some workers performing emergency services will have little or no health physics training, so dose minimization through use of protective equipment cannot always be assumed. However, the use of respiratory protective equipment can reduce dose f(Om inhalation, and clothing can reduce beta dose. Stable iodine is also recommended for blocking thyroid uptake of radioiodine in personnel involved in emergency actions where .atmospheric releases include radioiodine.
The decision to issue stable iodine should include consideration of established State medical procedures, and planning is required to ensure its availab#ity and proper use. The statement proposed for deletion described in Part I does not apply to any of the applicable EPA guidance listed above. As discussed in Part I, Background Information section, the original SER version of the E-Plan included a range of protective actions for plant emergency workers for controlling radiological exposures in Table 6.2 but the sentence proposed for deletion was not included.
It was introduced later, without requesting NRC approval:
No other NRC SERs were sought on Table 7.2 up to this date. Therefore, deleting this sentence does not constitute a licensing or commitment violation.
To cover all bases, as part of AR-2016-17490 evaluation, EP organized a meeting with RP and ISD representatives on 8/1/18 to discuss the following:
* EP could not find any regulation or guidance (10CFR50.47(b), Appendix E to Part 50, NUREG 0654 and EPA 400) associated with the statement in EP-PS-001-45 form that "use of personnel with high lifetime cumulative exposure should be discouraged" (for emergency exposure extensions).
Note that the lifetime dose would also be used as criteria to select personnel for dose extension in ALARA brief (EP-PS-001-4).
* The guidance in EP-PS-001-45 is aligned with the guidance in Additional General Criteria in Table 7.2 of the SSES Emergency Plan Rev 61 (E-Plan) which states "to the extent reasonable, persons with high lifetime cumulative radiation exposure should not take part in these actions".
* Since the guidance above is not part of any known regulations or guidance, EP proposed deletion of the guidance in the E-Plan, EP-PS-001-45 and EP-PS-001-4 form. Participants agreed with EP proposal and mentioned that there is no associated regulation in 10CFR20 on this issue either. In addition, participants agreed that older personnel are expected to have a high lifetime cumulative exposure and they are the preferred personnel to be used in a radiological emergency due to their experience and lower radiological risk when compared with the younger personnel.
Therefore, the guidance is also not aligned with the current science. In addition, EP performed a benchmark to attempt identification of any associated regulations or guidance on this issue and asked the industry the following questions:
Does your E-Plan or E-Plan Implementing Procedures base any decision on the emergency worker lifetime dose? Electronic Form EP-102-2, Rev. 4, Page 4 of 5 The following answers were received:
Wolf Creek (WNOC) Seabrook No No No First Energy Callaway Uses a "plant requirement based on the judgement of our HP Staff at the time" for use of personnel that "Preferably has a lifetime dose (in rem) of fess than his/her age and has not previously received a dose in excess of 1 OCFR20 limits" Therefore, deleting "To the extent reasonable, persons with high lifetime cumulative radiation exposure should not take part in these actions." from Table 7.2, Emergency Exposure Criteria, Additional General Criteria Section from E-Plan and all applicable EP implementing procedures does not affect SS!=S Emergency Planning Functions, Elements, Commitments and Licensin Basis. Part IV. Evaluation of the Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions: . As discussed in Section 111, Applicable Program Elements from NUREG-0654 Sections 11.K associated with the Emergency Planning Function [11], procedures on establishing protective actions for controlling radiological exposures for emergency workers "shall include expeditious decision making and a reasonable consideration of relative risks." To use lifetime dose as criteria for dose extension over 25 rem will be very time consuming and thus not appropriate in an emergency.
To obtain lifetime doses for personnel hired at SSES and who worked before at another nuclear plant is difficult to obtain. This type of record is not required for normal operation occupational exposure and can be obtained only on a voluntary basis. The previous dose tracking system (NIMS) had the capability to enter this information whereas in the new dose tracking systems (Sentinel) implemented at SSES this feature is not available anymore. Note that Sentinel can generate lifetime exposure for personnel involved in Special Non-Emergency Exposures based on their known personal dose accumulated at SSES and elsewhere.
In this case, however, there is time to generate this report since the required work is not performed in an emergency.
Therefore deleting "To the extent reasonable, persons with high lifetime cumulative radiation ffxposure should not take part in these actions." from Table 7.2, Emergency Exposure Criteria, Additional General Criteria Section from E-Plan can only improve the efficiency of making decisions for selecting personnel who volunteers for dose extension over 25 rem and thus does not decrease the effectiveness of the E-Plan. Part V. Evaluation Conclusion Answer the following questions about the proposed change. 1. Does the ro osed change compl with 10 CFR 50.47 b and 10 CFR 50 Appendix E? 2. Does the proposed change maintain the effectiveness of the Emergency Plan (i.e., no reduction in effectiveness
? 3. [8l YES D NO. [8l YES ONO 0 YES [8l NO If questions 1 or 2 are answered NO, or question 3 answeredYES, obtain prior NRC approval under provisions of 10 CFR 50.90. If questions 1 and 2 are answered YES, and question 3 answered NO, implement applicable change rocess es. Part VI. Signatures:
Adrian Miron 10/24/18 Preparer Name (Print) {JFG EP109) ~/( Reviewer Name (Print) (JFG EP109) Electronic Form EP-102-2, Rev. 4, Page 5 of 5 Attachment B, 1 OCFR50.54q Evaluation Checklist Evaluation Number: E2018-10-29-01 I Screen Number: $2018-10-25-01 Part I. Description of Proposed Change (Copy applicable information from 50.54(q) screen form Part I or attach a mark-up of the existing text with the proposed change can be used as an alternative):
Per CR-2018-03742, PPL Electric Utilites is no longer providing major equipment support for Susquehanna SES. Don E. Bower, Inc. will instead provide major equipment support to the site. This change is being made to Appendix A -Letters of Agreement in the Emergency Plan. Part II. Evaluation of the Proposed Change for Compliance with the requirements of 10 CFR 50.47(b) and 10 CFR 50 Appendix E: See Attachment
: 1. Part Ill. Evaluation of Emergency Planning Functions, Elements, and Commitments affected by the Proposed Change and the Licensing Basis for those Functions, Elements, and Commitments:
See Attachment
: 1. Part IV. Evaluation of the Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:
See Attachment
: 1. Part V. Evaluation Conclusion Answer the following questions about the proposed change. 1. Does the proposed chanQe comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? !g]YES ONO 2. Does the proposed change maintain the effectiveness of the Emergency Plan (i.e., no lg] YES ONO reduction in effectiveness)?
: 3. Does the proposed chanQe constitute an emergency action level scheme change? 0 YES [gJ NO If questions 1 or 2 are answered NO, or question 3 answered YES, obtain prior NRC approval under provisions of 10 CFR 50.90. If questions 1 and 2 are answered YES, and question 3 answered NO, implement applicable change orocess(es).
Part VI. Signatures:
Meaean M. Brown ... u.. e .. _, I O / 2.. "I / let' Preparer Name (Print) (JFG EP109) Pref*!rer Signature Date I RcA.,,,.tJ P. R@~~tv -d//l--~-10 I '.30 /,-, 8' '<.)r*. -Reviewer Name (Print)'(JFG EP109) Reviewer Signafu@ Date' Electronic Form EP-102-2, Rev. 4, Page 1 of 1 Background and Scope: Per CR-2018-03742, PPL Electric Utilites is no longer providing major equipment support for Susquehanna SES. Don E. Bower, Inc. will instead provide major equipment support to the site. This change is being made to Appendix A -Letters of Agreement in the Emergency Plan. The new letter of agreement with Don E. Bower, 1.nc. is virtually identical to the agreement that had existed with PPL Electric Utilities.
PLE-0026052 states in part "Don E. Bower, Inc. agrees to provide heavy equipment support operations, including personnel and equipment, at the Susquehanna Steam Electric Station as may be required".
There are currently three (3) other heavy equipment companies (in addition to Don E. Bower, Inc.} that have signed the 2018 letters of Agreement and continu~ to provide heavy equipment support service to SSES. PPL Electric Utilities.
is based approximately 25 miles south of the plant and Don E. Bower, Inc. is based approximately 7 miles west of the plant. Part II. Evaluation of the Proposed Change for Compliance with the requirements of 1 O CFR 50.47(b) and 10 CFR 50 Appendix E: Evaluation of 10CFR50.47(b) requirements associated with Emergency Planning Standard [11 & [31:
* 10 CFR 50.47(b)(1)
-Primary responsibilities for emergency response by the nuclear facility licensee and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.
* 10 CFR 50.47(b)(3) -Arrangements for requesting and effectively using assistance resources have been made, arrangements to accommodate State and local staff at the licensee's Emergency Operations Facility have been made, and other organizations capable of augmenting the planned response have been identified.
SSES remains in compliance with this requirement since there were four total heavy equipemnt companies available to support SSE$ before and after this change .. Evaluation of Sections IV.A.6 of 1 OCFR50 Appendix E requirements associated with Emergency Planning Standard [11 & [31: A description qf the local offsite services to be provided in support of the licensee's emergency organization.
SSES remains in compliance with these requirements since the new letter of agreement with Don E. Bower, Inc. is virtually identical to the agreement that had existed with PPL Electric Utilities.
PLE-0026052 states in part "Don E. Bower, Inc. agrees to provl~e heavy equipment support operations, including personnel and'equipment, at the Susquehanna Steain Electric Station as may be required".
Part III. Evaluation of Emergency Planning Functions, Elements, and Commitments affected by the Proposed Change and the Licensing Basis for those Functions, Elements, and Commitments:
Emergency Planning Standard [11 & (31: from 10CFR50.54(q)
Screening Form:
* Arrangements for requesting and using off site assistance have been made.
* Adequate equipment is maintained to support emergency response.
SSES remains in compliance with this requirement since there were four total heavy equipemnt companies available to support SSES before and after this change. NUREG-0654 Section 11.A, B and C Program Elements associated with the Emergency Planning Standard (11 & [31: *
* A. Primary responsibilities for emergency response by the nuclear facility, licensee, and by State and Local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continues basis. o A. 1. a -Each plan shall identify the State, local, Federal and private escort organizations (including utilities), that are intended to be part of the overall response organization for Emergency Planning Zones. o A.3. -Each plan shall include written agreements referring to the concept of operations developed between Federal, State, and local agencies and other support organizations having an emergency response role within the Emergency Planning Zones. The agreements shall identify the emergency measures to be provided and the mutually acceptable criteria for their implementation, and specify the arrangements for exchange of information.
These agreements may be provided in an appendix to the plan or the plan itself may contain descriptions of these matters and a signature page in the plan may serve to verify the agreements.
The signature page format is appropriate for organizations where response functions are covered by laws, regulations or executive orders where separate written agreements are not necessary.
* B. On-shift facility licensee responsivities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of response capabilities is available, and the interfaces among various onsite response activities and offsite support response activities are specified.
o B. 8. -Each licensee shall specify the contractor and private organizations who may be requested to provide technical assistance to and augmentation of the emergency organization.
o B. 9. -Each licensee shall identify the services to be provided by local agencies for handling emergencies, e.g., Police, Ambulance, Medical, Hospital, and fire-fighting organizations shall be specified.
The licensee shall provide for transportation and treatment of injured personnel who may also be contaminated.
Copies of the arrangements and agreements reached with contractor, private, and local support agencies shall delineate the authorities, responsibilities, and limits on the actions of the contractor, private organization, and local services support groups.
* c: Arrangements for requesting and effectively using assistance resources have been made, arrangements to accommodate State and Local Staff at the licensee's near-site Emergency Operations Facility have been made, and other organizations capable of augmenting the planned response have been identified.
o C.4. -Each organization shall identify nuclear and other facilities, organizations or individuals which can be relied upon in an emergency to provide assistance.
Such* assistance shall .be identified and supported by appropriate letters of agreement.
SSES remains in compliance with this requirement for heavy equipement support and maintaining a letter of agreement with this company and the other three for the reasons stated above. Applicable sections of the Emergency Plan associated with NUREG-0654 Section II. A, B and C Program Elements:
: 1. 2. 3. 4. 5. 6. A.1.a Chapter 6, Section 6.0, Appendix A A.3. Appendix A 8.8 .. Chapter 6, Appendix A 8.9.
* Chapter 6, Appendix A. ,' C.4. Appendix A Chapter 6, Sections 6.3.3 & 6.3.4 AooendixA There are no additional changes needed to the Emergency Plan sections listed above other than the change to Appendix A .. Part IV. Evaluation of the Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions and Commitments:
There is no negative Impact of the proposed change on the effectiveness of the Emergency Plan Functions for the reasons stated above. There is no negative impact of the proposed change to commitments for the following reasons: *
* SSES will maintain compliance with the applicable regulatory requirements.
* Don E. Bower, Inc. is a viable alternative service to provide heavy eq!,lipment support since there are currently three (3) other heavy equipment companies (in addition to Don E: Bower, Inc.) that have signed the 2018 letters of Agreement and continue to provide heavy equipement support to SSES;
* PPL Electric Utilities.
is based approximately 25 miles south of the plant and Don E. Bower, Inc. is based approximately 7 miles west of the plant Reg. Guide 1.219 Revision 1 section 4.12 was reviewed for examples of changes that could require prior NRG approval and none were found to be applicable.
Per the guidance in EP-102 Attachments F and G, this change does not constitute a scheme change. The proposed change is not a reduction in effectiveness of the Emergency Plan and therefore . does not require prior NRC approval.
Attachment 8, 10CFR50.54q Evaluation Checklist Evaluation Number: E2018-10-29-02 I Screen Number: S2018-10-25-01 Part I. Description of Proposed Change (Copy applicable information from 50.54(q) screen form Part I or attach a mark-up of the existing text with the proposed change can be used as an alternative):
Per CR-2018-12173, Shickshinny Volunteer Fire Department is no longer providing offsite fire response support to SSES. Summerhill Fire Company has signed the 2018 Letter of Agreement with SSES to provide fire fighting support in replacement of the Shickshinny Volunteer Fire Department.
Part II. Evaluation of the Proposed Change for Compliance with the requirements of 10 CFR 50.47(b) and 10 CFR 50 Appendix E: See Attachment
: 1. Part Ill. Evaluation of Emergency Planning Functions, Elements, and Commitmeqts affected by the Proposed Change and the Licensing Basis for those Functions, Elements, and Commitments:
See Attachment
: 1. Part IV. Evaluation of the Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:
See Attachment
: 1. Part V. Evaluation Conclusion Answer the following questions about the proposed change. 1. Does the proposed chanQe comply with 10 CFR 50.47(b) and 10 CFR 50 Aooendix E? 181YES0 NO 2. Does the proposed change maintain the effectiveness of the Emergency Plan (i.e., no 181 YES ONO reduction in effectiveness)?
: 3. Does the proposed change constitute an emergency action level scheme chc;1nge?
0 YES 181 NO ) If questions 1 or 2 are answered NO, or question 3 answered YES, obtain prior NRC approval under provisions of 10 CFR 50.90. If questions 1 and 2 are answered YES, and question 3 answered NO, implement applicable change process{es).
Part VI. Signatures:
Megean M. Brown , ll.,\..io
* n --l.,.L (\~~ 10 L~'\ I 18' Preparer Name (Print) (JFG EP109) ~Preparer Signature Date R~" lrl P. 1-,Y Ur J!. A-.-1)('\
1&deg;/ao/1Y Reviewer Name (Print) (JFG EP109) Reviewer Sig6ilt~ Date Electronic Form EP-102-2, Rev. 4, Page 1 of 1 E2018-10-29-02 Attachment 1 Background and Scope: Per CR-2018-12173, Shickshinny Volunteer Fire Department is no longer providing offsite fire response support to SSES. Summerhill Fire Company has signed the 2018 Letter of Agreement with SSES to provide fire fighting support in replacement of the Shickshinny Volunteer Fire Department.
The new letter of agreement with Summerhill Fire Company is virtually identical to the agreement that had existed with the Shickshinny Fire Department.
PLE-0026081 states in part "Summerhill Fire Company agrees to provide firefighting assistance, including personnel and equipment, at the Susquehanna Steam Electric Station as may be required".
There are currently four (4) other Fire Companies
{in addition to the Summerhill Fire Company) that have signed the 2018 letters of Agreement and continue to provide fire fighting support services to SSES. Shickshinny Fire Company is based approximately 5 miles east of the plant and Summerhill Fire Company is based approximately 9 miles north of the plant. Part II. Evaluation of the Proposed Change for Compliance with the requirements of 1 O CFR 50.47(b) and 10 CFR 50 Appendix E: Evaluation of 10CFR50.47(b) requirements associated with Emergency Planning Standard {11 & [31:
* 10 CFR 50.47(b}(1)
-Primary responsibilities for emergency response by the nuclear facility licensee and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis. *
* 10 CFR 50.47(b)(3} -Arrangements for requesting and effectively using assistance resources have been made, arrangements to accommodate State and local staff at the licensee's Emergency Operations Facility have been made, and other organizations capable of augmenting the planned response have been identified.
*
* SSES remains in compliance with this requirement since there were five (5) fire companies available to support SSES before and after this change. Evaluation of Sections IV.A. 6 of 1 OCFR50 Appendix E requirements associated with Emergencv Planning Standard [11 & [31: A description of the local offsite services to be provided in support of the licensee's emergency organization.
* SSES remains in compliance with these requirements since the new letter of agreement with Summerhill Fire Company. is virtually identical to the agreement that had existed with the Shickshinny Fire Department.
PLE-0026081 states in part "Summerhill Fire Company agrees.to provide firefighting assistance, including personnel and equipment, at the Susquehanna Steam Electric Station as may be required".
I Part Ill. Evaluation of Emergency Planning Functions, Elements, and Commitments affected by the Proposed Change and t~e Licensing Basis for those Functions, Elements, and Commitments:
Emergency Planning Standard 111 & [37: from 1 OCFR50. 54(q) Screening Form:
* Arrangements for requesting and using off site assistance have been made.
* Adequate equipment is maintained to support emergency response.
SSES remains in compliance with this requirement since the total number of Fire Companies available to support SSES before and after this change there will remain the same. NUREG-0654 Section II.A, B and C Program Elements associated with the Emergency Planning Standard &#xa3;11 & &#xa3;37:
* A. Primary responsibilities for emergency response by the nuclear facility, licensee, and by State and Local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continues basis. o A.1.a -Each plan shall identify the State, local, Federal and private escort organizations (including utilities), that are intended to be part of the overall response organization for Emergency Planning Zones. ' o A.3. -Each plan shall include written agreements referring to the concept of operations developed between Federal, State, and local agencies and other support organizations having an emergency response role within the Emergency Planning Zones. The agreements shall identify the emergency measures to be provided and the mutually acceptable criteria for their implementation, and specify the arrangements for exchange of information.
These agreements may be provided in an appendix to the plan or the plan itself may contain descriptions of these matters and a signature page in the plan may serve to verify the agreements.
The signature page format is appropriate for organizations where response functions are covered by laws, regulations or executive orders where separate written agreements are not necessary.
* B. On-shift facility licensee responsivities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of response capabilities is available, and the interfaces among various onsite response activities and offsite support response activities are specified.
o B. 8. -Each licensee shall specify the contractor and private organizations who may be requested to provide technical assistance to and augmentation of the emergency organization.
* o B.9. -Each licensee shall identify the services to be provided by local agencies for handling emergencies, e.g., Police, Ambulance, Medical, Hospital, and fire-fighting organizations shall be specified.
The licensee shall provide for transportation and treatment of injured personnel who may a/so be contaminated.
Copies of the arrangements and agreements reached with contractor, private, and local support agencies shall delineate the authorities, responsibilities, and limits on the actions of the contractor, private organization, and local services support groups.
* C. Arrangements for requesting and effectively using assistance resources have been made, arrangements to accommodate State and Local Staff at the licensee's near-site Emergency Operations Facility have been made, and other organizations capable of augmenting the planned response have been identified.
o
* C.4. -Each organization shall identify nuclear and other facilities, organizations or individuals which can be relied upon in an emergency to provide assistance.
Such assistance shall be identified and supported by appropriate letters of agreement.
SSES remains in compliance with this requirement for fire fighting support and maintaining a letter of agreement with Summerhill Fire Company and the other four (4) for the reasons stated above. *
* Applicable sections of the Emergency Plan associated with NUREG-0654 Section II. A, B and C Program Elements:
: 1. -A:1.a Chapter 6, Section 6.0, Appendix A 2. A.3. Appendix A 3. B.8. Chapter 6, Appendix A 4. B.9. Chapter 6, Appendix A 5. C.4. Appendix A 6. Chapter 6, Sections 6.3.3 & 6.3.4 AooendixA There are no additional changes needed to the Emergency Plan sections listed above other than the change to Appendix A. * -Part IV. Evaluation of the Impact of the Proposed Change on the Effectiveness of Emergency Plan Func~ions and Commitments:
-. There is no negative impact of the proposed change on the effectiveness of the Emergency Plan Functions for the reasons stated above. There is no negative impact of the proposed change to commitments for the following reasons: -* The new letter of agreement with Summerhill Fire Company. is virtually identical to the agreement that had existed with the Shickshinny Fire Department.
PLE-0026081 states in part "Summerhill Fire Company agrees to provide firefighting assistance, including personnel and equipment, at the Susquehanna Steam Electric Station as may be required".
* _ There are currently four (4) other Fire Companies (in addition to the Summerhill Fire Company) that have signed the 2018.letters of Agreement and continue to provide fire fighting support services to SSES. ,
* Shickshinny Fire Company is based approximately 5 miles east of the plant and Summerhill Fire Company is based approximately 9 miles north of the plant.
* Reg. Guide 1.219 Revision 1 section 4.12 was reviewed for examples _of changes that could require prior NRG approval and none were found to _be applicable.
Per the guidance in EP-102 Attachments F and G, this change does not constitute a scheme change. The proposed change is not a reduction in effectiveness of the Emergency Plan and therefore does not require prior NRC approval.
* -
Attachment A, 1 OCFR50.54q Screening Form Screening Number: S2018-10-29-01 I Part I. Description of ActiVity Being Reviewed (event or action, or series of actions that may result in a change to the Emergency Plan or affect the implementation of the Emergency Plan). Provide the existing text and the revised text (attaching a mark-up of the existing text with proposed change can be used as an alternative):
Deleted reference to supplemental meteorologlcal tower from section 7.1.1.1 in the SSES Emergency Plan rev 61 per AR-2017-17969 Part II. Activity a Change per Section 3.1.3? 18:1 YES ONO Does the activity constitute a chande per definition 3.1. 3 -An action that Continue to next part 10 CFR 50.54(q) results in modificatlon or addition to, or removal from the SSES Evaluation is NOT Emergency Plan, OR the resources, capabilities and methods ldentified in required.
Enter justification and the plan? complete Part VI. Justification:
Part Ill. Activity Previously Reviewed?
DYES 18:1 NO Is this activity fully bounded by an,NRC approved 10 CFR 50.90 submittal 10 CFR 50.54(q) Continue to next part or Alert and Notification System Design Report (44 CFR 350.14)? Evaluation is NOT required.
Enter If YES, identify bounding source document number/approval reference justification and and ensure the basls for concluding the source document fully bounds the complete Part VI. proposed change is documented below: -* Justification:
/ D Bounding document attached (optional)
Part IV. Editorial Change DYES 18:1 NO Is this activity an editorial or typographical change such as formatting, paragraph 10 CFR 50.54(q) Continue to numbering, spelling, or punctuation that does not change intent per definition 3.1.4? Evaluation is NOT next part required.
Enter justification and complete Part VI. Justification:
Part V. Emergency Planning Element/Function Screen (Associated 10 CFR 50.47(b) planning standard function identified in brackets.)
If this activity affects any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II, then place a check in the appropriate box. 1. Responsibility for emergency response ls assigned.
[1] D 2. The response organization has the staff to respond and to augment staff on a continuing basis (24/7 D staffing) in accordance with the Emergency Plan. f 11 3. The process ensures that on shift emergency response responsibilities are staffed and assigned.
[2] D 4. The process for timely augmentation of on*shift staff is established and maintained.
[2] D 5. Arrangements for requesting and using off site assistance have been made. [3] D 6. State and local staff can be accommodated at the EOF in accordance with the Emergency Plan. [3] n 7. A standard scheme of emergency classification and action levels Is in use. [4] (RSPS) D 8. Procedures for notification of State and local governmental agencies are capable of alerting them of the declared emergency within 15 minutes after declaration of an emergency and providing follow-up D notifications.
[5J (RSPS) Electronic Form EP~102-1, Rev. 4, P~ge 1 of 2 Attachment A, 1 OCFR50.54q Screening Fora:_n, Continued Part V. Emergency Planning Element/Function Screen (cont.) (Associated 10 CFR 50.47(b) planning standard identified in brackets.)
If this activity affects any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II, then place a check in the aooropriate box. 9. Administrative and physical means have been established for alerting and providing prompt D instructions to the public within-the plume exposure pathwav. f51 (RSPS) 10. The public ANS meets the design requirements of FEMA-REP-10, Guide for Evaluation of Alert and Notification Systems for Nuclear Power Plants, or complies with the licensee's FEMA-approved ANS D design report and suooorting FEMA aooroval letter. [5] .(RSPS) 11. Systems are established for prompt communication among principal emergency response D oroanizations.
rBl *-12. Systems are established for prompt communication to emergency response personnel.
[6] D 13. Emergency preparedness information is made available to the public on a periodic basis within the D plume exposure pathway Emergency Planning Zone (EPZ). [7) 14. Coordinated dissemination of public information during emergencies is established.
[7] D 15. Adequate facilities are maintained to support emergency response.
[8] D 16. Adequate equipment is maintained to support emergency response.
[8] .~ 17. Methods, systems, and equipment for assessment of radioactive releases are in use. [9] (RSPS) 121 18. A range of public PARs is available for implementation during emergencies.
[1 O] (RSPS) D 19. Evacuation time estimates for the population located in the plume exposure pathway EPZ are available to support the formulation of PARs and have been provided to State and local governmental D authorities.
r101 (RSPS) 20. Kl is available for implementation as a protective action recommendation in those jurisdictions that D chose to provide Kl to the public [1 OJ 21. A range of protective actions is available for plant emergency workers during emergencies, including D those for hostile action events.[101
: 22. The resources for controlling radiological exposures for emergency workers are established.
[11] D 23. Arrangements are made for medical services for contaminated, injured individuals.
[12] D 24. Plans for recovery and reentry are developed.
[13] D 25. A drill and exercise program (including radiological, medical, health physics and other program areas} D is established.
[14] 26. Drills, exercises, & training evolutions that provide performance opportunities to develop, maintain, & D demonstrate kev skills are assessed via a formal critique process in order to identify weaknesses.
r141 27. Identified weaknesses are corrected.
[14] D 28. Training is provided to emergency responders.
[15] D 29. Responsibility for Emergency Plan development and review is established.
[16] D 30. Planners responsible for Emergency Plan development and maintenance are properly trained. [16] D APPLICABILITY CONCLUSION D If no Part V criteria are checked, a 10 CFR 50.54( q) Evaluation is NOT required; complete Part VI. 121 If any Part V criteria are checked, complete Part VI and perform a 1 O CFR 50.54(q) Evaluation.
Part VI. Signatures:
;i~, Adrian Miron 10/29/18 Preparer Name (Print) (JFG EP109) . _Preparer Signatu~_
Date .. [( /;;,/;?; -:roe /V\~rm (lALJA() * . Reviewer Name (Print) (JFG EP109) ':7ti(ev/efwer
$ignature Date' ti V V Electronic Form EP-102-1, Rev. 4, Page 2 of 2 Attachment B, 10CFR50.54q Evaluation Checklist Evaluation Number: E2018-10-29-03 I Screen Number: S2018-10-29-01 Part I. Description of Proposed Change (Copy applicable information from 50.54(q) screen form Part I or attach a mark-up of the existing text with the proposed change can be used as an alternative):
Deleted reference to supplemental meteorological tower in Nescopeck from section 7 .1.1.1 in the SSES Emergency Plan rev 61 per AR-2017-17969 and all applicable EP implementing procedures (ex. EP-PS-001)
S2018-10-29-01 identified 2 Emergency Planning Elements/Functions potentially associated to this change:
* 16. Adequate equipment is maintained to support emergency response.
[8]
* 17. Methods, systems, and equipment for assessment of radioactive releases are in use. [9] (RSPS) These are associated with 10CFR50.47.b(8) and 10CFR50.47.b(9) requirements, respectively.
Background information on the change:
* The description of 2 supplemental towers, one towards Shickshinny (upriver) and one in Nescopeck (downriver) was introduced in Section 7.1.1.1 of the SSES Emergency Plan Rev 25 (E-Plan) issued on 2/7/97 without NRC approval.
The description of the change was: "This section was changed to describe the current site meteorological tower assignments and provide historical perspective." Other reasons for implementing the change are described in the E-Plan itself, as follows: the "supplemental towers were installed in the river valley near the station to more accurately model the effects of surrounding terrain on atmospheric dispersion and transporf', "Meteorological validation of the Upriver supplemental tower data was terminated in October 1, 1994 due to excessive trend and vegetaUon growth impacting the wind speed and wind direction sensors", and the "Downriver tower is used only to support assessment and restoration efforts in the event there is an accidental release of radioactive material."
* SSES Emergency Plan Rev 39 (E-Plan) issued on 11/20/2001 removed descrlptlon for the Shickshinny (upriver) that was terminated ln 1994. The change was processed without NRC approval.
* The current description of the Nescopeck (downrlver) supplemental tower remained unchanged in Section 7.1.1.1 in all E-Plan revisions up to current rev 61.
* No NRC SERs were sought on Section 7.1.1.1 from rev 24 and the original NRC SER did not include description of the supplemental towers. Electronic Form EP-102-2, Rev. 4, Page 1 of 6 Part II. Evaluation of the Proposed Change for Compliance with the requirements of 10 CFR 50.47(b) and 10 CFR 50 Appendix E: 10 CFR 50.47(b)(8) -Adequate emergency facilities and equipment to support the emergency response are provided and maintained.
By implementing the change described in Part 1, SSES continue to meet 10 CFR 50.47(b)(8) requirements since the requirement of maintaining a principal and backup tower at the site is not altered in the E-Plan and its implementing procedures.
Note that that data from principal or backup site towers are used for dose assessment and those towers are included in the EITER procedure EP-115. Per current dose assessment EP procedures (EP-PS-001-41) data from the Nescopeck tower are used only if the prim.ary and backup site met towers data is not available.
As shown in the E-Plan, "Downriver tower is used only to support assessment and restoration efforts in the event there is an accidental release of radioactive material" and was not meant for supporting the dose assessment function but rather the restoration efforts. Therefore, by maintaining a primary and a backup tower at the SSES site, SSES is in full compliance with this requirement and continue to adequately maintain equipment to support the emergency response.
The restoration effort will be discussed in the next section. No applicable Sections IV.E.1-4, IV.E.8, and IV.G of 10CFR50 Appendix E requirements associated with the change described in Part 1 on Emergency Planning Standard [8] were found. 10 CFR 50.47(b)(9) -Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use. Section IV.E.2 of in 1 OCFR50 Appendix E requirements was found to be applicable to the change described in Part I: Adequate provisions shall be made and described for emergency facilities and equipment, including equipment for determining the magnitude of and for continuously assessing the impact of the release of radioactive materials to the environment.
By implementing the change described in Part 1, SSES continue to meet 10 CFR 50.47(b){9) and Section IV.E.2 of in 1 OCFR50 Appendix E requirements since the requirement for maintaining a principal and backup tower at the site is not altered in the E-Plan and its implementing procedures.
Note that that data from principal or backup site towers is used for dose assessment and those towers are included in the EITER procedure EP-115. Per current dose assessment EP procedures (EP-PS-001-41) data from the Nescopeck tower are used only if the primary and backup site met towers data is not available.
As shown in the E-Plan "Downriver tower is used only to support assessment and restoration efforts in the event there is an accidental release of radioactive material" and was not meant for supporting the dose assessment function but rather the restoration efforts. Therefore, by maintaining a primary and a backup tower at the SSES site, SSES is in full compliance with these requirements and adequately maintains methods and equipment for assessing potential offsite consequences of a radiological emergency condition and determining the magnitude of and continuously assessing the impact of the release of radioactive materials to the environment.
The restoration effort will be discussed in the next section. Therefore, deleting reference to supplemental meteorological tower in Nescopeck from section 7.1.1.1 from Plan and all applicable EP implementing procedures does not affect the requirements in 10CFR50.47(b) and Appendix E to 1 OCFR Part 50.
* Electronic Form EP-102-2, Rev. 4, Page 2 of 6 Part Ill. Evaluation of Emergency Planning Functions, Elements, and Commitments affected by the Proposed Change and the Licensing Basis for those Functions, Elements, and Commitments:
Emergency Planning Standards (Function) for 10 CFR 50.47(b)(8) that is applicable to the change described in Part I is: Adequate equipment is maintained to support emergency response By implementing the change described in Part 1, SSES continue to meet this Planning Standard (PS) requirement since SSES will continue to maintain a principal and backup tower at the site as shown in the Plan and its implementing procedures.
Note that that data from principal or backup tower are used for dose assessment from the site and those towers are included in the EITER procedure EP-115. Per current dose assessment EP procedures (EP-PS-001-41) data from the Nescopeck tower are used only if the primary and backup met towers data at the site is not available.
As shown in the E-Plan, "Downriver tower is used only to support assessment and restoration efforts in the event there is an accidental release of radioactive material" and was not meant for supporting the dose assessment function but rather the restoration efforts. Therefore, by maintaining a primary and a backup tower at the SSES site, SSES is in full compliance with this requirement and continue to adequately maintain equipment to support the emergency response.
Applicabie Program Elements from NUREG-0654 Sections 11.H associated with the Emergency Planning Function [BJ are:
* Each licensee shall identify and establish onsite monitoring systems that are to be used to initiate emergency measures in accordance with Appendix 1, as well as those to be used for conducting assessment.
The equipment shall include: a. geophysical phenomena monitors, (e.g., meteorological, hydrologic, seismic);
* Each licensee shall provide meteorological instrumentation and procedures which satisfy the criteria in Appendix 2, and provisions to obtain representative current meteorological information from other sources. Applicable Program Elements from NUREG-0654 Appendix 2, Meteorological Criteria For Emergency Preparedness At Operating Nuclear Power Plants, associated with change described in Part I are: 10 CFR Pait 50.47 requires that the Emergency Plan shall provide "(A)dequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition . . . " The basic functions needed to comply with the meteorological aspects of these requirements are: 1. A capability for making meteorological measurements.
: 2. A capability for making near real-time predictions of the atmospheric effluent transporl and diffusion.
: 3. A capability for remote interrogation of the atmospheric measurements and predictions by appropriate organizations.
Meteorological Measurements . The emergency facilities and equipment as stated in Appendix E to 10 CFR Part 50 shall include "(E)quipment for determining the magnitude of and for continuously assessing the impact of the release of radioactive materials to the environment." To address this requirement, in parl, the nuclear power plant operator shall have meteorological measurements from primary and backup systems. Each site with an operating nuclear power plant shall have a primary meteorological measurements system. The primary system shall produce current and record historical focal meteorological data. These data will provide a means to estimate the dispersion of radioactive material due to accidental radioactive releases to the atmosphere by the plant. .... Each site with an operating nuclear power plantshalf have a viable backup meteorological measurements system. The backup system shall provide meteorological information when the primary system is out of service and, thus, assurance that basic meteorological information is available during and immediately following an
* accidental airborne radioactivity release. Electronic Form EP-102-2, Rev. 4, Page 3 of 6 By implementing the change described in Part 1, SSES continue to meet this guidance since SSES will continue to maintain a principal and backup tower af the site as shown in the E-Plan and its implementing procedures.
Note that that data from principal or backup site met towers is used for dose assessment and those towers are included in the EITER procedure EP-115. Per current dose assessment EP procedures PS-001-41) data from the Nescopeck tower are used only if the primary and backup met towers data at the site is not available.
As shown in the E-Plan "Downriver tower is used only to support assessment and .restoration efforts in the event there is an accidental release of radioactive material" and was not meant for supporting the dose assessment function but rather the restoration efforts. Therefore, by maintaining a primary and a backup tower at the SSES site, SSES is in full compliance with this guidance and continue to adequately maintain equipment to support the emergency response.
In addition, provisions to "obtain representative current meteorological inform_ation from other sources" are described in Section B of EP-PS-001-41 form by contacting National Weather'Service (NWS) Emergency Meteorological Support Office, using www.weather.com or ABS Consulting (during working hours). Therefore, by implementing this change, this criterion is also met. Emergency Planning Standards (Function) for 10 CFR 50.47(b)(9) that is applicable to the change described in Part I is: Methods, systems, and equipment for assessment of radioactive releases are in use. By implementing the change described in Part 1, SSES continue to meet this PS requirement since SSES will continue to maintain a principal and backup tower at the site as shown in the E-Plan and its implementing procedures.
Note that that data from principal or backup site met towers is used for dose assessment and those towers are included in the EITER procedure EP-115. Per current dose assessment EP procedures PS-001-41) data from the Nescopeck tower are used only if the primary and backup met towers data at the site is not available.
As shown in the E-Plan, "Downriver tower is used only to support assessment and restoration efforts in the event there is an accidental release of radioactive material" and was not meant for supporting the dose assessment function but rather the restoration efforts. Therefore, by maintaining a primary and a backup tower at the SSES site, SSES is in full compliance with this requrrement and continue to adequately maintain methods and equipment to support the assessment of radioactive releases.
Applicable Program Elements from NUREG-0654 Sections II.I associated with the Emergency Planning Function [9] are:
* Each licensee shall have the capability of acquiring and evaluating meteorological information sufficient to meet the criteria of Appendix 2. There shall be provisions for access to meteorological information by at least the near site Emergency Operations Facility, the Technical Support Center, the Control Room and an offsite NRG center ..... As discussed above, SSES was found in compliance with guidance from Appendix 2 of NU REG 0654. By implementing the change described in Part 1, SSES continue to meet this guidance since SSES will continue to maintain a principal and backup tower at the site as shown in the E-Plan and its implementing procedures.
Note that that data from principal or backup site met tower is used for dose assessment and those towers are included in the EITER procedure EP-115. The primary and backup met tower data continue to be available in the CR, TSC, Alt TSC and EOF via the plant computer system. Per current dose assessment EP procedures (EP-PS-001-41) data from the Nescopeck tower are used only if the primary and backup met towers data at the site is not available.
As shown in the E-Plan, "Downriver tower is used only to support assessment and restoration efforts in the event there is an accidental release of radioactive material" and was not meant for supporting the dose assessment function but rather the restoration efforts. Therefore, by maintaining a primary and a backup tower at the SSES site, SSES is in full compliance with this guidance and continue to adequately maintain methods and equipment to support the assessment of radioactive releases.
Restoration efforts are described in Section 4.2.3, 6.0 (Phase IV), 6.5 and Figure 6.6. In addition, EP-00-003, Termination and Restoration, and EP-PS-248, EOF Environmental Sampling Director, are used in restoration efforts. The Nescopeck meteorological tower is not mentioned in any of these sections in the E-Plan and implementing procedures.
Electronic Form EP-102-2, Rev. 4, Page 4 of 6 In addition, it is not clear how additional met data in Nescopeck would be used to support assessment and restoration efforts. As specified in Section 6.4.3 of the E-Plan, "If the situation necessitates additional technical assistance, DOE can set up and staff a Federal Radiological Monitoring and Assessment Center (FRMAC) in the vicinity of SSES. A FRMAC, which draws DOE resources and personnel from its Nevada Operations Office, can be operational within about 24 hours. The location of such a center would be selected based on actual radiological deposition patterns.
The Federal FRMAC team is initially managed by DOE, with personnel also provided by NRC, EPA, USDA, HHS, and other agencies.
The State and Susquehanna would assign personnel to the FRMAC to coordinate monitoring activity." Once set up, FRMAC's mission will be to help decision makers in the Intermediary Phase of the accident, i.e., once the releases are under control and different Protective Action Guidance are applicable in accordance with EPA 400 guidance.
As specified in Section 1.1 in DOE/NV/25946-980, FRMAC Operations Manual, ''FRMAC is responsible for coordinating all environmental radiological monitoring, sampling and assessment activities for the response" and thus, regardless of the wind direction at the site or elsewhere, FRMAC will produce an "assessment of the affected areas" around SSES. Therefore, the Nescopeck met tower data can be easily disregarded by real data m~asured after the release is under control, in accordance with SSES E-Plan and implementing procedures, as well as by taking advantage of modern resources and capabilities of the Federal Government.
Applicable guidance for the change described in Part from Reg. Guide 1.219 Revision 1 sections 4.8 and 4.9 are: *. 4.8.c(1)(a)
-a reduction in the existing reliability or redundancy of data acquisition, display, and analysis equipment provided in the ERFs; and 4.9.c(1)(a)
-a change that reduces the availability of meteorological data in ERFs where dose assessments are performed and PAR decisions are made None of this guidance are applicable to the change described in Part I because the SSES will continue to maintain 2 met towers onsite and dose assessment is based on these readings in each ERF. Thus, the redundancy and availability of data needed for dose assessment is satisfied.
In addition, as discussed below the supplemental met tower data is not redundant to the onsite met towers. Therefore, both criteria above continue to be satisfied by implementing the change described in Part 1. As discussed in Part I, Background Information section, the descriptions of the upriver and down river supplemental met towers were included in the E-Plan Rev 25 without NRC approval.
Subsequently, the upriver met tower description was removed without N RC approval in Rev 39 of the E-Plan. No NRG SER addressed section 7.1.1.1 from rev 25 to rev 61 and th~ original NRC SER did not include description of the supplemental meteorological towers.
Therefore, removing the description of the downriver met tower does not constitute a ficensing or commitment violation.
It can be concluded that, removing Nescopeck met tower from the E-Plan and all applicable EP implementing procedures does not affect SSES Emergency Planning Functions, Elements, Commitments and Licensing Basis. Part IV. Evaluation of the Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:
As observed several times, Nescopeck met tower readings (wind speed and direction) do not always coincide with the primary and backup meteorological towers located on site. This is because the Nescopeck met tower is located 3.6 miles away from the site and because of complex river basin effects. Therefore, using this data instead of the primary or backup met towers during the dose assessment process in the initial phase of an accident would be less than desirable and a factor of confusion for ERO. Therefore, eliminating the Nescopeck tower from the dose assessment procedures could only increase the effectiveness of the E-Plan. Electronic Form EP-102-2, Rev. 4, Page 5 of 6 Part V. Evaluation Conclusion
: 2. Does the proposed change maintain the effectiveness of the Emergency Plan (i.e., no reduction in effectiveness
? 3. Does the pro osed change constitute an emergenc action level scheme change? ~YES0NO ~YES0NO 0YES~NO If questions 1 or 2 are answered NO, or question 3 answered YES, obtain prior NRC approval under provisions of . 10 CFR 50.90. If questions 1 and 2 are answered YES, and question 3 answered NO, implement applicable change rocess es. Part VI. Signatures:
Adrian Miron 10/29/18 Preparer Name (Print) (JFG EP109) Date 1&deg;ofv Mi1Tdl Reviewer Name (Print) (JFG EP109) Electronic Form EP-102-2, Rev. 4, Page 6 of 6}}

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