Text

Emergency Plan Revision 67 (PLA-8077)
	ML23361A013
Person / Time
Site:	Susquehanna
Issue date:	12/27/2023
From:	Casulli E; Susquehanna, Talen Energy
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk
References
	PLA-8077
	Download: ML23361A013 (1)
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{{#Wiki_filter:TALEN~ Edward Casulli Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3795 Fax 570.542.1504 Edward.Casulli@TalenEnergy.cum ENERGY December 27, 2023 Attn: Document Control Desk 10 CFR 50.54(q) U.S. Nuclear Regulatory Commission 10 CFR 72.44(f) Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION EMERGENCY PLAN REVISION 67 Docket Nos. 50-387, 50-388 PLA- 8077 and 72-28 Pursuant to 10 CFR 50.54(q) and 10 CFR 72.44(f), Susquehanna Steam Electric Station (SSES) hereby submits Revision 67 to the Emergency Plan. This revision contains changes that did not require NRC approval. In accordance with 10 CFR 50.54(q)(3), Revision 67 to the Emergency Plan does not result in a reduction of the effectiveness of the plan. The plan, as changed, continues to satisfy the applicable requirements of 10 CFR 50.47(b) and Appendix E to 10 CFR 50. Revision 67 of the Emergency Plan is included in Enclosure 1. Changes are described on page 3 of Enclosure 1. Pursuant to 10 CR 50.54(q), Enclosure 2 contains a report of each change made. There are no new or revised regulatory commitments contained in this submittal. Should you have any questions regarding this submittal, please contact Ms. Melisa Krick, Manager - Nuclear Regulatory Affairs, at (570) 542-1818. E. Casulli - SSES Emergency Plan Revision 67 - 10 CFR 50.54(q) Screens and Evaluations Copy: NRC Region I Mr. C. Highley, NRC Senior Resident Inspector Ms. A. Klett, NRC Project Manager Mr. M. Shields, PA DEP/BRP Director, Division of Fuel Management

Enclosure 1 to PLA-8077 SSES Emergency Plan Revision 67

Emergency Plan, Rev. 67, Page 1 of 166 SUSQUEHANNA NUCLEAR, LLC SUSQUEHANNA STEAM ELECTRIC STATION EMERGENCY PLAN REVISION 67 DATE: 12/11/2023 PORC MEETING: 23-11-09

Emergency Plan, Rev. 67, Page 2 of 166 SUSQUEHANNA NUCLEAR, LLC SUSQUEHANNA STEAM ELECTRIC STATION TEAM

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THIS DOCUMENT HAS BEEN UPDATED TO INCLUDE REVISIONS THROUGH 66

Emergency Plan, Rev. 67, Page 3 of 166 AFFECTED PAGES OR SECTIONS NOTE: 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. This revision takes credit for the 2023 Annual Emergency Plan Review per AR-2023-00273.

(S2023-05-24-01)

2. Removed Security/ from title of Manager-Security/Emergency Preparedness throughout the document per DPA-07-DI-2023-02751. (S2023-05-24-01)

3. Changed response pagers to Notification System in section 6.0, Phase I h) step. (S / E2023-08-01-01)

4. Changed section 7.1.1.3 and Appendices B and C and deleted MIDAS from Figure 8.2 in support of URI implementation at SSES per DPA-13-DI-2022-01144. (S / E2023-02-02-01)

5. Replaced Figure 8.1 with the updated C-2532 Sheet 1 with the new site boundary per ACT-01-CR-2023-02344. (S / E2022-09-08-01)

6. Deleted reference to Hunlock Creek Ambulance Association from Appendix A per DPA-04-DI-2023-01542. (S /E2023-05-04-01)

7. Deleted FSAR Figure 13.1-3 from Section A in Appendix J per DI-2023-02233. (S2023-05-24-01)

8. Added EP-00-005, Termination and Restoration procedure to Appendix J Sections M.1 and M.2 per DI-2023-02233. (S2023-05-24-01)

9. Corrected typo in Appendix J section M.4 per DI-2023-02233. (S2023-05-24-01)

Emergency Plan, Rev. 67, Page 4 of 166 TABLE OF CONTENTS 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 43 6.1 NORMAL OPERATING ORGANIZATION 45 6.2 ON-SITE EMERGENCY ORGANIZATION - (PHASE II) 46 6.3 OFF-SITE RESOURCES AND ACTIVITIES - (PHASE III) 52 6.4 COORDINATION WITH PARTICIPATING GOVERNMENT AGENCIES 57 6.5 RESTORATION 60 7.0 EMERGENCY MEASURES 71 7.1 ASSESSMENT ACTIONS FOR ALL EMERGENCY CLASSIFICATIONS 71 7.2 CORRECTIVE ACTIONS 76 7.3 PROTECTIVE ACTIONS 76 7.4 AID TO AFFECTED PERSONNEL 80 8.0 EMERGENCY FACILITIES AND EQUIPMENT 89 8.1 ON-SITE EMERGENCY CENTERS 89 8.2 SUSQUEHANNA OFF-SITE EMERGENCY CENTERS 97 8.3 COUNTY AND STATE EMERGENCY CENTERS 100 8.4 ASSESSMENT CAPABILITIES 100 8.5 PROTECTIVE FACILITIES 101 8.6 ADDITIONAL COMMUNICATIONS SYSTEMS 102 8.7 ON-SITE FIRST AID AND MEDICAL FACILITIES 102 8.8 DAMAGE CONTROL EQUIPMENT 103 8.9 INFORMATION SYSTEMS 103 9.0 MAINTAINING EMERGENCY PREPAREDNESS 110 9.1 ORGANIZATIONAL PREPAREDNESS 110 9.2 REVIEW AND UPDATING 115 9.3 MAINTENANCE AND INVENTORY OF EMERGENCY EQUIPMENT/ SUPPLIES 116 9.4 PUBLIC EDUCATION AND INFORMATION 116 10.0 APPENDICES A LETTERS OF AGREEMENT 120 B WIND ROSES, DOSE/DISTANCE PLOTS AND JOINT FREQUENCY 122 DISTRIBUTION C SSES EMERGENCY PLAN POSITION SPECIFIC PROCEDURES (TYPICAL) 126 D EQUIPMENT INFORMATION LISTINGS 128 E SUSQUEHANNA NUCLEAR, LLC POLICY STATEMENT 144 F DEVIATIONS to NEI 99-01, Rev 6 146 G SSES EVACUATION TIME ESTIMATES 148 H DOWNSTREAM SUSQUEHANNA RIVER WATER USAGE 150 I POPULATION UPDATE FOR SSES EMERGENCY PLANNING ZONE 153 J NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS 155 REFERENCE TO SSES EMERGENCY PLAN K ON-SHIFT STAFFING ANALYSIS 165 Page 1 of 3

Emergency Plan, Rev. 67, Page 5 of 166 LISTING OF TABLES TABLE TITLE PAGE 5.1 TABLE DELETED N/A 5.2 EMERGENCY ACTIONS BASED ON CLASSIFICATION 36 6.1 STATION EMERGENCY PLAN MINIMUM STAFFING REQUIREMENTS 62 6.2 ADDITIONAL ASSISTANCE FROM OUTSIDE SUSQUEHANNA NUCLEAR, LLC 65 7.1

SUMMARY

OF IMMEDIATE NOTIFICATION AND RESPONSE FOR ALL 80 CLASSIFICATIONS 7.2 EMERGENCY EXPOSURE CRITERIA 82 7.3 PROTECTIVE ACTION RECOMMENDATIONS 85 8.1 RELATIONSHIP OF THE PRIMARY PARAMETER, SECONDARY DISPLAY, AND 104 ALGORITHMS ON SPDS 9.1 TRAINING OF SUSQUEHANNA SES EMERGENCY RESPONSE PERSONNEL 116 Page 2 of 3

Emergency Plan, Rev. 67, Page 6 of 166 LISTING OF FIGURES 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 66 6.3 OSC ORGANIZATION 67 6.4 EOF ORGANIZATION 68 6.6 LONG TERM RESTORATION ORGANIZATION 69 6.7 COMMUNICATION INTERFACES WITH OFFSITE AGENCIES 70 8.1 MAP OF THE SUSQUEHANNA SES EMERGENCY FACILITIES 106 8.2 TECHNICAL SUPPORT CENTER FLOOR PLAN 107 8.3 EMERGENCY OPERATIONS FACILITY/JOINT INFORMATION CENTER FLOOR 108 PLAN 8.4 SIREN LOCATION 109 Page 3 of 3

Emergency Plan, Rev. 67, Page 7 of 166 1.0 DEFINITIONS

1. ACCIDENT - an unforeseen and unintentional event which may result in an emergency.

2. ACTIVATE - an emergency response facility has sufficient staffing to perform required functions and the 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.

3. 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.

4. 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.

5. ANNUAL - occurring within calendar year starting January 1 and ending December 31.

6. 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.

7. 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.

8. BIENNIAL EXERCISE - NRC/DHS-FEMA exercise performed on alternate years, to be completed within the calendar year scheduled.

9. BIWEEKLY - occurring on alternate weeks, within the 7-day week.

10. BOMB - refers to an explosive device suspected of having sufficient force to damage plant systems or structures.

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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. An 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. CDE - 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) and Multipurpose Canister (MPC).

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 - the Talen Management group which determines major policy commitments for the company. The Corporate Leadership 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.

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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:

x Notification of Unusual Event (NOUE) - synonymous with Unusual Event (UE) x Alert x Site Area Emergency (SAE) x 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.

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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 10 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 instructions, 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 terms of dose commitment: 1 Rem TEDE or 5 Rem CDE 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.

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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. 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.

47. 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.

48. HOSTAGE - is a person(s) held as leverage against the station to ensure that demands will be met by the station.

49. 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.

50. 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).

51. 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.

52. 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).

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53. 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.

54. 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.

55. JOINT INFORMATION CENTER - the designated location from which news bulletins, press briefings and other media interfacing can be provided.

56. LDE - Lens Dose Equivalent; the external exposure to the lens of the eye.

57. 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.

58. LUZERNE COUNTY EMERGENCY MANAGEMENT AGENCY (LCEMA) - the host 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 hours 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.

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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. PRIMARY SYSTEM -The pipes, valves, and other equipment which connect directly to the RPV such that a reduction in RPV pressure will effect a decrease in the steam or water being discharged through an unisolated break in the system.

74. PROTECTED AREA - An area encompassed by Physical Barriers and to which access is controlled.

75. 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.

76. 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.

77. PROTECTIVE ACTIONS - those emergency measures taken for the purpose of preventing or minimizing radiological exposures.

78. QUARTERLY - occurring during the calendar quarter.

79. RADIATION DOSE - the quantity of radiation absorbed by the body or any portion of the body.

80. 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.

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81. RADIOACTIVE MATERIAL - any solid, liquid, or gas which emits radiation spontaneously.

82. 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.

83. 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 portions of LLRWHF.

84. 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).

85. RADIOLOGICALLY CONTROLLED AREA EVACUATION - evacuation of nonessential individuals from some or all of the Radiologically Controlled Area.

86. RECOVERY ACTIONS - those actions taken after the emergency to restore the plant as nearly as possible to its pre-emergency condition.

87. RECOVERY MANAGER - the individual responsible for the management of emergency response activities in the EOF during an emergency at the Susquehanna Steam Electric Station.

88. REFUELING PATHWAY - The reactor refueling cavity, spent fuel pool and fuel transfer canal comprise the refueling pathway.

89. REM (Acronym for roentgen equivalent man) - a unit of measure of radiation dose in biological tissue.

90. 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.

91. RESTORE - Take the appropriate action required to return the value of an identified parameter to the applicable limits.

92. 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.

93. SDE - Shallow Dose Equivalent; external exposure of the skin or extremity which is measured at 0.007 cm in tissue.

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94. 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.

95. 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.

96. 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 10CFR50.2):

Those structures, systems and components that are relied 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 exposures.

97. 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.

98. 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.

99. 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 in the emergency plan. Both terms designate the same individual.

100. 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%. 101. 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 failure 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. 102. 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. 67, Page 16 of 166 103. SITE EVACUATION - evacuation of all non-essential personnel from the Exclusion Area. 104. STATE - the Commonwealth of Pennsylvania. 105. 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. 106. 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. 107. 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. 108. 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. 109. THYROID DOSE - radiation exposure to the thyroid resulting from an intake of radioactive materials. 110. TRANSMISSION POWER DISPATCHER - individual manning the transmission and distribution system for PPL Corporation. 111. UNISOLABLE - An open or breached system line that cannot be isolated, remotely or locally. x The term UNISOLABLE also includes any decision by plant staff or procedure direction to not isolate a primary system. x Normal leakage past a closed isolation valve is not considered UNISOLABLE leakage 112. 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. 113. 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 indicators operability, the conditions existence, or the reports accuracy is removed. Implicit in this definition is the need for timely assessment. Page 10 of 11

Emergency Plan, Rev. 67, Page 17 of 166 114. 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. 115. 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: SCC, Control Structure, Diesel Generator Buildings, ESSW Pump House, Spray Pond and Reactor Buildings. 116. WHOLE BODY EXPOSURE - direct radiation exposure to the body from external sources. Page 11 of 11

Emergency Plan, Rev. 67, Page 18 of 166 2.0 ACRONYMS 2.1 ANS - Alert Notification System 2.2 ARI - Alternate Rod Insertion 2.3 ARM - Area Radiation Monitors 2.4 CAM - Continuous Air Monitors 2.5 CAS - Central Alarm Station 2.6 CCEMA - Columbia County Emergency Management Agency 2.7 CEDE - Committed Effective Dose Equivalent 2.8 CR - Control Room 2.9 CREOASS - Control Room Emergency Outside Air Supply System 2.10 CSAR Certified Safety Analysis Report 2.11 CTN - Centrex Telephone Network 2.12 DAC - Derived Air Concentration 2.13 DCS - Document Control Services 2.14 DEP/BRP - Department of Environmental Protection/Bureau of Radiological Protection 2.15 DHS - FEMA Department of Homeland Security - Federal Emergency Management Agency 2.16 DOE - U.S. Department of Energy 2.17 EAL - Emergency Action Levels 2.18 EAS - Emergency Alert System 2.19 ECCS - Emergency Core Cooling Systems 2.20 ED - Emergency Director at Susquehanna SES 2.21 EDE - Effective Dose Equivalent 2.22 EMA - Emergency Management Agency 2.23 EMC - Emergency Management Coordinator (Municipality) 2.24 EOC - Emergency Operations Center 2.25 EOF - Emergency Operations Facility 2.26 EP - Emergency Preparedness 2.27 EPA - Environmental Protection Agency 2.28 EP-PS - Emergency Plan Position Specific Procedures 2.29 EPZ - Emergency Planning Zone 2.30 ERDS - Emergency Response Data System 2.31 ERF - Emergency Response Facility 2.32 ERO Emergency Response Organization for SSES 2.33 ETN - Electronic Tandem Network 2.34 FPC - Fuel Pool Cooling 2.35 FRC - Federal Response Coordinator 2.36 FRERP - Federal Radiological Emergency Response Plan 2.37 FRMAC - Federal Radiological Monitoring and Assessment Center 2.38 FSAR - Susquehanna SES Final Safety Analysis Report, Units 1 and 2 2.39 FTS - Federal Telecommunications System 2.40 HHS - Health and Human Services 2.41 HPCI - High Pressure Coolant Injection System 2.42 JIC - Joint Information Center 2.43 LCEMA - Luzerne County Emergency Management Agency 2.44 LCO - Limiting Condition for Operation 2.45 LER - License Event Report Page 1 of 2

Emergency Plan, Rev. 67, Page 19 of 166 2.46 LLRWHF - Low Level Radwaste Holding Facility 2.47 LOCA - Loss of Coolant Accident 2.48 MOCA - Monitored Owner Controlled Area 2.49 MSIV - Main Steam Isolation Valve 2.50 MSL - Main Steam Line 2.51 NEP - Nuclear Emergency Planning 2.52 NRC - Nuclear Regulatory Commission 2.53 NRP - National Response Plan 2.54 NSRB Nuclear Safety Review Board 2.55 NSSS - Nuclear Steam Supply System 2.56 ODCM - Offsite Dose Calculation Manual 2.57 ORO Offsite Response Organization 2.58 OSC - Operations Support Center 2.59 PAGS - Protective Action Guides from EPA 2.60 PEMA - Pennsylvania Emergency Management Agency 2.61 PORC - Plant Operations Review Committee 2.62 PPL - PPL Corporation 2.63 PSP - Pennsylvania State Police 2.64 RCA - Radiologically Controlled Area 2.65 RCIC - Reactor Core Isolation Cooling 2.66 RDAS - Remote Data Analysis System 2.67 RHR - Residual Heat Removal 2.68 RPS - Reactor Protection System 2.69 RX - Reactor 2.70 SAS - Secondary Alarm Station 2.71 SDE - Shallow Dose Equivalent 2.72 SDS - Satellite Display System 2.73 SEIC - Susquehanna Energy Information Center 2.74 SGTS - Standby Gas Treatment System 2.75 SLC - Standby Liquid Control 2.76 SOCA - Security Owner Controlled Area 2.77 SPDS - Safety Parameter Display System 2.78 SSE - Safe Shutdown Earthquake 2.79 SSES Susquehanna Steam Electric Station 2.80 SSES URI Unified RASCAL Interface customized for SSES 2.81 Susquehanna Susquehanna Nuclear, LLC (subsidiary company of Talen Energy Corporation) 2.82 TEDE - Total Effective Dose Equivalent 2.83 TR - Temperature Recorder 2.84 TSC - Technical Support Center 2.85 UMC - Unit Monitoring Console (PCS) 2.86 UPS - Uninterruptible Power Supply 2.87 USDA - United States Department of Agriculture 2.88 VERMS Vent Effluent Radiation Monitoring System Page 2 of 2

Emergency Plan, Rev. 67, Page 20 of 166

3.0 REFERENCES

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 Revision 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 NUREG 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). 3.10 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 10CFR 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. 3.20 Susquehanna Nuclear, LLC Training and Qualification Plan. Page 1 of 2

Emergency Plan, Rev. 67, Page 21 of 166 3.21 Regulatory Guide 1.101 Emergency Planning and Preparedness for Nuclear Power Reactors (Revision 3, August 1992). 3.22 Regulatory Issue Summary 2004-15, Supplement 1, Emergency Preparedness Issues: Post-9/11. 3.23 EC 690275/AR 850156, Extended Power Uprate (EPU) Impact Evaluation. 3.24 NEI 03-12, Template for Security Plan and Training and Qualification Plan, June 2004. 3.25 PLA-7823, Susquehanna Steam Electric Station Proposed Amendment to Licenses NPF-14 and NPF-22: Revision to the Dose Consequence Analysis for a Loss Of Coolant Accident. 3.26 NRC 2020-0025, "Issuance of Amendment Nos. 276 and 258 Re: Revise Technical Specification 5.5.2 to Modify the Design-Basis Loss-of-Coolant Accident Analysis (EPID L-2020-LLA-0000)," dated October 8, 2020 (ADAMS Accession No. ML20199G749). Page 2 of 2

Emergency Plan, Rev. 67, Page 22 of 166 4.0 SCOPE AND CONTENTS 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 measures 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 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. 4.2.2 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. Page 1 of 4

Emergency Plan, Rev. 67, Page 23 of 166 4.2.3 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 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. 4.2.5 Emergency Training 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 2 of 4

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Emergency Plan, Rev. 67, Page 26 of 166 5.0 EMERGENCY CONDITIONS 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. Event declaration occurs within 15 minutes of having necessary information available in accordance with 10CFR50 Appendix E IV.C. 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 EP-RM-004, EAL Classification Basis. This document is a programmatic description of SSES classification system that demonstrates how an initiating condition leads directly to the appropriate emergency classification based on the magnitude of the event and continues to be subject to the 10 CFR 50.54(q) change process. 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 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, S, H, E and C in EP-RM-004, EAL Classification Basis. 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. Page 1 of 10

Emergency Plan, Rev. 67, Page 27 of 166 5.1.2 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. Conditions that constitute an Alert classification are outlined in Tables R, F, S, H and C in EP-RM-004, EAL Classification Basis. The emergency actions that will be taken by Susquehanna and offsite agencies for an Alert 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 of monitoring teams if a radioactive release is involved. 5.1.3 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 failure 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. Conditions that constitute a Site Area Emergency are outlined in Tables R, F, S, H and C in EP-RM-004, EAL Classification Basis. The emergency actions taken by Susquehanna and offsite agencies for a Site Area Emergency are listed in Table 5.2. In general, the actions will be similar to the actions taken for an Alert with increased emphasis on information dissemination, more senior technical and management staff in the emergency response facilities, and additional field radiological monitoring. Page 2 of 10

Emergency Plan, Rev. 67, Page 28 of 166 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 in EP-RM-004, EAL Classification Basis. 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 in EP-RM-004, EAL Classification Basis 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. Page 3 of 10

Emergency Plan, Rev. 67, Page 29 of 166 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. Initial assessment of this accident, performed by the Control Room Personnel under the direction of the ED includes evaluation of radiation levels. Data are 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, H and C in EP-RM-004, EAL Classification Basis b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation 5.2.2 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, H and C in EP-RM-004, EAL Classification Basis b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation Page 4 of 10

Emergency Plan, Rev. 67, Page 30 of 166 5.2.3 Main Steam Line Break 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 and releases steam until complete closure of the MSIVs. Noble gases and radioiodines in the coolant are assumed to be released directly to the environment. 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, H and C in EP-RM-004, EAL Classification Basis b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation 5.2.4 Instrument Line Break 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. Page 5 of 10

Emergency Plan, Rev. 67, Page 31 of 166 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 I-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 remaining 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, H and C in EP-RM-004, EAL Classification Basis b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation 5.2.5 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, H and C in EP-RM-004, EAL Classification Basis b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation Page 6 of 10

Emergency Plan, Rev. 67, Page 32 of 166 5.2.6 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 include: a) Evaluate Emergency Action Levels per Tables R, F, S, H and C in EP-RM-004, EAL Classification Basis b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation 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, H and C in EP-RM-004, EAL Classification Basis b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation Page 7 of 10

Emergency Plan, Rev. 67, Page 33 of 166 5.2.8 Liquid Radwaste Failure 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, H and C in EP-RM-004, EAL Classification Basis b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation 5.2.9 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. 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 the 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, H and C in EP-RM-004, EAL Classification Basis b) Declare the appropriate classification as warranted Page 8 of 10

Emergency Plan, Rev. 67, Page 34 of 166 5.2.10 Feedwater Line Break - Outside Containment This accident is described in 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 in EP-RM-004, EAL Classification Basis b) Declare the appropriate classification as warranted c) Implement Radiologically Controlled Area Evacuation. Page 9 of 10

Emergency Plan, Rev. 67, Page 35 of 166 5.2.11 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: x Reduced Storage Module air inlet and outlet shielding x Natural phenomena events as defined in the CSAR x Accidental transfer cask drop with loss of neutron shield x Lightning effects x Debris blockage of Storage Module air inlet and outlet opening x Postulated Dry Cask Storage leakage x 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, R and H in EP-RM-004, EAL Classification Basis. b) Declaration of a Notification of Unusual Event as warranted. c) Implement recovery actions. Page 10 of 10

Emergency Plan, Rev. 67, Page 36 of 166 TABLE 5.2 EMERGENCY ACTIONS BASED ON CLASSIFICATION Page 1 of 7 Classification Licensee Actions Off-Site Agency Actions

1. Notification of Unusual Event 1. Promptly notify plant emergency 1. Notify key officials and public if deemed management personnel of event particulars necessary by county/state Emergency Class Description and an assessment of safety significance of Director.

the event. Events are in process or have and occurred which indicate a and potential degradation of the level 2. Provide assistance if requested and able. of safety of the plant or indicate a 2. Notify PEMA, LCEMA, CCEMA and NRC of security threat to facility "Unusual Event". protection has been initiated. No releases of radioactive material and requiring offsite response or monitoring are expected unless 3. Closeout event with verbal summary to further degradation of SAFETY offsite authorities (PEMA, LCEMA, CCEMA, SYSTEMS occurs. and NRC) followed by written summary if required by 10 CFR 50.73. Purpose or Purpose of offsite notification is to (1) assure that the first step in 4. Escalate to higher emergency classification if any response later found to be appropriate. 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. Page 1 of 7

Emergency Plan, Rev. 67, Page 37 of 166 TABLE 5.2 EMERGENCY ACTIONS BASED ON CLASSIFICATION Page 2 of 7 Classification Licensee Actions Off-Site Agency Actions

2. Alert 1. Promptly notify state/local authorities and 1. Provide assistance, if requested 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 (ERDS) within one hour. or status information. and 6. Escalate to a more severe class. Page 2 of 7

Emergency Plan, Rev. 67, Page 38 of 166 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.

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Emergency Plan, Rev. 67, Page 39 of 166 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. 67, Page 40 of 166 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.

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Emergency Plan, Rev. 67, Page 41 of 166 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. 67, Page 42 of 166 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.

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Emergency Plan, Rev. 67, Page 43 of 166 6.0 ORGANIZATIONAL CONTROL OF EMERGENCIES 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. 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 Notification System 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. Page 1 of 19

Emergency Plan, Rev. 67, Page 44 of 166 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 alternate TSC may exceed 60 minutes. Phase III - 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 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. Functional operation will include: x Management of overall emergency response x Coordination of radiological and environmental assessment Page 2 of 19

Emergency Plan, Rev. 67, Page 45 of 166 x Determination of recommended protective actions x Communications x 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 1 NRC Communicator Fire Brigade response personnel per Technical Requirements Manual Security Personnel as specified in the SSES Security Plan 15 Total The above on-shift staffing has been evaluated and determined to be adequate in accordance with 10CFR50 Appendix E section IV.A.9 (Reference Appendix K). 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. 67, Page 46 of 166 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 plan. 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.

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Emergency Plan, Rev. 67, Page 47 of 166

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 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.

l. 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 personnel.

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Emergency Plan, Rev. 67, Page 48 of 166 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 Communicators.

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.

6.2.4 TSC Emergency Plan Communicator (Table 6.1 60 Minute Response, Figure 6.2)

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.

6.2.5 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.

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Emergency Plan, Rev. 67, Page 49 of 166

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 KI and emergency dose extensions.

6.2.6 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.

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Emergency Plan, Rev. 67, Page 50 of 166 6.2.7 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:

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.

6.2.9 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.

6.2.10 RP Specialist - RAD Assessment Staff (Table 6.1 60 Minute Response, Figure 6.3) Responsibilities:

a. Determine and maintain up-to-date status for radiological conditions in the plant.

b. Assess on-site habitability.

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Emergency Plan, Rev. 67, Page 51 of 166

c. Provide guidance and brief teams on radiological and ALARA considerations.

d. Monitor in-plant team exposures.

6.2.11 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. 6.2.12 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/I&C actions. (Electrical Engineer) 6.2.13 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 I&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. 6.2.14 Non - Operations Support Personnel (Table 6.1 90 Minute Response, Figure 6.3) Four RP Technicians and One (Electrical Maintenance worker or I&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. 67, Page 52 of 166 6.3 OFF-SITE RESOURCES AND ACTIVITIES (PHASE III) 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: x Management of overall emergency response x Coordination of radiological and environmental assessment x Determination of recommended protective actions x Communications x 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 the EOF has activated. Page 10 of 19

Emergency Plan, Rev. 67, Page 53 of 166 6.3.1 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.

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Emergency Plan, Rev. 67, Page 54 of 166

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).

l. 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 technical 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 12 of 19

Emergency Plan, Rev. 67, Page 55 of 166

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 KI 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)

Page 13 of 19

Emergency Plan, Rev. 67, Page 56 of 166 6.3.2 Joint Information Center 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 bulletins, 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 press briefings.

e. Manage rumor control.

f. Establish interfaces and coordinates news bulletins with the federal and state agencies in the JIC.

6.3.3 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 condition 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. 6.3.4 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. Page 14 of 19

Emergency Plan, Rev. 67, Page 57 of 166 6.4 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: x Planning and coordination with municipal, State, and Federal authorities. x Initial response to notification by SSES. x Alert and warning of local populations within the 10 mile EPZ. x Evacuation and other protective measures for local populations within the 10 mile EPZ. x Emergency services. x Situation analysis. x 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: x Issuance of planning guidance. x Coordination of State response to nuclear incidents. x Coordination of multi-county Emergency Response Planning. x Operation of PEMA EOC. x Provision for emergency public information. x Coordination of State agencies and departments. Page 15 of 19

Emergency Plan, Rev. 67, Page 58 of 166 DEP/BRP provides for: x Technical consultation on Radiological and Plant conditions. x Accident assessment. x Recommendations for protective actions. x Recommendations for protection of potable water and food. x Recommendations for recovery and re-entry (off-site). x Operation of DEP/BRP EOC. 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 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. NRC - designated Lead Federal Agency (LFA) under the National Response Plan (NRP). The primary method of notification to the NRC is via the Emergency Notification System (ENS). Upon notification of an emergency classification, the NRC 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, NRC 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 JIC, TSC, Control Room and OSC. If conditions warrant, the NRC 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 16 of 19

Emergency Plan, Rev. 67, Page 59 of 166 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. DHS - 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 Susquehannas 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. Page 17 of 19

Emergency Plan, Rev. 67, Page 60 of 166 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 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 establish a restoration organization when the following guidelines have been met: x In-plant systems are stable, adequate core cooling established and contingency systems and plans available. x In-plant radiation levels are stable or are decreasing with time. x Releases of radioactive material to the environment are under control or have ceased. x 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. x Restoration Manager - A designated officer or senior manager from Susquehanna to manage SSES restoration operations. x Plant Operations Manager - A designated manager from Susquehanna qualified to control plant operations including security. x Technical Support Manager - A designated manager from Susquehanna qualified to manage a technical group. x Radiological Manager - A designated manager qualified to manage the radioactive waste and radiological control aspects. Page 18 of 19

Emergency Plan, Rev. 67, Page 61 of 166 x 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. x Advisory Support Function - Advisory support consists of senior representatives of the NSSS supplier, the NRC, and special consultants. x Scheduling/Planning Manager - A designated manager to coordinate plans and schedules for the Restoration Manager. x Administration and Logistics Manager - A designated manager who is responsible for providing administrative, logistic, communications and personnel support. x Public Information Manager - A designated manager qualified to manage public relations activities. During restoration operations, the radiation exposure limits of 10CFR20 apply. Compliance with those limits is the responsibility of the Restoration Manager via the applicable Radiation 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, radioactive 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 organizations and agencies prior to initiating release. Page 19 of 19

Table 6.1 Emergency Plan, Rev. 67, Page 62 of 166 STATION EMERGENCY PLAN MINIMUM STAFFING REQUIREMENTS (Note A) Capability for Additions Major Functional Area Major Tasks Position Title or Expertise On Shift 60 min 90 min 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 1 -- (Note D) (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-plant (RP Tech)] Survey Team Personnel -- 1 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 Chemistry/Radiochemistry Chemistry Technicians 1 1 --

Page 1 of 3

Table 6.1 Emergency Plan, Rev. 67, Page 63 of 166 STATION EMERGENCY PLAN MINIMUM STAFFING REQUIREMENTS (Note A) Capability for Additions Major Functional Area Major Tasks Position Title or Expertise On Shift 60 min 90 min Plant System Engineering Technical Support Shift Technical Advisor 1 -- -- Operations Coordinator -- 1 -- Core/Thermal Hydraulics Engr. -- 1 -- Electrical Engr. -- 1 -- Mechanical Engr -- 1 -- Technical Support Coordinator -- 1 -- Engineering Support Supervisor -- -- 1 Repair and Corrective Actions Management of Damage Control Damage Control Team Teams Coordinator -- 1 -- OSC Coordinator -- 1 -- Repair and Corrective Actions Mechanical Maintenance/ (Note G) 1 -- (onshift requirements may be fulfilled Rad Waste Operator (Note G) by NLOs) Electrical Maintenance/ 1 1 Instrument and Control Technician Firefighting Firefighting communications -- Fire Brigade Local per Technical Support Requirements Manual Rescue Operations and First Aid -- -- (Note H) Local Support Site Access Control and Security, personnel accountability Security Personnel All per Personnel Accountability Security plan Security Coordinator -- 1 -- 15 22 14 Plus Fire Brigade and Security Plan Required Personnel Page 2 of 3

Table 6.1 Emergency Plan, Rev. 67, Page 64 of 166 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 See Appendix K for staffing analysis. Note F 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 individuals 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. 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. 67, Page 65 of 166 TABLE 6.2 ADDITIONAL ASSISTANCE FROM OUTSIDE SUSQUEHANNA NUCLEAR, LLC Name/Address Emergency Function Availability (Hours) Reporting Location

1. Committed Resources x General Electric Engineering advise and analysis for N/A GE Facilities NSSS equipment Operations and Maintenance 48 EOF expertise on NSSS equipment x 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 x Other Nuclear Utility Operations, Maintenance, 4 EOF Support Radiological personnel for augmenting emergency staffing 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. 67, Page 66 of 166 TSC ORGANIZATION

                                                                                     *r----------------

I EMERGENCY I I I DIRECTOR* I I

                                                                                     -------- -------~

I I

I Operations ------. I I Admin Staff I I Security I I I I Rad Prot ------. I I I I Coordinator* I I I I Coordinator* I I I I Coordinator* I I

                                               *-----7------*                                                        *------------* *------*-----*

l I *------------- A Rad I- - - - - - - _I __ -- - - -

I I' I

Monitoring II I I I Emergency Plan I Damage Control ----t I Shift Manager l : I I Communicator* .. ______________ Team (2) I Team Coord.* I I I I t------7------! I HPN I I Communicator

                                                                                     . r------------~ [-------------~

I I NRC I I

                                                                                         ~-------------*

I I Communicator* I I I OSC Coordinator** II Tech Support I I I I I Coordinator* I

                                                                                                                                                          -       TSC Dose 1i------   ------*

i- - Core

                                                                                                                                       - - --Thermal
                                                                                                                                              -- - - - - - -. Calculator I                          I I  Hydraulic Engineer      I L. * * * ** ** * * * * * **                       I             I i-- - - - - - - - -- -- -.I I             I I

L.........J Additional I I I Electrical Engineer I I I I Rad Staff I I I L ___________ I Susquehanna Steam Electric Station L-- - - - - - - - - - - - _1 Units 1 and 2 i- - -Mechanical Emergency Plan I I I Engineer I TSC ORGANIZATION L--------------* FIGURE 6.2 Engineering Support r-------------------------------------------------------------

Designates minimum requirements in accordance with Table 6.1 for 60-minute response. I

       -------------------------------------------------------------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. 67, Page 67 of 166 OSC ORGANIZATION

                                                            ~--------------------~

OSC COORDINATOR

_______ J _________ _

Non-Operations Support Personnel ----------* ---------------

                                                     *Non-Operations Support Personnel    I I

I RP Specialist I I (Rad Assessment Staff) I Chemistry Coordinator Four RP Technicians Four RP Technicians One Chemistry Technician One Electrical Maintenance or I&C One Mechanical Maintenance Technician One Electrical Maintenance or I&C Report @ 90 minutes Technician Report @ 60 minutes

Designates positions required for OSC activation.

~------------------------------------------------------------- 1 Designates minimum requirements in accordance with Table 6.1 for 60-minute response. I Susquehanna Steam Electric Station

------------------------------------------------------------~

Units 1 and 2 Emergency Plan 1 I OSC ORGANIZATION I Designates minimum requirements in accordance with Table 6.1 for 90-minute response. I'--------------------------------------------------' I FIGURE 6.3 Page 2 of 5

Emergency Plan, Rev. 67, Page 68 of 166 EOF ORGANIZATION I' I RECOVERY MANAGER* II I I I I L----------

                                                                                                                      'II EOF SUPPORT II                    PUBLIC INFORMATION SUPERVISOR* I I               I                  MANAGER I

ENGINEERING I

                                             '       DOSE I ASSESSMENT I

TECHNICAL SUPPORT I I I

         .,I SUPERVISOR*     I I

I

                                             .,I SUPERVISOR*   I I

ADVISOR PUBLIC OFFICIALS CONTACTS I EMERGENCY I I I PLAN I L-----------* I DOSE ASSESSMENT I LIAISON COMMUNICATOR* I ENGINEERING I I STAFFER* SUPPORT ADMIN. STAFF SUPPORT I (RAD Assessment Staff): SUPERVISOR

                                                          ,---------------.                  OFFSITE AGENCY NEP DUTY PLANNER FIELD TEAM DIRECTOR*

(RAD Assessment Staff) LIAISONS TECHNICAL BRIEFERS iCJ----------: I A RAD I ADMIN. STAFF I MONITORING I I TEAM (2)* I I I NEWS MANAGER I B RAD I MONITORING I I SECURITY TEAM (2)** I ENVIRONMENTAL SAMPLING TEAM ADDITIONAL RAD STAFF 1 Designates minimum requirements in accordance with Table 6.1 for 90 minute response. I Susquehanna Steam Electric Station Units 1 and 2

Designates positions required for EOF activation. Emergency Plan

            ** Not required for activation unless A team unavailable.                                                                                      EOF ORGANIZATION NOTE: RAD Monitoring Team (2) refers to 1 Team with 2 people.

FIGURE 6.4 r--------------------------------------------------------------* I Designates minumum requirements in accordance with Table 6.1 for 60 minute response. I

            ,~-----------------------------------------~*

I I Page 3 of 5

Emergency Plan, Rev. 67, Page 69 of 166 CORPORATE HEADQUARTERS PUBLIC ADMIN/ RESTORATION INFORMATION LOGISTICS MANAGER MANAGER MANAGER ADVISORY SCHEDULING/ TECHNICAL PLANT RADIOLOGICAL MAINTENANCE SUPPORT PLANNING SUPPORT OPERATIONS MANAGER MANAGER FUNCTIONS MANAGER MANAGER MANAGER Susquehanna Steam Electric Station Units 1 and 2 Emergency Plan LONG TERM RESTORATION ORGANIZATION FIGURE 6.6 Page 4 of 5

Emergency Plan, Rev. 67, Page 70 of 166 COMMUNICATION INTERFACES WITH OFF - SITE AGENCIES Control Room Control Room NRC Emergency Plan Communicator Communicator TSC TSC NRC Emergency Plan Communicator Communicator TSC HPN Communicator CTN EOF Communicator ENS HPN I I____, NRC PEMA LCEMA CCEMA

                                                           .....__________          ~                        ~~

CJ Liaison Support Supervisor*

Responsible for Interface with Agencies located in EOF CTN

                                                           .___________.7 DEP/ BRP CTN Emergency               Tech Support                 Rad Protection Director( PAR)            Coordinator                   Coordinator             Susquehanna Steam Electric Station Units 1 and 2 Emergency Plan Recovery Manager            Engineering                 DASU/Liaison (PAR )             Support Supervisor            Support Supervisor           COMMUNICATION INTERFACES WITH OFF- SITE AGENCIES FIGURE 6.7 Page 5 of 5

Emergency Plan, Rev. 67, Page 71 of 166 7.0 EMERGENCY MEASURES 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. x Perform surveillance of in-plant instrumentation. x Initial and continued observation of off-normal conditions. x Obtain assistance from off-duty personnel and/or off-site support groups. x Deploy on-site damage control teams. x Perform reactor coolant sampling and analysis. x Deploy field radiological monitoring teams to perform direct radiation measurements and air sampling. x Perform dose calculation activities. Correlate with field team data. x Perform sampling and analysis of environmental media. 7.1.1 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 1 of 10

Emergency Plan, Rev. 67, Page 72 of 166 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 Supervisors 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 10 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. The meteorological systems are instrumented to provide continuous data to the control room and the Plant Computer System for utilization in the TSC and EOF. Data that enters Plant Computer System is viewable through various display formats and is also transmitted to the NRC via ERDS. 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 data 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 2 of 10

Emergency Plan, Rev. 67, Page 73 of 166 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 offsite doses to the public based on evaluation of isotope specific release rates and 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 3 of 10

Emergency Plan, Rev. 67, Page 74 of 166 The dose calculation model has the following characteristics typical of a class B model: NOTE: A class "B" model is a numerical model that represents the actual spatial and temporal variations of plume distribution. x The atmospheric dispersion calculation uses real-time site specific meteorological data to compute plume dispersion, deposition, and depletion using a combination of straight line and trajectory puff (LaGrangean) Gaussian models. x Estimates release rates by isotope based on real-time plant measurements and alternate backup methods. x Computes plume trajectory as a function of site specific terrain conditions in the puff model. x Includes wet and dry deposition. x Calculates Total Effective Dose Equivalent (TEDE) and child thyroid Committed Dose Equivalent (CDE) based on the evaluated release rates and the dispersion model. x Provides a summary of offsite consequences with spatial distribution of consequences throughout the planning zone. Page 4 of 10

Emergency Plan, Rev. 67, Page 75 of 166 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 CDE. However adult physiology is used in calculating thyroid CDE for purposes of evaluating the need 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 results are provided: x TEDE 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. x Plume exposure rates for field team management. x Fifty year child thyroid CDE, from inhalation of radioactive materials. x Summary print of release rates, projected doses, and calculation basis. x Plume plotting of the TEDE and CDE thyroid dose distribution. The dose calculation program is a standalone program running on PCs located in the TSC, Alternate TSC and EOF. The dose assessment program also has the capacity to integrate the time dependent releases and local meteorology over the course of a release event and provide a summary of offsite consequence estimates for the entire event. This integrated event assessment includes TEDE, child thyroid CDE and isotope specific deposition spatially distributed throughout the planning zone radius. 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. Page 5 of 10

Emergency Plan, Rev. 67, Page 76 of 166 7.2 CORRECTIVE ACTIONS 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 7.2 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. 7.3 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 EOF. 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 implemented in a timely manner. Protective action recommendations are outlined in Table 7.3. Page 6 of 10

Emergency Plan, Rev. 67, Page 77 of 166 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. 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. Page 7 of 10

Emergency Plan, Rev. 67, Page 78 of 166 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 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 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 alternate 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 decision 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. Page 8 of 10

Emergency Plan, Rev. 67, Page 79 of 166 7.3.2 Off-Site Protective Actions 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 x Administration of thyroid prophylaxis x 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 CCEMA 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 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.

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, identifies 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. Page 9 of 10

Emergency Plan, Rev. 67, Page 80 of 166 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 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. 7.4.3 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. Page 10 of 10

Emergency Plan, Rev. 67, Page 81 of 166 CODE: Notification of Unusual Event = 1 Alert = 2 Site Area Emergency = 3 General Emergency = 4 TABLE 7.1

SUMMARY

OF IMMEDIATE NOTIFICATION AND RESPONSE FOR ALL CLASSIFICATIONS ONSITE OFFSITE IMMEDIATE NOTIFICATIONS ACTIONS IMMEDIATE NOTIFICATIONS ACTIONS Fire Brigade (1-4) Fight Fire (1-4) Fire Units (1-4) Fight Fire (1-4) Damage Control Team (1-4) Repairs (1-4) First Aid/Rescue Team (1-4) Rescue (1-4) Rescue Assistance (1-4) Rescue (1-4) First Aid (1-4) Ambulance (1-4) Transport (1-4) Hospital (1-4) Treatment (1-4) Security Force (1-4) Security Measures (1-4) PSP (1-4) Assist Security (1-4) Personnel Evacuation (1-4) Dose Assessment Personnel (1-4) Dose Calculations (1-4) Talen Headquarters (1-4) Confirmatory Calculations (2-4) Dose Assessment (1-4) Maintain Communications (2-4) Field Monitoring Teams (1-4) Field Monitoring (1-4) Field Monitoring and Continuous Evaluation of Dose Projections (2-4) All Other Station Personnel (1-4) Augment Shift Talen Headquarters(1-4) Alert Key Personnel (1) Resources/Activate Site personnel designated as Activate and Staff Offsite ERO TSC (2,3,4) off-site response (2,3,4)* (2,3,4) Augment Resources/Activate Recommend Offsite Action (4) Offsite ERO (2,3,4) Personnel Evacuation (as appropriate ) (3,4) Page 1 of 2

Emergency Plan, Rev. 67, Page 82 of 166 TABLE 7.1

SUMMARY

OF IMMEDIATE NOTIFICATION AND RESPONSE FOR ALL CLASSIFICATIONS ONSITE OFFSITE IMMEDIATE NOTIFICATIONS I ACTIONS IMMEDIATE NOTIFICATIONS ACTIONS PIM 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 LCEMA, CCEMA, 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.

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Emergency Plan, Rev. 67, Page 83 of 166 TABLE 7.2 EMERGENCY EXPOSURE CRITERIA 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 accumulated 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 of the 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. Guidance on Dose Limits for Workers Performing Emergency Services Dose Limit a (rem) Activity Condition 5 rem All 10 rem Protecting 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. 67, Page 84 of 166 TABLE 7.2 EMERGENCY EXPOSURE CRITERIA Additional General Criteria x Only volunteers are given planned emergency exposure. x Attached tables provide information concerning acute and delayed health effects. x Whenever practical, consideration is given to dividing exposure among as many personnel as possible. x 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. x All reasonable measures must be taken to control contamination and internal exposure. x Persons performing emergency activities should be familiar with exposure consequences. x Women capable of reproduction should not take part in these actions. x Retrospective doses are evaluated on an individual case basis. x 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 of 3

Emergency Plan, Rev. 67, Page 85 of 166 TABLE 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. 67, Page 86 of 166 TABLE 7.3 PROTECTIVE ACTION RECOMMENDATIONS Emergency Conditions Susquehanna Actions Susquehanna Recommendations A. Airborne Release Determine the following: SSES will provide an initial PAR based on site-specific wind persistence study to the Senior

1. General Public 1. Plant status and prognosis. State Official within 15 minutes from the declaration of a General Emergency as follows:

x Degree of fuel damage 1. For a Rapidly Progressing Severe Accident (RPSA): x Containment integrity a. Evacuate 2 mile radius; x Decay heat removal b. Evacuate affected sectors 2-10 miles downwind. x Ventilation systems x 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:

a. Evacuate 2 mile radius; x Release path, monitored,

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 x Duration of release dose assessment projects doses less than 1000 mrem TEDE and less than 5000 mrem x 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. x Treatment availability, filtered, unfiltered Initial PAR shall also advise citizens to take KI in accordance with the states emergency plans x Type of release, gap, fuel and advise remainder of the EPZ to monitor and prepare. melt x 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. Evacuate all sectors where PAGs were exceeded.

Page 1 of 3

Emergency Plan, Rev. 67, Page 87 of 166 TABLE 7.3 PROTECTIVE ACTION RECOMMENDATIONS Emergency Conditions Susquehanna Actions Susquehanna Recommendations A. Airborne Release (Cont'd) Determine the following:

3. If RPSA or HAB conditions do not apply, or for all other General Emergencies, ERO

1. General Public (Cont'd) 3. Weather Conditions, effect on shall consider the following subsequent PARs based on dose assessment results or dose projections. changes in wind direction affecting new sectors, if conditions exist which would require classification of a General Emergency per EALs:

4. Dose projections and avoided a. Evacuate additional affected sectors 2-5 miles downwind dose. 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 CDE 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 10CFR50.47(b)(10), Appendix E to Part 50, Section IV Paragraph 3 and NUREG-0654, Supplement 3, Rev 1. Emergency Conditions Susquehanna Action Results Susquehanna Recommendations A. Airborne Release (Cont'd.) 1. Determine the following:

2. Dairy Cows a. Peak activity for I131 a. Forage Concentration .05 micro Ci/kg Milk .015 micro Ci/l 1.5 Rem projected dose to the infant thyroid whichever is first.

b. Meteorological Conditions b. Known sectors potentially DEP/BRP to recommend appropriate protective affected action to affected farmers.

(1) Wind Speed (2) Precipitation (3) Stability Class (4) Wind Direction Page 2 of 3

Emergency Plan, Rev. 67, Page 88 of 166 TABLE 7.3 PROTECTIVE ACTION RECOMMENDATIONS Emergency Conditions Susquehanna Action Results Susquehanna Recommendations B. Liquid Radioactive Release 1. Determine the following: A single isotope exceeds its 1. Recommend to DEP/BRP that consideration Into Susquehanna River specific effluent concentration be given to termination of user intake of all

a. Source of release (EC) value from Column 2 of downstream users.

b. Volume (approx.) of Table 2 of Appendix B to release 10CFR20 or diluted sum of EC 2. Assess additional results of sampling and

c. Anticipated length of fractions at Danville is greater analyses of radionuclide activity time release will than 0.85. concentrations of SSES liquid effluent and/or continue Susquehanna River water upstream of the Danville Water Authority, and provide

2. Notify: appropriate updated recommendations to DEP/BRP based on that assessment.

a. DEP/BRP

b. Danville Water authority

c. NRC

3. Initiate sampling of:

a. Release point

b. Susquehanna River

4. Initiate projections of radionuclide activity concentrations at the Danville Water Authority.

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Emergency Plan, Rev. 67, Page 89 of 166 8.0 EMERGENCY FACILITIES AND EQUIPMENT 8.1 ON-SITE EMERGENCY CENTERS 8.1.1 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 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. 8.1.2 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 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 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 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. Page 1 of 16

Emergency Plan, Rev. 67, Page 90 of 166 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 6.4, and NUREG-0737, Item II.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 Rem 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 II.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. Page 2 of 16

Emergency Plan, Rev. 67, Page 91 of 166 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, and 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 3 of 16

Emergency Plan, Rev. 67, Page 92 of 166 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 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 approximately 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 II.B.2 8.1.2.2.1.b Postulated Post Accident Radiation Doses The back-up OSC is monitored for radiation exposure using portable ARM installed by Radiation Protection per OSC request, in accordance with their procedures. The radiation dose will be limited to less than 5 Rem TEDE. Applicable criteria are specified in General Design Criterion 19, Standard Review Plan NUREG 0800 Section 6.4, and NUREG-0737, Item II.B.2. 8.1.2.2.1.c Radiation Monitoring Until the portable ARM is installed in the back-up OSC, a commercial grade monitor located in the center of the Control Room that alarms on high gross gamma radiation dose rates can also be used to ensure adequate radiological protection of the backup OSC personnel. 8.1.2.2.2 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 4 of 16

Emergency Plan, Rev. 67, Page 93 of 166 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, USNRC Standard Review Plan NUREG 0800 Section 6.4, and NUREG-0737, Item II.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. Page 5 of 16

Emergency Plan, Rev. 67, Page 94 of 166 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 741'-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 Plant Computer terminals, associated copiers. (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. 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 II.B.2. Page 6 of 16

Emergency Plan, Rev. 67, Page 95 of 166 8.1.3.4.1.b Postulated The radiation dose to personnel is the same as the Control Room personnel. The doses from controlling accidents are summarized in Section 15 of the FSAR. 8.1.3.4.1.c Radiation Monitoring 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. 8.1.3.4.2 HVAC The TSC HVAC system is a part of the Control Room HVAC 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. Exposure will not exceed 5 Rem TEDE for the duration of the accident. This is in accordance with General Design Criterion 19, USNRC Standard Review Plan NUREG 0800 Section 6.4, and NUREG-0737, Item II.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. 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. Page 7 of 16

Emergency Plan, Rev. 67, Page 96 of 166 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 channel 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. Page 8 of 16

Emergency Plan, Rev. 67, Page 97 of 166 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 Computer System, 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 For all event classifications, the East Mountain Business Center, Plains Township, will be activated as the Joint Information Center. 8.2.2 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 10 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 9 of 16

Emergency Plan, Rev. 67, Page 98 of 166 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 to 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. Page 10 of 16

Emergency Plan, Rev. 67, Page 99 of 166 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 radiological 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) 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. Page 11 of 16

Emergency Plan, Rev. 67, Page 100 of 166 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 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 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. Page 12 of 16

Emergency Plan, Rev. 67, Page 101 of 166 8.4.3 Natural Phenomena Monitors 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. 8.4.4 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. 8.4.5 Radiological Monitoring Team Equipment Reference Appendix D. 8.5 PROTECTIVE FACILITIES 8.5.1 Control Room 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.

8.5.2 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. 8.5.3 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.

Page 13 of 16

Emergency Plan, Rev. 67, Page 102 of 166 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 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 Commercial Telephone System 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, DEP/BRP, PEMA, LCEMA, and CCEMA. This is the primary system for emergency communications. 8.6.2 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. Emergency First Aid/Trauma kits are at designated locations throughout the station. Inventories are performed regularly. Page 14 of 16

Emergency Plan, Rev. 67, Page 103 of 166 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 Computer System The Plant Computer System 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 I/O 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 ERDS and SPDS functions are integrated into its design.
All of the Plant Computer System data and functions are easily made available at locations remote from SSES.

8.9.1.1 Data Acquisition Data is acquired from I/O 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 Plant Computer System SDS. 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 Plant Computer System 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 Plant Computer System SDS is independent from each station and controlled by multiple copies of the identical software. Page 15 of 16

Emergency Plan, Rev. 67, Page 104 of 166 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. Page 16 of 16

Emergency Plan, Rev. 67, Page 105 of 166 TABLE 8.1 RELATIONSHIP OF THE PRIMARY PARAMETER, SECONDARY DISPLAY, AND ALGORITHMS 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. Primary 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

Emergency Plan, Rev. 67, Page 106 of 166 J'Ll.4LQQQ_ LEGEND N346,000 PP L PROPERIY LINI:. T-XXX TOWNSHIP ROADS CLOSFST SITE BOUNDARY DISTANCE (FFFT) (2) EPB DISTANCE BOUNDED BY '<DUTE

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                                                          !I II SUSQUEHANNA NUCLEAR LLC

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                                                                                                                                                                   ",,, C-2532         '"*" "' 1 fRAr.TIONAI Figure 8.1 MAP OF THE SUSQUEHANNA SES EMERGENCY FACILITIES Page 1 of 1

Emergency Plan, Rev. 67, Page 107 of 166 NUCLEAR REGULATORY COMMISSION SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 EMERGENCY PLAN Technical Support Center FLOOR PLAN FIGURE 8.2 Typical work station including desk, chair, Field Team telephone as necessary for Radio Indicates telephone-may be a standard telephone. May also represent FTS emergency response for phone. the listed positions. Verms Interface Administrative Coordinator Security Coordinator TSC Dose Calculator HPN Communicator Radiation Protection Coordinator Emergency Director TSC Emergency Plan Communicator TSC NRC Communicator Operations Coordinator Technical Support Coordinator Damage Control Team Coordinator Status Boards and Area Maps-Typical TERMINAL Cabinet Engineering Support Area NSSS Engineer Core thermal Hydraulic Engineer Computer Electrical/I& C Engineer Symbol for Computer WS Station-PICSY Radio SPDS Power Supply (Symbol is not necessarily Engineering indicative of the specific Support Area number of computer installations. The symbol Library designates a typical installation) Elevator Page 1 of 1

Emergency Plan, Rev. 67, Page 108 of 166 East Mountain Business Center/ Floor Plan EOF/JIC Page 1 of 1

Emergency Plan, Rev. 67, Page 109 of 166 SUSQUEHANNA STEAM ELECTRIC STATION Units 1 and 2 EMERGENCY PLAN SIREN LOCATION Figure 8.4 Page 1 of 1

Emergency Plan, Rev. 67, Page 110 of 166 9.0 MAINTAINING EMERGENCY PREPAREDNESS 9.1 ORGANIZATIONAL PREPAREDNESS 9.1.1 Training

a. All unescorted personnel entering or working within the SSES Radiologically Controlled Area receive as a minimum, the following instruction:

x Appropriate portions of the SSES EP. x Use of emergency facilities and equipment, familiarization with station alarms and personnel response, and station communications systems. x Personnel accountability, evacuation, and radiation exposure criteria. x 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 specific review of dose calculations/projections, protective actions guides, and reportable information.

Page 1 of 7

Emergency Plan, Rev. 67, Page 111 of 166

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: x Interface with the Site Security Force x Basic radiation protection indoctrination and training x SSES facility layout Fire companies also receive training in the following areas: x On-site fire protection system equipment x Differences between on-site firefighting equipment and fire company supplied equipment x Communications system x Review of sections of the SSES EP and EP-PSs x 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. Page 2 of 7

Emergency Plan, Rev. 67, Page 112 of 166 9.1.2 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 10CFR50 Appendix E: x Annual medical drill involving offsite support x Annual fire drill involving offsite support x Annual radiological drill to site area or general emergency level with offsite participation biennially x Annual full-scale ANS test x Annual environmental monitoring drill x Semi-annual Health Physics drill testing survey sampling and analysis techniques x Annual drill that tests ability to obtain and analyze a post accident coolant sample x Perform augmentation exercise every eight years x Hostile Action Based exercise every eight years x 10 CFR 50.155 strategy in an exercise every eight years Page 3 of 7

Emergency Plan, Rev. 67, Page 113 of 166 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. x All functions in each ERF (e.g., all ERFs that are responsible for dose assessment perform those duties in response to a radiological release). x Use of alternative facilities to stage the ERO for rapid activation during hostile action. x Real-time staffing of facilities during off-hours (i.e., 6:00 p.m. to 4:00 a.m.). x Providing medical care for injured, contaminated personnel (every two years). x Response to essentially 100 percent of initiating conditions identified in the site emergency plan implementing procedure for classification of emergencies. x Response to actual industry event sequences appropriate for the nuclear plant technology (e.g., BWR or PWR). x All ERO teams must be provided the opportunity to demonstrate key skills within the scope of their duties. x Use of procedures developed in response to an aircraft threat. Additional non-integrated drills and tests are conducted as follows: x Bi-weekly Silent Tests for sirens x Quarterly Growl Tests for sirens x Quarterly fire drills x Monthly communications drills with state and county agencies x Monthly communications tests with the NRC Drill scenarios for major drills are prepared to involve participation of several emergency teams and all or 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. Page 4 of 7

Emergency Plan, Rev. 67, Page 114 of 166 9.1.3 Overall Coordination of Nuclear Emergency Preparedness The Manager-Emergency Preparedness is responsible for the overall coordination of all nuclear emergency planning activities. The Manager-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-Emergency Preparedness is typically responsible for: x Revising of the SSES Emergency Plan x Revising of EP-PSs and other Emergency Planning Administrative procedures x Conducting of integrated drills and exercises and communication drills x Defining EP training scope for ERO x Defining EOF and JIC EP Training x Coordinating EP interface between State and Federal agencies x Coordinating maintenance and testing of ANS x Coordinating interface between state, county, municipal, and Susquehanna ERO x Assuring operational readiness of Emergency Response Facilities Page 5 of 7

Emergency Plan, Rev. 67, Page 115 of 166 9.2 REVIEW AND UPDATING 9.2.1 SSES Emergency Plan The Manager-Emergency Preparedness is responsible for the review and revision of the SSES Emergency Plan, ensuring: x 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 10CFR50.54t. x Annual review of the SSES Emergency Plan. x Annual review of Letters of Agreement. x Recommendation of Emergency Plan changes to PORC. x PORC review of Emergency Plan changes and submission of changes to NSRB. x 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). x Perform an annual review of the Evacuation Time Estimate (ETE) to ensure 10CFR50 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. 9.2.2 Emergency Plan Procedures The Manager-Emergency Preparedness is responsible for the review and revision(s) of the Emergency Plan Procedures, ensuring: x The periodic review is accomplished in accordance with established plant procedures. x Revisions to procedures are done in accordance with established plant procedures. x Controlled copies of procedure revisions are issued by station document control programs. x ERO personnel are briefed on revisions as required. Page 6 of 7

Emergency Plan, Rev. 67, Page 116 of 166 9.3 MAINTENANCE AND INVENTORY OF EMERGENCY EQUIPMENT/SUPPLIES The Manager-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-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 Nuclear Emergency Preparedness staff.

9.4.4 Other Distributed Publication(s) 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 7

TABLE 9.1 Emergency Plan, Rev. 67, Page 117 of 166 TRAINING OF SUSQUEHANNA SES EMERGENCY RESPONSE PERSONNEL Personnel Category Involved Personnel Initial Training and Periodic Retraining

1. Emergency Directors Shift Managers, and currently assigned Initial training: EP and EP PSs.

Emergency Directors Retraining: Changes in responsibilities. Frequency: Annual

2. Personnel responsible for Emergency Director; Emergency Initial training: EP and EP PSs.

accident assessment/ Coordinators, Recovery Manager, Dose management Assessment Personnel Retraining: Applicable EP PSs and changes. Frequency: Annual

3. Radiation Monitoring Radiation Protection Supervision; Radiation Initial training: Radiation monitoring EP PSs and applicable Teams Protection Technicians; and Site Personnel Radiation Protection Procedures Retraining: Hands-on instrument usage.

Frequency: Annual

4. Fire Brigade Unit Supervisors - Fire Brigade Leader, Site Training and retraining are outlined in the SSES Fire Protection Support Services Review Report.

personnel - Fire Brigade Members

5. Damage Control Teams Non-Licensed Operators; Maintenance Repair and Damage Control are a normal part of the job functions.

Supervision; Maintenance Personnel; Radiation Protection Technicians; I&C Initial training: Availability of damage control equipment, use of Supervision; I&C Personnel communication systems, and interfaces with other emergency teams. Retraining: Review of the above topics. Frequency: Annual Page 1 of 2

TABLE 9.1 Emergency Plan, Rev. 67, Page 118 of 166 TRAINING OF SUSQUEHANNA SES EMERGENCY RESPONSE PERSONNEL Personnel Category 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 Training and retraining: Communication system and interfaces with local Medical Response Teams) directed by Team Leader) medical support personnel.

Security Force Members 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) Chemistry Training and retraining: CPR Training (see Note) Site Support Services Retraining frequency: See Note

7. Fire Support Personnel Local Fire Companies Training and retraining are outlined in Section 9 of the SSES EP.

8. Medical Support Personnel Ambulance Companies and Support Hospital Staff Initial training: Treatment and handling of contaminated/injured per Letters of Agreement (Appendix A) personnel, communication systems, radiological hazards and interfaces with SSES personnel.

Retraining: Review of the above topics. Retraining frequency: 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. Retraining frequency: Annual

10. Security 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. Retraining frequency: Annual NOTE: Specific training and retraining requirements are identified in the Training Matrices for Emergency Planning, Security, Radiation Protection, Chemistry, Operations, Site Support Services and all ERO members. 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 SSS - First Aid and CPR biennially Page 2 of 2

Emergency Plan, Rev. 67, Page 119 of 166 APPENDIX A LETTERS OF AGREEMENT Page 1 of 3

Emergency Plan, Rev. 67, Page 120 of 166 LETTERS OF AGREEMENT 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 Volunteer Fire Department Columbia County Commissioners Don E. Bower, Inc Department of Environmental Protection/Bureau of Radiation Protection Federal Radiation Monitoring and Assessment Center (FRMAC) GE BWR Emergency Support Geisinger Ambulance Geisinger Bloomsburg Hospital Geisinger Medical Center Hobbie Volunteer Fire Co. - EMS Institute of Nuclear Power Operations Lackawanna County Commissioners Latona Trucking Luzerne County Council Medico Construction Equipment Inc. 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. 67, Page 121 of 166 These letters of agreement provide for: x Coordination of planning efforts by State and local agencies; industry support groups; fire ambulance and hospital support services; and Susquehanna. x Appropriate emergency response to assure employee and public safety during an emergency condition at SSES. x Mutual notification capabilities. x Appropriate training and exercising of emergency response capabilities. x Fire, first aid and medical support. x Environmental monitoring and assessment support. x Other emergency support services as deemed necessary The Manager-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: Reference Action Request 1066721 for why separate LOA is not needed for Pennsylvania State Police. Page 3 of 3

Emergency Plan, Rev. 67, Page 122 of 166 APPENDIX B WIND ROSES, DOSE/DISTANCE PLOTS AND JOINT FREQUENCY DISTRIBUTION ORIGINAL DOCUMENT ISSUED 01/1992 Page 1 of 4

Emergency Plan, Rev. 67, Page 123 of 166 WIND ROSES In accordance with 10 CFR 50.36a and the Susquehanna Steam Electric Station (SSES) Units 1 and 2 Technical Specification (TS) 5.6.3, SSES sends to the NRC an annual Radioactive Effluent Release Report for SSES Units 1 and 2 which contains the most recent wind rose at SSES. This is retrievable in NIMS, under DMWASRCH menu with the key word Radioactive Effluent Release Report. Page 2 of 4

Emergency Plan, Rev. 67, Page 124 of 166 DOSE/DISTANCE PLOTS The dose/distance plots have been removed and reference to the use of SSES URI as the approved methodology/tool for determining magnitude of and for continually assessing the impact of the release. SSES URI has the capability to provide assessments using event-specific fuel damage estimates. Additionally, the code 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 4

Emergency Plan, Rev. 67, Page 125 of 166 JOINT FREQUENCY DISTRIBUTION In accordance with 10 CFR 50.36a and the Susquehanna Steam Electric Station (SSES) Units 1 and 2 Technical Specification (TS) 5.6.3, SSES sends to the NRC an annual Radioactive Effluent Release Report for SSES Units 1 and 2 which contains the most recent Joint Frequency Distribution at SSES. This is retrievable in NIMS, under DMWASRCH menu with the key word Radioactive Effluent Release Report. Page 4 of 4

Emergency Plan, Rev. 67, Page 126 of 166 APPENDIX C SSES EMERGENCY PLAN POSITION SPECIFIC PROCEDURES (TYPICAL) Page 1 of 2

Emergency Plan, Rev. 67, Page 127 of 166 APPENDIX C SSES EMERGENCY PLAN POSITION SPECIFIC PROCEDURES (TYPICAL) EMERGENCY PLAN POSITION SPECIFIC PROCEDURES (Response Procedures) CR Procedures EOF Procedures Emergency Director Recovery Manager Emergency Plan Communicator EOF Support Supervisor NRC Communicator NEP Duty Planner EOF Emergency Plan Communicator TSC Procedures Environmental Sampling Team Emergency Director Radiological Monitoring 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 Sampling Director TSC Administrative Coordinator EOF Technical Advisor TSC E Plan Communicator Engineering Support Supervisor HPN Communicator Fuels Lead Engineer / Core Thermal Hydraulics Engineer RP II Dose Calculator EOF Systems Lead Engineer Damage Control Team Coordinator EOF Support Engineer TSC NRC Communicator TSC Information Coordinator JIC Procedures Fuels Lead Engineer / Core Thermal Public Information Manager Hydraulics Engineer TSC RP Radio Communicator News Manager JIC Technical Briefer Support Services Manager OSC Procedures Media & Public Officials Contact OSC Coordinator JIC Logkeeper RP Specialist JIC Writer Maintenance Foreman/Field Unit Supervisor JIC Administrative Coordinator Chemistry Coordinator OTHER EMERGENCY PLAN RESPONSE PROCEDURES 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 URI User Manual Personnel Accountability Page 2 of 2

Emergency Plan, Rev. 67, Page 128 of 166 APPENDIX D EQUIPMENT INFORMATION LISTINGS Page 1 of 16

Emergency Plan, Rev. 67, Page 129 of 166 CONTENTS OF APPENDIX D Equipment Information Listings Typical Station Decontamination Area Equipment Typical Damage Control Equipment Storage Box Contents Onsite Search and Rescue/First Aid, Typical Ambulance and Hospital Radiation Emergency Equipment and Supplies Natural Phenomena Monitors Radiological Monitors Environmental Monitoring Systems Typical Radiation Protection Van Radiation Emergency Monitoring Equipment Emergency Classification Dependent Instrumentation Typical Initial Emergency Equipment for Initial Incident Response Typical TSC Equipment Typical EOF Equipment Page 2 of 16

Emergency Plan, Rev. 67, Page 130 of 166 ENCLOSURE 1 TO APPENDIX D Typical Station Decontamination Area Equipment Decontamination Procedures Masking Tape Coveralls Paper Towels Decontamination Soap Shoe Covers, paper Disposable Bath Towels Sponge Plastic Gloves + Cotton Inserts Frisker Hand Brushes Typical Damage Control Equipment Storage Box Contents Amprobe Plugs, Wood, 1 & 6 Bars, Pry, Large Plugs, Wooden Box, 1, 11/4, 11/2, 2, 21/2, 3 Bars, Pry, Rolling Lead Rubber, Roll 1/16 thick, 10 X 3 Black Wire, 1/4 lb. Rolls, 16 Gauge Screwdrivers, Large Standard Box, Tool, 23 Screwdrivers, Medium Standard Bucket, 14 quart, Plastic Screwdrivers, Phillips, Large Cable Cutters Screwdrivers, Phillips, Medium Clamps, C, Medium String, Ball Clamps, C, Large Twine, Bale Clamps, C, Small Wedges, Wooden Electricians Pouch with Miscellaneous Hand Tools Wrench, Adjustable, 12 Enerpac, Rescue Unit Wrench, Adjustable, 8 Flashlight, 5 cell Wrench, Allen Pac 3/16, 7/32, 1/4, 5/16, 3/8 Hammer, Ball Peen, 16 oz. Wrench, Allen Pac .050, 1/16, 5/64, 3/32, Hammer, Sledge, 10 lb. 7/64, 1/8, 9/64, 5/32, 3/16, 7/32 Hammer, Sledge, 8 lb. Wrench, Chain Multimeter Wrench, Hex, #110 Nylon Rope, 100 coils, 3/4 Wrench, Hex, #17 Nylon Rope, 25 coils, 3/8 Wrench, Hex, 24 Nylon Rope, 50 coils, 3/8 Wrench, Pipe, 18 Nylon Rope, 50 coils, 3/4 Wrench, Pipe, 14 Plastic Sheet, 20 X 20, Fire Retardant Pliers, Lineman Pliers, Water Pump Page 3 of 16

Emergency Plan, Rev. 67, Page 131 of 166 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 Folding Litter Basket Stretcher (Stokes) Portable Oxygen-Demand Valve (size D tank Emergency First Aid/Trauma Kits With assorted airways, cannulas, and masks) Scoop Stretcher Trauma Kit Assorted Splinting Devices Ambulance Kit: Masking Tape Herculite Waste Rad Bags Shoe Covers Plastic Gloves Portable Frisker and Probe Cotton Gloves Lab Coats Hospital: Dosimeter Charger Self Reading Dosimeters Survey Meter Set of Radiation Signs and Ribbon Frisker with Probe Stanchions/Pylons Herculite Step-off Pad Lead Container, high activity samples Thermoluminescent Dosimeters, badge type Thermoluminescent Dosimeters, ring type Page 4 of 16

Emergency Plan, Rev. 67, Page 132 of 166 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

Emergency Plan, Rev. 67, Page 133 of 166 Enclosure 4 to Appendix D RADIOLOGICAL MONITORS Instrument Type Individual Detectors Function & Sensitivity Air Sampling Equipment Continuous Air Monitors Particulate Low volume samplers Particulate, Iodine, Noble Gas Breathing zone samplers Particulate, Iodine Personnel Dosimetry Electronic Dosimetry 0 - 100,000 mrem TLDs Portable Survey Instruments GM survey instruments 0 - 2 R/hr Ion chamber survey instruments 0 - 50 Rem/hr Telescoping GM survey instruments 0 - 1,000 R/hr GM count rate meters 0 - 50,000 cpm Meter with alpha scintillation probe 10 CPM to 100,000 CPM Neutron detector 0 - 1 Rem/hr Portal monitors Counting Room Low background gas N/A proportional counters Liquid scintillation counter scintillation - alpha scintillation - beta High Purity Ge Spectrometer GM End Window Scaler Page 6 of 16

Emergency Plan, Rev. 67, Page 134 of 166 Enclosure 4 to Appendix D (Cont'd.) AREA RADIATION MONITORS (ARMs) Location Range Local I Channel # I Building and Area I Elev. I (mR/hr) I Alarm I 1 1R/2R Resid Heat Removal Area 645' 0.1-1000 Yes 2 1R/2R RCIC Pump Turbine Room 645' 0.01-100 Yes 3 1R/2R HPCI Pump Turbine Room 645' 0.01-100 Yes 4 1R/2R Radwaste Sump Area 645' 0.1-1000 Yes 5 1R/2R Control Rod Drive (North) 719' 0.1-1000 Yes 6 1R/2R Control Rod Drive (South) 719' 0.1-1000 Yes 7 1R/2R Offgas By Pass Line 656' 0.1-1000 Yes 8 1R/2R Cleanup Recirc. Pump Access Area 749' 0.01-100 Yes 9 1R/2R CRD Repair Area 719' 0.1-1000 Yes 10 1R/2R Fuel Pool Room 749' 0.1-1000 Yes 11 1R/2R Sample Station Room 749' 0.01-100 Yes 12 1R/2R Recirc. Fan Room 799' 0.01-100 Yes 13 1R/2R New Fuel Storage Vault 817' 0.1-1000 Yes 14 1R/2R Spent Fuel Pool 818' 0.1-1000 Yes 15 1R/2R Refueling Floor Area 818' 0.01-100 Yes 16 1R/2R Access to Remote Shutdown 670' 0.01-100 Yes 17 1T/2T Cond. Pumps Area 656' 0.01-100 Yes 18 1T/2T RFPT Area at Reactor Bldg 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 Bay 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 1R/2R Resid. Heat Removal Area 645' 0.1-1000 Yes 26 1R/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 Bldg. 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 3l 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 Storage 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. 67, Page 135 of 166 Enclosure 4 to Appendix D (Cont'd) AREA RADIATION MONITORS (ARMs) Location Range Local I Channel # I Building and Area I Elev. I (mR/hr) I Alarm I 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 Bldg. 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 1R/2R HPCI Pump & Turbine Room 645' 100-1,000,000 No 49 1R/2R Refueling Floor Area 818' 100-1,000,000 No 50 1R/2R Control Rod Drive North 719' 100-1,000,000 No 51 1R/2R Control Rod Drive South 719' 100-1,000,000 No 52 1R/2R RWCU Recirc. Pump Access Area 749' 100-1,000,000 No 53 1R/2R Access to Remote Shutdown Panel 670' 100-1,000,000 No 54 1R/2R Fuel Pool Pump Room 749' 100-1,000,000 No 55 1R/2R RHR Room - Loop A 645' 100-1,000,000 No 56 1R/2R RHR Room - Loop B 645' 100-1,000,000 No 57 1R/2R RCIC Pump Turbine Room 645' 100-1,000,000 No Page 8 of 16

Emergency Plan, Rev. 67, Page 136 of 166 Enclosure 4 to Appendix D (Cont'd.) PROCESS MONITORS System Det. Types Range Location Main Steam Line ION 6 Near main steamlines 1-10 mR/hr Chambers between primary and (IC) secondary containment walls, just downstream of MSIVs Refueling Floor Wall GMs 0.0l-l00 Exhaust ducting upstream Exhaust Duct mR/hr of inboard isolation damper, prior to discharge through reactor building vent Refueling Floor High GMs 0.0l-l00 Exterior to fuel pool Exhaust Duct. mR/hr ventilation exhaust duct Railroad Access GMs 0.0l-l00 Exhaust duct prior to Rx Exhaust Duct mR/hr building vent Emergency Outside GMs 0.0l-l00 In the outside intake air Air Intake mR/hr plenum Offgas Pretreatment ICs 6 1-10 mR/hr Discharge of the delay (SJAE) pipe after SJAE Liquid Radwaste Scintillation 7 Off-line on liquid waste 10 - 10 Effluent (SCIN) effluent discharge cpm Service Water (FPC) SCIN Downstream of fuel pool l0- - l0 1 6 HX prior to discharge to cps cooling towers RHR Service Water SCIN On the downstream piping l0- - l0 1 6 of each RHR HX cps RX Building Closed SCIN Suction piping of the l0- - l0 1 6 Water RBCCW pumps cpm Standby Gas GM 0.0l-l00 Inside exhaust ductwork Treatment mR/hr SGTS Vent Exhaust Containment Monitor IC 8 Drywell 1-10 R/hr Page 9 of 16

Emergency Plan, Rev. 67, Page 137 of 166 Enclosure 4 to Appendix D (Cont'd.) VENT MONITORS Type Minimum Location SCIN 10-6 micro Ci/cc gas. Five locations in turbine building, reactor building, and SGTS vents Iodine Sampling NA* Cartridge 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. 67, Page 138 of 166 Enclosure 5 to Appendix D ENVIRONMENTAL MONITORING SYSTEMS

1. Environmental Monitoring Systems Instrument System Individual Detectors Purpose 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

Emergency Plan, Rev. 67, Page 139 of 166 Enclosure 5 to Appendix D (Contd.) 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 Batteries Portable Frisker with Probe

3. Typical Emergency Environmental Sample Kit Contents Assortment of Sampling Bags Plastic Gloves Flashlight Sample Containers Grid Coordinate Map Sample Labels Electronic Dosimeters Scale Pliers Scissors Spare Batteries Page 12 of 16

Emergency Plan, Rev. 67, Page 140 of 166 ENCLOSURE 6 TO APPENDIX D Typical Radiation Protection Van Radiation Emergency Monitoring Equipment Survey Meter with current calibration Stopwatch Portable Frisker with probe Masking Tape Low Volume Air Sampler with head (AC powered) Microfiber Wipes Low Volume Air Sampler with DC power plug Smear Papers DC to AC Inverter Plastic bags for samples VHF mobile radio Extension cord Respirators Work light Iodine Canister Flashlight Potassium Iodide Tablets First Aid Kit Sets of Anti-contamination Clothing Spare batteries Disposable gloves Safety Vests Calculator Gamma Survey Meter Check Source Frisker Check source Silver Zeolite cartridges Particulate Filters Tweezers Page 13 of 16

Emergency Plan, Rev. 67, Page 141 of 166 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 Radiation 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. 67, Page 142 of 166 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. 67, Page 143 of 166 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. 67, Page 144 of 166 APPENDIX E Susquehanna Nuclear, LLC Policy Statement: SUSQUEHANNA SES EMERGENCY MANAGEMENT Page 1 of 2

Emergency Plan, Rev. 67, Page 145 of 166 TALEN~ Brad Berryman Susquehanna Nuclear, LLC Sr. Vice President & Chief Nuclear Officer 769 Salem Boulevard Berwick, PA 18603 Tel 570.5422904 ENERGY brad.berryman@lalenenergy.com October 29, 2018 SUSQUEHANNA NUCLEAR LLC POLICY STATEMENT: SUSQUEHANNA STEAM ELECTRIC STATION EMERGENCY MANAGEMENT Immediate response, assessment, and the implementation of protective and corrective measures pertaining 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 occun*ence of an emergency, the Shift Manager on duty at the station sha11 assume the role of SSES EmergencyDirector, as described in the SSES Emergency Plan, untll telieved of that responsibility by the Emergency Director or his designated alternate. If the emergency requires activation of the Emergency Operations Facility (EOF), the SSES Recove1y Manager shall assume responsibility for overall management of the emergency and off-site Protective Action Recommendations: The SSES Emergency Director retains 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, artd the appropriate protective and corrective actions have been implemented. Following that critical period, but still with complete regard for health and safety, major 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

Emergency Plan, Rev. 67, Page 146 of 166 APPENDIX F DEVIATIONS TO NEI 99-01 REV. 6 Page 1 of 2

Emergency Plan, Rev. 67, Page 147 of 166 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. 67, Page 148 of 166 APPENDIX G SSES EVACUATION TIME ESTIMATES Page 1 of 2

Emergency Plan, Rev. 67, Page 149 of 166 NOTE: The Evacuation Time Estimate is incorporated by reference and can be found in the Susquehanna Information Management System. Annual reviews are stored.in ActionWay under Recurring Task X0262. Page 2 of 2

Emergency Plan, Rev. 67, Page 150 of 166 APPENDIX H DOWNSTREAM SUSQUEHANNA RIVER WATER USAGE Page 1 of 3

Emergency Plan, Rev. 67, Page 151 of 166 APPENDIX H 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. J.M. Smucker 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 people.

5. Merck & Co. Danville - 27.4 I Pr 7-9 Serves about 500 people. Large quantity for cooling, 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 emergencies.

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. Millersburg Water Co. Millersburg - 69.4 M Sb NA

12. Harrisburg 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. Wrightsville Water Co. Wrightsville - 119.0 M Pr NA

19. Columbia 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 Mgd.

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. 67, Page 152 of 166 APPENDIX H 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 Authority 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 LEGEND NA Not Available (SES) Steam Electric Station (HES) Hydroelectric Station (PS) Pumping Station (NS) Nuclear Station I Industrial M Municipal Pu Public Pr Primary Sb Standby Mgd Million gallons per day Page 3 of 3

Emergency Plan, Rev. 67, Page 153 of 166 APPENDIX I POPULATION UPDATE FOR SSES EMERGENCY PLANNING ZONE Page 1 of 2

Emergency Plan, Rev. 67, Page 154 of 166 REFER TO THE EVACATION TIME ESTIMATE IN APPENDIX G FOR THE CURRENT POPULATION INFORMATION Page 2 of 2

Emergency Plan, Rev. 67, Page 155 of 166 APPENDIX J NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN Page 1 of 10

Emergency Plan, Rev. 67, Page 156 of 166 NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN A. Assignment of Responsibility 1.a. Chapter 6, Section 6.0, Table 6.2, Appendix A 1.b. Chapter 4 Table 5.2 Chapter 6 1.c. Chapter 6, Figures 6.2, 6.3, 6.4, 6.6, 6.7 1.d. Chapter 6, Sections 6.2.1, 6.3.1.1 1.e. 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

3. Appendix A

4. Chapter 6, Sections 6.2.7, 6.3.1.3 B. Onsite Emergency Organization

1. Chapter 6, Sections 6.0 Phase I, II, III, 6.1, Tables 6.1, Figure 6.2, Figure 6.3

2. Chapter 6, Sections 6.0, 6.1 Appendix E

3. Chapter 6, Section 6.2.1

4. Chapter 6, Section 6.2.1

5. Chapter 6, Tables 6.1

6. Chapter 6, Figure 6.7 7.a. Chapter 6, Section 6.2.6 7.b. Chapter 6, Section 6.2.5, 6.5 7.c. Chapter 6, Section 6.2.1 7.d. Chapter 6, Section 6.3.2.1

8. Chapter 6, Table 6.2 Appendix A

9. Chapter 6, Table 6.2 Appendix A Page 2 of 10

Emergency Plan, Rev. 67, Page 157 of 166 NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN C. Emergency Response Support Resources 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 D. Emergency Classifications

1. Chapter 5, Sections 5.1, 5.2, Appendix D, Appendix F, Tables F, R, S, E, H, C in EP-RM-004, EAL Classification Basis.

2. Chapter 5, Table F, R, S, E, H, C in EP-RM-004, EAL Classification Basis.

E. Notification, Methods and Procedures

1. Chapter 6, Figure 6.7 Appendix C, Position Specific Instructions for:

x Control Room Emergency Plan Communicator x TSC Emergency Plan Communicator x EOF Communicator x Radiation Protection Coordinator x Technical Support Coordinator x Recovery Manager x Dose Assessment Supervisor

2. Appendix C, Position Specific Instructions for:

x Emergency Director x Control Room NRC Communicator x Control Room Emergency Plan Communicator x TSC Emergency Plan Communicator x Security Coordinator

3. Appendix C, Position Specific Instructions for:

x Control Room Emergency Plan Communicator x TSC Emergency Plan Communicator x EOF Communicator Page 3 of 10

Emergency Plan, Rev. 67, Page 158 of 166 NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN 4.a., b., c., k., n. Appendix C, Position Specific Instructions for: x Control Room Emergency Plan Communicator x TSC Emergency Plan Communicator x EOF Communicator 4.d., e., f., g., h., i., j., l. Appendix C, Position Specific Instructions for: x Radiation Protection Coordinator x Dose Assessment Supervisor 4.m. Appendix C, Instructions for: x TSC Security Coordinator x Offsite Organization Response to Plant Events

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 F. Emergency Communications

1. Chapter 6, Figure 6.7 Chapter 8, Sections 8.1.3.5, 8.2.2.4 1.a. Chapter 6, Sections Phase Ic), 6.2.3, 6.2.4e), 6.2.5g),

6.3.1.1i), 6.3.1.4e), 6.3.1.5, 6.4 Appendix C, Position Specific Instruction for: x Control Room Emergency Plan Communicator x TSC Emergency Plan Communicator x EOF Communicator x Radiation Protection Coordinator x Tech Support Coordinator x Recovery Manager x Dose Assessment Supervisor 1.b. Chapter 8, Sections 8.3.1, 8.3.2 1.c. Chapter 6, Sections Phase Ic), 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: x Control Room Emergency Plan Communicator x Control Room NRC Communicator x TSC Emergency Plan Communicator x TSC NRC Communicator x EOF Communicator Page 4 of 10

Emergency Plan, Rev. 67, Page 159 of 166 NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN 1.d. 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 1.e. Chapter 6, Sections Phase I, Phase II, Phase III, 6.2, 6.3 1.f. Chapter 8, Sections 6.2.1d, 6.3.1.1c, 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:

x Security Coordinator x Offsite Organization Response to Plant Events

3. Chapter 9, Sections 9.1.2, 9.3 G. Public Education and Information 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. Chapter 6, Section 6.3.2 Chapter 8, Section 8.2.1 3.b. Chapter 8, Section 8.2.1 4.a. Chapter 6, Section 6.3.2.1 4.b. Chapter 6, Sections 6.3.2, 6.3.2.1 4.c. Chapter 6, Section 6.3.2.1e)

5. Chapter 9, Section 9.4.2 H. Emergency Facilities and Equipment

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 III

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 Page 5 of 10

Emergency Plan, Rev. 67, Page 160 of 166 NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN 6.a., b. Chapter 7, Section 7.1, 7.1.1 6.c. Appendix C, Position Specific Instructions for: x Chemistry Coordinator x 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. 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)

I. Accident Assessment

1. Chapter 5, Table F, R, S, E, H, C in EP-RM-004, EAL Classification Basis Appendix F

2. Chapter 7, Section 7.1 3.a., b. Chapter 7, Section 7.1, 7.1.1.3

4. Chapter 7, Section 7.1, 7.1.1, 7.1.1.3

5. Chapter 7, Section 7.1.1.1

6. Chapter 7, Sections 7.1.1.3, 7.1.1.4

7. Chapter 7, Section 7.1, 7.1.1

8. Chapter 7, Section 7.1, 7.1.1.3

9. Chapter 7, Section 7.1.1.3 Appendix D, Enclosures 4, 5, 6

10. Chapter 7, Section 7.1.1, Table 7.3, 7.1.1.3 Page 6 of 10

Emergency Plan, Rev. 67, Page 161 of 166 NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN J. Protective Response 1.a., b., c., d. Chapter 7, Section 7.3, 7.3.1, 7.3.2 Appendix C, Position Specific Instruction for: x Control Room Emergency Plan Communicator x TSC Emergency Plan Communicator x Radiation Protection Coordinator x Security Coordinator x Control Room Emergency Director x TSC Emergency Director

2. Chapter 7, Section 7.3.1.4

3. Chapter 7, Section 7.3.1.4

4. Chapter 7, Sections 7.3.1.3, 7.3.1.4

5. Chapter 7, Sections 7.3.1, 7.3.1.3, 7.3.1.4 Appendix C, Position Specific Instructions for:

x Emergency Director x Security Controller 6.a. Chapter 7, Section 7.3.1 6.b. Chapter 7, Section 7.3.1 6.c. Chapter 6, Section 6.2.1k, 6.2.4l Chapter 7, Table 7.2

7. 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:

x Emergency Director x Radiation Protection Coordinator x Control Room Emergency Plan Communicator x TSC Emergency Plan Communicator x Recovery Manager x Dose Assessment Supervisor x Liaison Support Supervisor x EOF Communicator

8. Appendix G Page 7 of 10

Emergency Plan, Rev. 67, Page 162 of 166 NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN 10.a. Appendix C, Position Specific Instructions for: x RP Tech I (OSCAR) x Field Team Director x Monitoring Team x Environmental Sampling Team Appendix G Appendix H Chapter 7, Section 7.3.1.4 & Figure 8.1 10.b. Appendix G Appendix I 10.c. Chapter 7, Section 7.3.2 Chapter 8, Section 8.5.4 10.m. Chapter 7, Sections 7.3.2, Appendix G K. Radiological Exposure Control 1.a., b., c., d., e., f., g. Chapter 7, Section 7.4.3, Table 7.2 Appendix C, Position Specific Instructions for: x Security Coordinator x Radiation Protection Coordinator x RP Specialist

2. Chapter 6, Section 6.2.11, 6.2.1k, 6.2.4l Chapter 7, Section 7.2, Table 7.2 Appendix C, Position Specific Instructions for:

x Radiation Protection Coordinator 3.a. Chapter 7, Section 7.3 Appendix C, Position Specific Instructions for: x Radiation Protection Specialist x Radiation Protection Coordinator Appendix D, Enclosures 5,6,8 3.b. Appendix C, Position Specific Instructions for: x Radiation Protection Specialist x Radiation Protection Coordinator x Field Team Director x Monitoring Team x Environmental Sampling Team 5.a., b. Chapter 7, Section 7.3.1, 7.4.2 6.a., b., c. Chapter 7, Section 7.3.1, 7.4.2 Page 8 of 10

Emergency Plan, Rev. 67, Page 163 of 166 NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN

7. Chapter 7, Section 7.3.1.4, 7.4.2 L. Medical and 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:

x Security Coordinator M. Recovery and Reentry Planning and Postaccident Operations

1. Chapter 6, Sections Phase IV, 6.5 Appendix C, Position Specific Instructions for:

x Emergency Director x Recovery Manager x Termination and Restoration

2. Chapter 6, Section 6.5, Figure 6.6 Appendix C, Position Specific Instructions for:

x Emergency Director x Recovery Manager x Termination and Restoration

3. Chapter 6, Section 6.5

4. Section 6.2.5, 6.3.1.4 Appendix C, Position Specific Instructions for:

x Radiation Protection Coordinator x Dose Assessment Supervisor N. Exercises and Drills 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 Page 9 of 10

Emergency Plan, Rev. 67, Page 164 of 166 NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN O. Radiological Emergency Response Training

1. Chapter 9, Sections 9.1.1, Table 9.1 1.a. Chapter 9, Section 9.1.1, Table 9.1

2. Chapter 9, Section 9.1.2, Table 9.1

3. Chapter 9, Section 9.1 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 for the Planning Effort : Development, Periodic Review and Distribution of Emergency Plans

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 in EP-RM-004, EAL Classification Basis, 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

Emergency Plan, Rev. 67, Page 165 of 166 On-Shift Staffing Analysis APPENDIX K On-Shift Staffing Analysis Page 1 of 2

Emergency Plan, Rev. 67, Page 166 of 166 On-Shift Staffing Analysis NOTE: The On-Shift Staffing Analysis is incorporated by reference and can be found in the Susquehanna Information Management System. Page 2 of 2

Enclosure 2 to PLA-8077 10 CFR 50.54(q) Screens and Evaluations

Enclosure 2 to PLA-8077, Page 1 of 560 10 CFR 50.54(q) Screens and Evaluations Document ID Enclosure Page S2023-05-24-01 2 S2023-08-01-01 28 E2023-08-01-01 32 S2023-02-02-01 40 E2023-02-02-01 43 S2022-09-08-01 545 E2022-09-08-01 549 S2023-05-04-01 554 E2023-05-04-01 557

Enclosure 2 to PLA-8077, Page 2 of 560 Attachment A, 10CFR50.54q Screening Form Screening Number: S2023-05-24-01 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 a description of 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 SSES Emergency Plan Rev 66 (E-Plan) as part of the annual review process and in support of URI implementation (see attached markup):

1. This revision takes credit for the 2023 Annual Emergency Plan Review per AR-2023-00273.

This is an administrative change that does not affect the Emergency Plan.

2. Removed Security/ from title of Manager-Security/Emergency Preparedness throughout the document per DPA-07-DI-2023-02751.

This is an administrative change that does not affect the Emergency Plan.

3. Changed response pagers to Notification System in section 6.0, Phase I h) step per DPA-36-DI-2021-11192. (S / E2023-08-01-01)

4. Changed section 7.1.1.3 and Appendices B and C and deleted MIDAS from Figure 8.2 in support of URI implementation at SSES per DPA-13-DI-2022-01144. (see S / E2023-02-02-01)

5. Replaced Figure 8.1 with the updated C-2532 Sheet 1 with the new site boundary per ACT-01-CR-2023-02344. (see S / E2022-09-08-01)

6. Deleted reference to Hunlock Creek Ambulance Association from Appendix A per DPA-04-DI-2023-01542. (see S /E2023-05-04-01)

7. Deleted FSAR Figure 13.1-3 from Section A in Appendix J per DI-2023-02233.

8. Added EP-00-005, Termination and Restoration procedure to Appendix J Sections M.1 and M.2 per DI-2023-02233.

9. Corrected typo in Appendix J section M.4 per DI-2023-02233.

Appendix J includes a cross-reference between planning standard criteria in NUREG-0654 Rev 1 with the Emergency Plan sections and does not contain any technical details. The changes are reference omissions, corrections or deletions identified in 2023 NOS Audit and do not change the intent of the Appendix. Therefore, this is an editorial change per EP-102 procedure. Part II. Is Activity a Change per Section 3.1.3? ~ YES NO Does the activity constitute a change per definition 3.1.3 - An action that Continue to next part 10 CFR 50.54(q) Evaluation is NOT results in modification or addition to, or removal from the SSES required. Enter the plan? Emergency Plan, OR the resources, capabilities and methods identified in justification and complete Part VI. Justification: Electronic Form EP-102-1 Rev. 6, Page 1 of 3

Enclosure 2 to PLA-8077, Page 3 of 560 Part III. Is Activity Previously Reviewed? YES ~ NO Is this activity fully bounded by an NRC approved 10 CFR 50.90 submittal 10 CFR 50.54(q) Continue to next part Evaluation is NOT or Alert and Notification System Design Report (44 CFR 350.14)? required. Enter justification and If YES, identify bounding source document number/approval reference complete Part VI. and ensure the basis for concluding the source document fully bounds the proposed change is documented below: Justification: Bounding document attached (optional) Part IV. Editorial Change ~ YES 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: As discussed in Part I, changes 1, 2, and 7 through 9 are administrative or editorial changes and can be implemented with no further analysis while changes 3, 4, 5 and 6 were analyzed separately in S / E2023-08 01, S / E2023-02-02-01, S / E2022-09-08-01 and S /E2023-05-04-01, respectively. All these separate evaluations concluded that these changes can be implemented without prior NRC approval, as they do not decrease the effectiveness of the Emergency Plan and meet the 10CFR50.47(b) and Appendix E to part 50 criteria. 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 is assigned. [1]

2. The response organization has the staff to respond and to augment staff on a continuing basis (24/7 staffing) in accordance with the Emergency Plan. [1]

3. The process ensures that on shift emergency response responsibilities are staffed and assigned. [2]

4. The process for timely augmentation of on-shift staff is established and maintained. [2]

5. Arrangements for requesting and using off site assistance have been made. [3]

6. State and local staff can be accommodated at the EOF in accordance with the Emergency Plan. [3]

7. A standard scheme of emergency classification and action levels is in use. [4] (RSPS)

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 notifications. [5] (RSPS)

Electronic Form EP-102-1 Rev. 6, Page 2 of 3

Enclosure 2 to PLA-8077, Page 4 of 560 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 appropriate box.

9. Administrative and physical means have been established for alerting and providing prompt 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 licensees FEMA-approved ANS design report and supporting FEMA approval letter. [5] (RSPS)

11. Systems are established for prompt communication among principal emergency response organizations. [6]

12. Systems are established for prompt communication to emergency response personnel. [6]

13. Emergency preparedness information is made available to the public on a periodic basis within the plume exposure pathway Emergency Planning Zone (EPZ). [7]

14. Coordinated dissemination of public information during emergencies is established. [7]

15. Adequate facilities are maintained to support emergency response. [8]

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)

18. A range of public PARs is available for implementation during emergencies. [10] (RSPS)

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 authorities. [10] (RSPS)

20. KI is available for implementation as a protective action recommendation in those jurisdictions that chose to provide KI to the public [10]

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]

23. Arrangements are made for medical services for contaminated, injured individuals. [12]

24. Plans for recovery and reentry are developed. [13]

25. A drill and exercise program (including radiological, medical, health physics and other program areas) is established. [14]

26. Drills, exercises, & training evolutions that provide performance opportunities to develop, maintain, &

demonstrate key skills are assessed via a formal critique process in order to identify weaknesses. [14]

27. Identified weaknesses are corrected. [14]

28. Training is provided to emergency responders. [15]

29. Responsibility for Emergency Plan development and review is established. [16]

30. Planners responsible for Emergency Plan development and maintenance are properly trained. [16]

APPLICABILITY CONCLUSION If no Part V criteria are checked, a 10 CFR 50.54(q) Evaluation is NOT required; complete Part VI. If any Part V criteria are checked, complete Part VI and d perform perfor~ a JO CFR.50.54(q) 10 CFR 50.5* Evaluation. Part VI. Signatures: Adrian Miron 5/24/2023 Preparer Name (Print) (JFG EP109) Preparer Signature Date Cj..,,..;.,H~ Aug 14, 2023 Jessica Shoup Reviewer Name (Print) (JFG EP109) Reviewer Signature Date Electronic Form EP-102-1 Rev. 6, Page 3 of 3

Enclosure 2 to PLA-8077, Page 5 of 560 Emergency Plan, Rev. 66, Page 1 of 170 SUSQUEHANNA NUCLEAR, LLC SUSQUEHANNA STEAM ELECTRIC STATION EMERGENCY PLAN REVISION 66§.Z DATE: XX/XX/XXXX:10/06/2022 PORC MEETING: TBD22 18 86

Enclosure 2 to PLA-8077, Page 6 of 560 Emergency Plan, Rev. 66, Page 2 of 170 SUSQUEHANNA NUCLEAR, LLC SUSQUEHANNA STEAM ELECTRIC STATION TEAM SUSQUEH~"'NA Generating Excellence ._.,--..*..... -ritJii,,'

    . ..      -   * ** . 7 THIS DOCUMENT HAS BEEN UPDATED TO INCLUDE REVISIONS THROUGH-6666

Enclosure 2 to PLA-8077, Page 7 of 560 Emergency Plan, Rev. 66, Page 3 of 170 AFFECTED PAGES OR SECTIONS NOTE: 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. This revision takes credit for the 2023 Annual Emergency Plan Review per AR-2023-00273.

(S2023-05-24-01)

2. Removed "Security/" from title of Manager-Security/Emergency Preparedness throughout the document per DPA-07-Dl-2023-02751. (S2023-05-24-01)

3. Changed "response pagers" to "Notification System" in section 6.0, Phase I h) step per DPA-36-Dl-2021-11192. (S / E2023-08-01-01)

4. Changed section 7.1.1.3 and Appendices B and C and deleted MIDAS from Figure 8.2 in support of URI implementation at SSES per DPA-13-Dl-2022-01144. (SI E2023-02-02-01)

5. Replaced Figure 8.1 with the updated C-2532 Sheet 1 with the new site boundary per ACT-01-CR-2023-02344. (SI E2022-09-08-01)

6. Deleted reference to Hunlock Creek Ambulance Association from Appendix A per DPA-04-Dl-2023-01542. (S /E2023-05-04-01)

7. Deleted FSAR Figure 13.1-3 from Section A in Appendix J per Dl-2023-02233. (S2023-05 QD

8. Added EP-00-005, Termination and Restoration procedure to Appendix J Sections M.1 and M.2 per Dl-2023-02233. (S2023-05-24-01)

9. Corrected typo in Appendix J section M.4 per Dl-2023-02233. (S2023-05-24-01)

1. Re1.iision 66 takes credit for the 2022 Annual Emergency Plan Review. (82022 0Q 06 01)

2. Added definition of primary system per NEI QQ 01 guidance per AR 2022 03384. (Editorial)

3. Modify the Emergency Plan to use common terminology for press briefings and news bulletins per AR 2021 10928. (E2022 0Q 06 01)

4. Added Revision 1 to NUREG 0654 in reference section per AR 2021 01890. (Editorial)

5. Removed population information in Figure 4.1 and 4.2 per AR 2022 13603. (Editorial)

6. Removed reference to Table Fin section 5.1.1 of the Emergency Plan as there is no NOUE in respective table per AR 2021 05447 (E2014 10 2Q 01 and 2016 SER Docket Nos. 50 387 and 50 388)

7. Removed the word "l=lorizontal" in 2 places in section 5.2.11 per DPA 01 DI 2019 14058.

(Eval E201 Q 04 03 01 Rev 1)

8. Revise 6.2.2 (C) of Emergency Plan to add "s" to communicator. AR 2022 13655 (Editorial)

Q. Removed", and VERMS Maintenance Interface Terminal" from section 8.1.3.1 per DPA 02 DI 2020 15633 and E2013 0Q 03 01 Rev 2.

10. Updated Figure 8.3 to current map of EOFJJIC/ Alt TSC per AR 2022 13660. (Editorial)

11. Revised section Q.1.2 to remo*.ie reference to 10 CFR 50.54 (hh)(1) and 10 CFR 50.54 (hh)(2) and replaced with requirements for 10 CFR 50.155 demonstration per DPA 01 DI 2022 00770.

(Conforming Change)

12. Formatted table 9.1 section 6 training with the departments listed per DPA 01 DI 2021 15414.

(Editorial)

Enclosure 2 to PLA-8077, Page 8 of 560 Emergency Plan, Rev. 66, Page 20 of 170 2.46 LLRWHF- Low Level Radwaste Holding Facility 2.47 LOCA- Loss of Coolant Accident 2.48 MOCA- Monitored Owner Controlled Area ~ MIDAS Meteorological Information and Dose Assessment System 2.50 MSIV- Main Steam Isolation Valve 2.51 MSL- Main Steam Line 2.52 NEP- Nuclear Emergency Planning 2.53 NRC- Nuclear Regulatory Commission 2.54 NRP- National Response Plan 2.55 NSRB Nuclear Safety Review Board 2.56 NSSS- Nuclear Steam Supply System 2.57 ODCM- Offsite Dose Calculation Manual 2.58 ORO Offsite Response Organization 2.59 OSC- Operations Support Center 2.60 PAGS- Protective Action Guides from EPA 2.61 PEMA- Pennsylvania Emergency Management Agency 2.62 PORC- Plant Operations Review Committee 2.63 PPL- PPL Corporation 2.64 PSP- Pennsylvania State Police 2.65 RCA- Radiologically Controlled Area 2.66 RCIC- Reactor Core Isolation Cooling 2.67 RDAS- Remote Data Analysis System 2.68 RHR- Residual Heat Removal 2.69 RPS- Reactor Protection System 2.70 RX- Reactor 2.71 SAS- Secondary Alarm Station 2.72 SDE- Shallow Dose Equivalent 2.73 SDS- Satellite Display System 2.74 SEIC- Susquehanna Energy Information Center 2.75 SGTS- Standby Gas Treatment System 2.76 SLC- Standby Liquid Control 2.77 SOCA- Security Owner Controlled Area 2.78 SPDS- Safety Parameter Display System 2.79 SSE- Safe Shutdown Earthquake 2.80 SSES Susquehanna Steam Electric Station 2.81 SSES URI Unified RASCAL Interface customized for SSES 2.81 Susquehanna Susquehanna Nuclear, LLC (subsidiary company of Talen Energy Corporation) 2.82 TEDE- Total Effective Dose Equivalent 2.83 TR- Temperature Recorder 2.84 TSC- Technical Support Center 2.85 UMC- Unit Monitoring Console (PCS) 2.86 UPS- Uninterruptible Power Supply 2.87 USDA- United States Department of Agriculture 2.88 VERMS Vent Effluent Radiation Monitoring System Page 2 of 2

Enclosure 2 to PLA-8077, Page 9 of 560 Emergency Plan, Rev. 66, Page 44 of 170 6.0 ORGANIZATIONAL CONTROL OF EMERGENCIES 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. 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 pagersNotification System 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. Page 1 of 19

Enclosure 2 to PLA-8077, Page 10 of 560 Emergency Plan, Rev. 66, Page 74 of 170 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 offsite doses to the public based on evaluation of isotope specific release rates and 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 3 of 10

Enclosure 2 to PLA-8077, Page 11 of 560 Emergency Plan, Rev. 66, Page 75 of 170 The dose calculation model used is a fast running, time dependent, variable trajectory plume segment "B" model with the following capabilitieshas the following characteristics typical of a class B model: NOTE: A class "B" model is a numerical model that represents the actual spatial and temporal variations of plume distribution.

Computes The atmospheric dispersion at the site calculation uses real-time site specific meteorological data to compute plume dispersion, deposition, and depletion using a combination of straight line and trajectory puff (LaGrangean) Gaussian models.based on atmospheric stability as a function of site specific terrain conditions with 15 minute upgrades of source term and meteorological conditions .
Estimates release rates by isotope based on atmospheric stabilityreal-time plant measurements and alternate backup methods.

             -Computes plume trajectory as a function of site specific terrain conditions with 15 minute upgrades of source term and meteorological conditions.

Provides estimates of deposition and relafr.ie concentration of radioactivity within the plume e*posure and ingestion EPZs for the duration of the release.

Incorporated in the calculations ispuff model.
Includes wet and dry deposition which enables dose estimates from three pathi.*1ays plume, ground shine, and ingestion.
Calculates Total Effective Dose Equivalent (TEDE) and child thyroid Committed Dose Equivalent (CDE) based on the evaluated release rates and the dispersion model.
Provides a summary of offsite consequences with spatial distribution of consequences throughout the planning zone.
Provides estimates of deposition and relatii.*e concentration of radioacti 11ity within the plume e*posure 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.

Page 4 of 10

Enclosure 2 to PLA-8077, Page 12 of 560 Emergency Plan, Rev. 66, Page 76 of 170 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 CDE. However adult physiology is used in calculating thyroid CDE for purposes of evaluating the need 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 optionsresults are availableprovided:

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 CDE dosePlume exposure rates for field team management.
Fifty year child thyroid committed dose (CDE1, from inhalation of radioactive materials.
Population dose (person rem) out to 50 miles .

                    .!...._Summary print of release rates, projected doses, and calculation basis for each of four projection times .

Plume plotting of the TEDE and CDE thyroid dose distribution.
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 , Alternate TSC and EOF. The dose assessment program also has the capacity to integrate the time dependent releases and local meteorology over the course of a release event and provide a summary of offsite consequence estimates for the entire event. This integrated event assessment includes TEDE, child thyroid CDE and isotope specific deposition spatially distributed throughout the planning zone radius. 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. Page 5 of 10

Enclosure 2 to PLA-8077, Page 13 of 560 Emergency Plan, Rev. 66, Page 107 of 170 1

                                                                   ,[i
                                          --.I!' I...Jii. 111** ~*n **
           *       :J\i;,,
             "'o,jitl.*
                     '  ~* *--     ,.

Page 1 of 3

Enclosure 2 to PLA-8077, Page 14 of560 Emergency Plan, Rev. 66, Page 108 of 170 P.Pl, PROPER!"( LINE 1-xxx 101/(NSHlP ROAJS ctosr:sr SITE BOU~IDI.RY r,ISTA"/Gf: (FEET) EPB DI~TA,-.,cE BOUNDEO BY ~OUTE 11 (FEE>} ()l REFERENCE f'Dll,(TS*

                                          *REFERENCE POUITS ARE NEr\RB'r' LOCAl!ONS WITH C

l"OTENTIJIJ...l'( s1rn-11F1CANT OCCUPAMCY Bl' MEMclfP.5 OF iHE" PUBUq ensm "OM Lfi..~O L!SE CENSUS INFOIU,tATlON. D E G H

              .', 2 Figure 8.1 Page 2 of 3

Enclosure 2 to PLA-8077, Page 15 of 560 Emergency Plan, Rev. 66, Page 109 of 170 MAP OF THE SUSQUEHANNA SES EMERGENCY FACILITIES Page 3 of 3

Enclosure 2 to PLA-8077, Page 16 of 560 Emergency Plan, Rev. 66, Page 110 of 170 NUCLEAR REGULATORY COMMISSION u SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND2 EMERGENCY PLAN ffi ffi Technical Support Center FLOOR PLAN FIGUREB.2

             ~              Typical work station including desk, chair,            Field Team
             ~         []   telephone as necessary for            Radio            Indicates telephone-may be a standard telephone. May also represent FTS emergency response for                               phone.

rn the listed positions.

       ~               []
             ~         []                                    Venns Interface Administrative Coordinator Security Coordinator TSC Dose Calculator
             ~ []         HPN Communicator Radiation Protection Coordinator Emergency Director TSC Emergency Plan Communicator
             ~ []         TSC NRC Communicator Operations Coordinator Technical Support Coordinator Damage Control Team Coordinator

[] rn

0 rnm f-----------------j

       ~               0
             ~

Engineering Support Area rnm TERMIN AL Cabiret Computer NSSS Engineer Core thermal Hydraulic Engineer Electrical/I& C Engineer rnm Symbol for Computer Fill llfl Station- b!UI U ws PICSY SPDS (Symbol is not necessarily Engineering indicative of the specific Support Area number of computer installations. The symbol designates a typical installation) Elevator Page 1 of 2

Enclosure 2 to PLA-8077, Page 17 of 560 Emergency Plan, Rev. 66, Page 111 of 170 NUCLEAR REGULATORY COMMISSION u SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND2 EMERGENCY PLAN ffi ffi Technical Support Center FLOOR PLAN FIGURE 8.2

          ~          Typical work station including desk, chair,          Field Team telephone as necessary for          Radio           Indicates telephone-may be a standard
          ~          emergency response for telephone. May also represent FTS phone.

rn the listed positions.

      ~         
          ~                                        Verms Interface Administrative Coordinator Security Coordinator TSC Dose Calculator
          ~       HPN Communicator Radiation Protection Coordinator Emergency Director TSC Emergency Plan Communicator
          ~       TSC NRC Communicator Operations Coordinator Technical Support Coordinator Damage Control Team Coordinator
          ~

rn

rn~ 1---------10

      ~         
          ~                                                             TERMINAL Cabinet Engineering Support Area NSSS Engineer Core 1hermal Hydraulic Engineer Computer      Electrical/I& C Engineer                                          Symbol for Computer rnl m ws                                                                            Station-PICSY SPDS (Symbol is not necessarily Engineering                                       indicative of the specific Support Area                                      number of computer installations . The symbol designates a typical installation)
                                         ~              Elevator Page 2 of 2

Enclosure 2 to PLA-8077, Page 18 of 560 Emergency Plan, Rev. 66, Page 118 of 170 9.1.3 Overall Coordination of Nuclear Emergency Preparedness 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 Page 5 of 7

Enclosure 2 to PLA-8077, Page 19 of 560 Emergency Plan, Rev. 66, Page 119 of 170 9.2 REVIEW AND UPDATING 9.2.1 SSES Emergency Plan 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 10CFR50.54t.
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 10CFR50 Appendix E Section IV and NUREG 0654 Element J.8 requirements are maintained. Update the full ETE should the criteria from Appendix Ebe met and re-submit the ETE to the NRC.

9.2.2 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.
Controlled copies of procedure revisions are issued by station document control programs.
ERO personnel are briefed on revisions as required.

Page 6 of 7

Enclosure 2 to PLA-8077, Page 20 of 560 Emergency Plan, Rev. 66, Page 120 of 170 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 Nuclear Emergency Preparedness staff.

9.4.4 Other Distributed Publication(s) 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 7

Enclosure 2 to PLA-8077, Page 21 of 560 Emergency Plan, Rev. 66, Page 124 of 170 LETTERS OF AGREEMENT 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 Volunteer Fire Department Columbia County Commissioners Don E. Bower, Inc Department of Environmental Protection/Bureau of Radiation Protection Federal Radiation Monitoring and Assessment Center (FRMAC) GE BWR Emergency Support Geisinger Ambulance Geisinger Bloomsburg Hospital Geisinger Medical Center Hobbie Volunteer Fire Co. - EMS l=lunlosk Creek Ambulanse Assosiation Institute of Nuclear Power Operations Lackawanna County Commissioners Latona Trucking Luzerne County Council Medico Construction Equipment Inc. 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

Enclosure 2 to PLA-8077, Page 22 of 560 Emergency Plan, Rev. 66, Page 125 of 170 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~_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: Reference Action Request 1066721 for why separate LOA is not needed for Pennsylvania State Police. Page 3 of 3

Enclosure 2 to PLA-8077, Page 23 of 560 Emergency Plan, Rev. 66, Page 128 of 170 DOSE/DISTANCE PLOTS The dose/distance plots have been removed and reference to the use of MIDAS SSES URI as the approved methodology/tool for determining magnitude of and for continually assessing the impact of the release. MIDAS SSES URI has the capability to provide assessments using event-specific fuel damage estimates. Additionally, MIDAS the code 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 4

Enclosure 2 to PLA-8077, Page 24 of 560 Emergency Plan, Rev. 66, Page 131 of 170 APPENDIXC SSES EMERGENCY PLAN POSITION SPECIFIC PROCEDURES (TYPICAL) EMERGENCY PLAN POSITION SPECIFIC PROCEDURES (Response Procedures) CR Procedures EOF Procedures Emergency Director Recovery Manager Emergency Plan Communicator EOF Support Supervisor NRC Communicator NEP Duty Planner EOF Emergency Plan Communicator TSC Procedures Environmental Sampling Team Emeroency Director Radiolooical Monitorino 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 Sampling Director TSC Administrative Coordinator EOF Technical Advisor TSC E Plan Communicator Engineering Support Supervisor HPN Communicator Fuels Lead Engineer / Core Thermal Hydraulics Engineer RP II Dose Calculator EOF Systems Lead Enoineer Damaoe Control Team Coordinator EOF Support Enoineer TSC NRC Communicator TSC Information Coordinator JIC Procedures Fuels Lead Engineer/ Core Thermal Public Information Manager Hydraulics Enoineer TSC RP Radio Communicator News Manaoer JIC Technical Briefer Support Services Manager OSC Procedures Media & Public Officials Contact OSC Coordinator JIC Logkeeper RP Specialist JIC Writer Maintenance Foreman/Field Unit Supervisor JIC Administrative Coordinator Chemistry Coordinator OTHER EMERGENCY PLAN RESPONSE PROCEDURES 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 MIQAS N6JURI User Manual Personnel Accountability Page 2 of 2

Enclosure 2 to PLA-8077, Page 25 of 560 Emergency Plan, Rev. 66, Page 160 of 170 NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN A Assignment of Responsibility 1.a. Chapter 6, Section 6.0, Table 6.2, Appendix A 1.b. Chapter 4 Table 5.2 Chapter 6 1.c. Chapter 6, Figures 6.2, 6.3, 6.4, 6.6, 6.7 i;;sAR i;;iij~Fe ~ 3. ~ 3 1.d. Chapter 6, Sections 6.2.1, 6.3.1.1 1.e. 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

3. Appendix A

4. Chapter 6, Sections 6.2.7, 6.3.1.3 B. Onsite Emergency Organization

1. Chapter 6, Sections 6.0 Phase I, II, Ill, 6.1, Tables 6.1, Figure 6.2, Figure 6.3

2. Chapter 6, Sections 6.0, 6.1 Appendix E

3. Chapter 6, Section 6.2.1

4. Chapter 6, Section 6.2.1

5. Chapter 6, Tables 6.1

6. Chapter 6, Figure 6. 7 7.a. Chapter 6, Section 6.2.6 7.b. Chapter 6, Section 6.2.5, 6.5 7.c. Chapter 6, Section 6.2.1 7.d. Chapter 6, Section 6.3.2.1

8. Chapter 6, Table 6.2 Appendix A

9. Chapter 6, Table 6.2 Appendix A Page 2 of 10

Enclosure 2 to PLA-8077, Page 26 of 560 Emergency Plan, Rev. 66, Page 167 of 170 NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN

7. Chapter 7, Section 7.3.1.4, 7.4.2 L. Medical and 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:

x Security Coordinator M. Recovery and Reentry Planning and Postaccident Operations

1. Chapter 6, Sections Phase IV, 6.5 Appendix C, Position Specific Instructions for:

x Emergency Director x Recovery Manager x Termination and Restoration

2. Chapter 6, Section 6.5, Figure 6.6 Appendix C, Position Specific Instructions for:

x Emergency Director x Recovery Manager x Termination and Restoration

3. Chapter 6, Section 6.5

4. Section 6.2.45, 6.3.1.4 Appendix C, Position Specific Instructions for:

x Radiation Protection Coordinator x Dose Assessment Supervisor N. Exercises and Drills 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 Page 9 of 10

Enclosure 2 to PLA-8077, Page 27 of 560 S2023-05-24-01 EPlan rev 67 Final Audit Report 2023-08-15 Created: 2023-08-10 By: Adrian Miron (Adrian.Miron@TalenEnergy.com) Status: Signed Transaction ID: CBJCHBCAABAAxskhfeR3nTjw_aXfmiYFbrVFS70v3SAj "S2023-05-24-01 EPlan rev 67" History

~ Document created by Adrian Miron (Adrian.Miron@TalenEnergy.com) 2023-08-10-4:05:09 PM GMT- IP address: 50.122.98.202 f2.. Document emailed to Jessica Shoup Uessica.shoup@talenenergy.com) for signature 2023-08 4:06:30 PM GMT
~ Email viewed by Jessica Shoup Uessica.shoup@talenenergy.com) 2023-08 0:51:05 AM GMT- IP address: 75.192.186.96 0c) Document e-signed by Jessica Shoup Uessica.shoup@talenenergy.com)

Signature Date: 2023-08 0:52:21 AM GMT - Time Source: server- IP address: 75.192.186.96 9 Agreement completed. 2023-08 0:52:21 AM GMT II Adobe Acrobat Sign

Enclosure 2 to PLA-8077, Page 28 of 560 Attachment A, 10CFR50.54q Screening Form Screening Number: S2023-08-01-01 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 a description of the revised text (attaching a mark-up of the existing text with proposed change can be used as an alternative): Discontinue the use of pagers within the Emergency Response Organization (ERO) as a means of notification to the ERO of an emergency event at Susquehanna. The pager and backup means (Motorola Vesta Communicator NXT!) will be replaced by Everbridge. Specifically, Changing the Emergency Plan Section 6.0 (Phase 1 (h)) from "These notifications are made, via the activation of ERO Response pagers or by telephone back up, to individuals designated for off-duty availability status (i.e. on-call) to fill key emergency response positions." to "These notifications are made, via the activation of ERO Response System or by telephone back up, to individuals designated for off-duty availability status (i.e. on-call) to fill key emergency response positions." Part II. ls Activity a Change per Section 3.1.3? [8JYES NO Does the activity constitute a change per definition 3.1.3 - An action that Continue to next part 10 CFR 50.54(q) Evaluation is NOT results in modification or addition to, or removal from the SSES required. Enter Emergency Plan, OR the resources, capabilities and methods identified in justification and the plan? complete Part VI. Justification: Part Ill. Is Activity Previously Reviewed? YES [8J NO Is this activity fully bounded by an NRC approved 10 CFR 50.90 submittal 10 CFR 50.54(q) Continue to next part Evaluation is NOT or Alert and Notification System Design Report (44 CFR 350.14)? required. Enter justification and If YES, identify bounding source document number/approval reference complete Part VI. and ensure the basis for concluding the source document fully bounds the proposed change is documented below: Justification: D Boundinq document attached (optional) Part IV. Editorial Change YES [8J 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 aooropriate box.

1. Responsibility for emergency response is assigned. [1]

2. The response organization has the staff to respond and to augment staff on a continuing basis (24/7 staffinq) in accordance with the Emerqencv Plan. [11

3. The process ensures that on shift emergency response responsibilities are staffed and assigned. [2]

4. The process for timely augmentation of on-shift staff is established and maintained. [2] ~

5. Arrangements for requesting and using off site assistance have been made. [3]

6. State and local staff can be accommodated at the EOF in accordance with the Emergency Plan. [3]

Electronic Form EP-102-1 Rev. 6, Page 1 of 3

Enclosure 2 to PLA-8077, Page 29 of 560

7. A standard scheme of emergency classification and action levels is in use. [4] (RSPS)

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 notifications. [51 (RSPS) Electronic Form EP-102-1 Rev. 6, Page 2 of 3

Enclosure 2 to PLA-8077, Page 30 of 560 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 appropriate box.

9. Administrative and physical means have been established for alerting and providing prompt 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 design report and supporting FEMA approval letter. [5] (RSPS) 11 . Systems are established for prompt communication among principal emergency response [8]

orqanizations. [61

12. Systems are established for prompt communication to emergency response personnel. [6]

13. Emergency preparedness information is made available to the public on a periodic basis within the plume exposure pathway Emergency Planning Zone (EPZ). [7]

14. Coordinated dissemination of public information during emergencies is established. [7]

15. Adequate facilities are maintained to support emergency response. [8]

16. Adequate equipment is maintained to support emergency response. [8] [8]

17. Methods, systems, and equipment for assessment of radioactive releases are in use. [9] (RSPS)

18. A range of public PARs is available for implementation during emergencies. [1 O] (RSPS)

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 authorities. [101 (RSPS)

20. Kl is available for implementation as a protective action recommendation in those jurisdictions that chose to provide Kl to the public [1 OJ

21. A range of protective actions is available for plant emergency workers during emergencies, including those for hostile action events.[101

22. The resources for controlling radiological exposures for emergency workers are established. [11]

23. Arrangements are made for medical services for contaminated, injured individuals. [12]

24. Plans for recovery and reentry are developed. [13]

25. A drill and exercise program (including radiological, medical, health physics and other program areas) is established. [141

26. Drills, exercises, & training evolutions that provide performance opportunities to develop, maintain, &

demonstrate key skills are assessed via a formal critique process in order to identify weaknesses. [141

27. Identified weaknesses are corrected. [14]

28. Training is provided to emergency responders. [15]

29. Responsibility for Emergency Plan development and review is established. [16]

30. Planners responsible for Emergency Plan development and maintenance are properly trained. [16]

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 any Part V criteria are checked, complete Part VI and perform a 10 CFR 50.54(Q) Evaluation . Part VI. Signatures: Patrick M. Gilligan

                                                             /qJPJ           /);J.A ,~                        08/01/23 Preparer Name (Print) (JFG EP109)                                Preparer Signature'                        Date Jessica Shoup                                                 q~ HS-fi.rur                                Aug 23, 2023 Reviewer Name (Print) (JFG EP109)                               Reviewer Signature                          Date Electronic Form EP-102-1 Rev. 6, Page 3 of 3

Enclosure 2 to PLA-8077, Page 31 of 560 S2023-08-01-01 Discontinue use of Pagers and Everbridge Transition Final Audit Report 2023-08-23 Created: 2023-08-23 By: Patrick Gilligan (Patrick.Gilligan@TalenEnergy.com) Status: Signed Transaction ID: CBJCHBCAABAAZtAcoP3YZJS3MuY5q5jsN4U5KB6wn_4D "S2023-08-01-01 Discontinue use of Pagers and Everbridge Tra nsition" History ~ Document created by Patrick Gilligan (Patrick.Gilligan@TalenEnergy.com) 2023-08 4:05:40 PM GMT- IP address: 12.40.226.114 181.. Document emailed to Jessica Shoup Uessica.shoup@talenenergy.com) for signature 2023-08 4:06:15 PM GMT ~ Email viewed by Jessica Shoup Uessica.shoup@talenenergy.com) 2023-08 7:40:33 PM GMT- IP address: 131.89.232.254 ~ Document e-signed by Jessica Shoup Uessica.shoup@talenenergy.com) Signature Date: 2023-08 9:03:25 PM GMT - Time Source: server- IP address: 131.89.232.254 fl'J Agreement completed. 2023-08 9:03:25 PM GMT a Adobe Acrobat Sign

Enclosure 2 to PLA-8077, Page 32 of 560 Attachment B, 10CFR50.54q Evaluation Checklist Evaluation Number: E2023-08-01-01 I Screen Number: S2023-08-01-01 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): Discontinue the use of pagers within the Emergency Response Organization (ERO) as a means of notification to the ERO of an emergency event at Susquehanna. The pager and backup means (Motorola Vesta Communicator NXT!) will be replaced by Everbridge. Specifically, Changing the Emergency Plan Section 6.0 (Phase 1 (h)) from These notifications are made, via the activation of ERO Response pagers or by telephone back up, to individuals designated for off-duty availability status (i.e. on-call) to fill key emergency response positions. to These notifications are made, via the activation of ERO Response System or by telephone back up, to individuals designated for off-duty availability status (i.e. on-call) to fille key emergency response positions. Part II. Evaluation of the Proposed Change for Compliance with the requirements of 10 CFR 50.47(b) and 10 CFR 50 Appendix E: Evaluation of 10CFR50.47(b) requirements associated with Emergency Planning Standard [2]: 10CFR 50.47(b)(2) - Onsite Emergency Organization - The process for timely augmentation of on-shift staff is established and maintained. Use of a cell phone in place of a pager/beeper maintains the planning function. Contacting augmenting ERO members through the Everbridge activation of cell phones has been determined to be as timely and effective as the use of a pager/beeper. Cell phone coverage (cell towers) is more widespread and has shown to be more reliable than pager coverage (pager towers). By using cell phone (voice and SMS) for notification and communicating with the ERO in lieu of commercial paging, the coverage and reliability of the process is improved. The process still involves the all call activation of the ERO via the activation of all of the provided means of notifying the employee (work, home, cell phone, email, etc.). Commercial paging capability has degraded over the years and is no longer as reliable as the ever-expanding cell phone coverage. Evaluation of 10CFR50.47(b) requirements associated with Emergency Planning Standard [5]: 10 CFR 50.47(b)(5) - Procedures have 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 followup messages to response organizations and the public has been established; and means to provide early notification and clear instruction to the populace within the plume exposure pathway Emergency Planning Zone have been established. The use of cell phones to contact augmenting ERO members maintains this planning function. Everbridge will now "ring" the cell phone as the first contact, which allows the ERO member to simply answer the text message or call, and respond immediately. The system will record their response and allow for the organization to know who received the message. If the system does not get a response from the individual, the process is auto-restarted up to 5 times until a response is received by design. With the use of pagers/beepers, the message was sent to the device with no callback number, the on-call ERO member would not call into the system and just respond. It was unknown until the on-call person shows up at the facility, that the message was received. Susquehanna has used a back up system, Communicator!NXT, for years to secure a back up in each position. The activation of the back up system, activates the pagers, sends a text and requires the second responder to call into the system and answer numerous questions. This process secures the second person if the on-call person does not get the message or is incapacitated. Communicator!NXT has shown the ERO member contact time (which supports ERO augmentation time) is improved with the use of cell phones. The switch from Communicator!NXT to Everbridge will not affect the expected response due to Everbridge being an updated product with more capabilities to activate the system, maintain the contact information and has platforms to expand notification capabilities. The system has been used by Talen Corporate and Susquehanna for years to provide notifications in both drills and real events across the enterprise. Electronic Form EP-102-2, Rev. 4, Page 1 of 7

Enclosure 2 to PLA-8077, Page 33 of 560 The process for activating ERO will basically remain the same when pagers are eliminated. The Control Room will activate Everbridge scenario only contacting the on-call personnel versus just activating all pagers. Security will activate a second scenario, seeking a backup responder incase the on-call person is not contacted or incapacitated versus activating Communicator!NXT seeking 1 backup responder. Evaluation of 10CFR50.47(b) requirements associated with Emergency Planning Standard [6]: 10 CFR 50.47(b)(6) - Provisions exist for prompt communications among principal response organizations to emergency personnel and to the public. Per Regulatory Guide 1.219, Section 4.6, "a change to ERO callout processes or hardware could require prior NRC approval if it would delay ERO notification such that the augmentation times in the emergency plan can no longer be achieved." This change replaces the pager with a cell phone as the primary device for contacting ERO members to support augmentation times. Everbridge will now "ring" the cell phone as the first contact, which allows the ERO member to simply answer the text message or call and respond immediately. The system will record their response and allow for the organization to know who received the message. If the system does not get a response from the individual, the process is auto restarted up to 5 times until a response is received by design. Several years of testing using response by cell phone contact has shown the ERO member contact time (which supports ERO augmentation time) is improved with the use of cell phones. Regulatory Guide 1.219, Section 4.6 also states that "a change could require prior NRC approval if it adjusts the frequency of communication testing or maintenance to a level that the site's experience with system reliability does not support." Testing of the functionality of Susquehanna contacting individual cell phones will continue to be required monthly, as stated in Section 9.1.2. The use of cell phones in place of pagers also continues to support the 10 CFR 50.47(b)(6), "Emergency Communications" planning standard of "systems are established for prompt communication to emergency response personnel." As discussed above, ERO member contact time (which supports ERO augmentation time) is improved with the use of cell phones. Evaluation of 10CFR50.47(b) requirements associated with Emergency Planning Standard [8]: 10 CFR 50.47(b)(8) - Adequate emergency facilities and equipment to support the emergency response are provided and maintained. The use of cell phones to contact augmenting ERO members maintains this planning function. The Everbridge system now "rings" the cell phone as the first contact, which allows the ERO member to simply answer the text message, and respond immediately. With the use of pagers/beepers, the message was sent to the device with no callback number and no means of knowing the responder was responding. If the text message is not answered under the new process, the cell phone will then receive a call and voice mail that indicates the emergency condition, and provides a callback number. Several years of testing using response by cell phone contact has shown the ERO member contact time (which supports ERO augmentation time) is improved with the use of cell phones. Evaluation of Sections IV.A. and IV.C of 10CFR50 Appendix E requirements associated with Emergency Planning Standard [2]: IV.A The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization and the means for notification of such individuals in the event of an emergency. By using cell phone (voice and SMS) for notification and communicating with the ERO in lieu of commercial paging, the coverage and reliability of the process is improved. The process still involves the all call activation of the ERO via the activation of all of the provided means of notifying the employee (work, home, cell phone, email, etc.). Commercial paging capability has degraded over the years and is no longer as reliable as the ever expanding cell phone coverage. Electronic Form EP-102-2, Rev. 4, Page 2 of 7

Enclosure 2 to PLA-8077, Page 34 of 560 IV.C Activation of Emergency Organization Was reviewed and is not applicable to the change. Evaluation of Sections IV.D.1 and IV.D.3 of 10CFR50 Appendix E requirements associated with Emergency Planning Standard [5]: IV.D

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 protective measures, should they become necessary, shall be described.

Was reviewed and is not applicable to the change.

2. A licensee shall have the capability to notify responsible State and local governmental agencies within 15 minutes after declaring an emergency.

Was reviewed and is not applicable to the change. Evaluation of Sections IV.E.1-4, IV.E.8, and IV.G of 10CFR50 Appendix E requirements associated with Emergency Planning Standard [8]: IV.E.1-4 Adequate provisions shall be made and described for emergency facilities and equipment, including: Was reviewed and is not applicable to the change. IV.E.8 Was reviewed and is not applicable to the change. IV.G 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. Was reviewed and is not applicable to the change. 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 [2] from 10CFR50.54(q) Screening Form:

The process for timely augmentation of onshift staff is established and maintained.

Use of a cell phone in place of a pager maintains the planning function. Contacting augmenting ERO members through the Susquehanna activation of cell phones has been determined to be as timely and effective as the use of a pager/beeper. Cell phone coverage (cell towers) is more widespread and has shown to be more reliable than pager coverage (pager towers). NUREG-0654 Section II.B Program Elements associated with the above Emergency Planning Standard [2]:

The licensee must be able to augment on-shift capabilities within a short period after declaration of an emergency.

The process by which the new system will notify ERO will still meet the timeliness requirements to activate. The change does not increase the augmentation time to or greater than 10 minutes. There is increased time from picking up the phone and hitting a button to opening an application, selecting the notification and sending the notification but it does not meet NUREG 1-219 requirements that constitute a change that requires NRC approval. The new process will not impede on those timeframes. Emergency Planning Functions [5] from 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 Electronic Form EP-102-2, Rev. 4, Page 3 of 7

Enclosure 2 to PLA-8077, Page 35 of 560 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 licensees FEMA-approved ANS design report and supporting FEMA approval letter.

Was reviewed and is not applicable to the change. NUREG-0654 Section II.E Program Elements and Appendix 3 associated with the above Emergency Planning Standard [5]:

Each organization shall establish procedures for alerting, notifying and mobilizing emergency response personnel.

Procedures affected by the change have been identified and will comply with NUREG-0654 Section II.E. The procedures for notification are in place and will be upgraded accordingly once the change is evaluated. The change from pagers to a system in the Emergency Plan allows Susquehanna to continue to notify personnel if they do not receive the message on the first attempt. The system will give a text message, phone call and email on initial notification, then repeat that sequence 5 times if the person does not respond. In lieu of pagers, emergency response personnel will be required to have their cell phones on and charged at all times when they are on call. The system of notification is designed to seek a second responder from each position pool to ensure the facility can be activated within required times. Emergency Planning Functions [6] from 10CFR50.54(q) Screening Form:

Systems are established for prompt communication to emergency response personnel.

The change to Everbridge from just activating pagers provides the system by which the prompt communication will occur. The system will allow to be activated via application, website or by telephone. NUREG-0654 Section II.F Program Elements associated with the above Emergency Planning Standard [6]:

The communication plans for emergencies shall include organizational titles and alternates for both ends of the communication links. Each organization shall establish reliable primary and backup means of communication for licensees, local, and State response organizations. Such systems should be selected to be compatible with one another. Each plan shall include:

e. provision for alerting or activating emergency personnel in each response organization; By using cell phone (voice and SMS) for notification and communicating with the ERO in lieu of commercial paging, the coverage and reliability of the process is improved. The process still involves the all call activation of the ERO via the activation of all of the provided means of notifying the employee (work, home, cell phone, email, etc.). Commercial paging capability has degraded over the years and is no longer as reliable as the ever expanding cell phone coverage.

Each organization shall conduct periodic testing of the entire emergency communications system Regulatory Guide 1.219, Section 4.6 also states that "a change could require prior NRC approval if it adjusts the frequency of communication testing or maintenance to a level that the site's experience with system reliability does not support." Testing of the functionality of Susquehanna contacting individual cell phones will continue to be required monthly, as stated in Section 9.1.2 Emergency Planning Functions [8] from 10CFR50.54(q) Screening Form:
Adequate equipment is maintained to support emergency response.

With the conversion to the use of Cell Phones as the primary device for ERO notifications and the elimination of Pagers as the primary notification device, the Emergency Plan revision describe "ERO Notification System to activate when emergency notifications are required." Electronic Form EP-102-2, Rev. 4, Page 4 of 7

Enclosure 2 to PLA-8077, Page 36 of 560 NUREG-0654 Section II.H Program Elements associated with the above Emergency Planning Standard [8]:

4. Each organization shall provide for timely activation and staffing of the facilities and centers described in the plan.

Per Regulatory Guide 1.219, Section 4.6, "a change to ERO callout processes or hardware could require prior NRC approval if it would delay ERO notification such that the augmentation times in the emergency plan can no longer be achieved." This change replaces the pager with a cell phone as the primary device for contacting ERO members to support augmentation times. Everbridge will now "ring" the cell phone as the first contact, which allows the ERO member to simply answer the text message or call and respond immediately. The system will record their response and allow for the organization to know who received the message. If the system does not get a response from the individual, the process is auto restarted up to 5 times until a response is received by design. Several years of testing using response by cell phone contact has shown the ERO member contact time (which supports ERO augmentation time) is improved with the use of cell phones. Part IV. Evaluation of the Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions: 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 current Susquehanna process for notifying the Emergency Response Organization (ERO) includes a defense-in-depth where the Control Room uses a phone dialer to alert all ERO pagers to a message. Also, as part of the ERO activation process, Security activates Communicator!NXT to perform an "all call" to all of the devices provided by the ERO members (work, home, company cell phone, personal cell phone, pager, email, and SMS/text message to any capable device). Over the years, paging reliability and coverage has declined and mobile phone capability and reliability has increased significantly. During the monthly call in drills, paging coverage concerns were raised whereas cell phone messaging have routinely worked. Use of Pagers is becoming obsolete due to newer technologies associated with mobile phones i.e. Smart Phones. Pager companies are not adding coverage to their existing capabilities due to a lack of demand. Cell phone coverage and reliability is growing / improving, and the use of cell phone text messaging has taken the place of the classic pager notifications. Text messaging is often available when cell phone voice coverage is marginal or unavailable. With the increased use of cell phones in lieu of home phones, people are placing a greater emphasis on keeping their cell phone charged and available at all times. Replacing pager notification with the messaging capability of cell phones has shown to be more reliable based on the routine testing and drills conducted at Susquehanna. Redundancy is maintained through contacting the ERO member via multiple channels using Everbridge and the use of an all call augmentation process that notifies all ERO members on all teams. Evaluation of upgrade from Communicator!NXT to Everbridge. Both Communicator!NXT and Everbridge are software products that are owned by Talen Energy. The change at Susquehanna is prompted primarily by the move toward one company wide software for notifications. Everbridge is an updated product with more capabilities to activate the system, maintain the contact information and has platforms to expand notification capabilities. The system has been used by Talen Corporate and Susquehanna for years to provide notifications in both drills and real events across the enterprise. The current process does not allow for any feedback to the organization that the on-call personnel received the message and are responding. This is the reason that Communicator!NXT was deployed to get a second responder, in case the on-call person did not get the page or was incapacitated. Susquehanna is ready for large events that may affect both units at the site with having essentially 2 personnel from each position responding. The current change discussed will ensure there is at least 2 personnel responding. Electronic Form EP-102-2, Rev. 4, Page 5 of 7

Enclosure 2 to PLA-8077, Page 37 of 560 Item Process Current Future Pagers- Everbridge Communicator!NXT 1 Notify on-call personnel. SM activates pagers by SM will open Everbridge App on phone or (All pagers activate, on-call picking up designated device, select notification and hit send. knows to just respond, phone and selecting a This will only go to on-call personnel and other personnel to wait for hot button that continue to contact that person via Text Communicator!NXT activates an auto-dialer Message, Email and Phone call up to 5 message.) to activate pagers. times. 2 Notify ERO - Second Once pagers activate, Once initial notification is received, responder. Security will open Security will open ManageEverbridge App Communicator!NXT on phone or device, select notification and website, select the hit send. This will only go to ERO scenario and activate. personnel who are not on call and only look for one responder via Text Message, Email and Phone call up to 5 times. 3 Back up activation -(On-call If pagers do not If the App is not working, there is a web personnel) activate, the message address to log into and each notification can be sent by calling can be activated via telephone. an all call number for the pagers or via Microsoft Outlook that activates all pagers. 4 Back up activation - If Communicator!NXT If the App is not working, there is a web (Second responder) website is down, there address to log into and each notification is a backup website can be activated via telephone. and can be activated via phone. 5 On-call Response Gets page with 22222 Receive polling text message, respond to or 99999 and poll and respond to appropriate facility. responds to appropriate facility. (No recorded If text not seen in one minute, system response) calls. Process repeated every 10 minutes five times. 6 Secondary responder Respond to Receive polling text message, respond to Communicator!NXT by poll and respond to appropriate facility. calling in then respond to appropriate facility. If text not seen in one minute, system calls. Process repeated every 10 minutes five times. Reg. Guide 1.219 Revision 1 section 4.2, 4.5, 4.6 and 4.8 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. Part V. Evaluation Conclusion Answer the following questions about the proposed change.

1. Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? YES NO Electronic Form EP-102-2, Rev. 4, Page 6 of 7

Enclosure 2 to PLA-8077, Page 38 of 560

2. Does the proposed change maintain the effectiveness of the Emergency Plan (i.e., no reduction in effectiveness)? ~ YES NO

3. Does the proposed change constitute an emergency action level scheme change? YES ~ 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: Patrick M. Gilligan ~~fl/,A -..... 08/23/2023 Preparer Name (Print) (JFG EP109) Preparer Signature V Date Jessica Shoup CJ~H'i~ Aug 23, 2023 Reviewer Name (Print) (JFG EP109) Reviewer Signature Date Electronic Form EP-102-2, Rev. 4, Page 7 of 7

Enclosure 2 to PLA-8077, Page 39 of 560 S2023-08-01-01 Discontinue use of Pagers and Everbridge Transition Final Audit Report 2023-08-23 Created: 2023-08-23 By: Patrick Gilligan (Patrick.Gilligan@TalenEnergy.com) Status: Signed Transaction ID: CBJCHBCAABAAJ8vjq05wFtRNunhM8Ej_3gp5wxK6U_fY "S2023-08-01-01 Discontinue use of Pagers and Everbridge Tra nsition" History

~ Document created by Patrick Gilligan (Patrick.Gilligan@TalenEnergy.com) 2023-08 3:11 :27 PM GMT- IP address: 12.40.226.114
~ Document emailed to Jessica Shoup (jessica.shoup@talenenergy.com) for signature 2023-08 3:29:00 PM GMT
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Signature Date: 2023-08 3:43:52 PM GMT - Time Source: server- IP address: 130.19.32.252 0 Agreement completed. 2023-08 3:43:52 PM GMT II Adobe Acrobat Sign

Enclosure 2 to PLA-8077, Page 40 of 560 Attachment A, 10CFR50.54q Screening Form Screening Number: S2023-02-02-01 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 a description of the revised text (attaching a mark-up of the existing text with proposed change can be used as an alternative): Transition from MIDAS to URI Part II. Is Activity a Change per Section 3.1.3? ~ YES NO Does the activity constitute a change per definition 3.1.3 - An action that Continue to next 10 CFR 50.54(q) part Evaluation is NOT results in modification or addition to, or removal from the SSES Emergency required. Enter Plan, OR the resources, capabilities and methods identified in the plan? justification and complete Part VI. Part III. Is Activity Previously Reviewed? YES ~ NO Is this activity fully bounded by an NRC approved 10 CFR 50.90 submittal 10 CFR 50.54(q) Continue to next part Evaluation is NOT or Alert and Notification System Design Report (44 CFR 350.14)? required. Enter justification and If YES, identify bounding source document number/approval reference and complete Part VI. ensure the basis for concluding the source document fully bounds the proposed change is documented below: Justification: Bounding document attached (optional) Part IV. Editorial Change YES ~ 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 is assigned. [1] ~

2. The response organization has the staff to respond and to augment staff on a continuing basis (24/7 staffing) in accordance with the Emergency Plan. [1]

3. The process ensures that on shift emergency response responsibilities are staffed and assigned. [2]

4. The process for timely augmentation of on-shift staff is established and maintained. [2]

5. Arrangements for requesting and using off site assistance have been made. [3]

6. State and local staff can be accommodated at the EOF in accordance with the Emergency Plan. [3]

7. A standard scheme of emergency classification and action levels is in use. [4] (RSPS) ~

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 notifications. [5] (RSPS) Electronic Form EP-102-1 Rev. 6, Page 1 of 2

Enclosure 2 to PLA-8077, Page 41 of 560 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 appropriate box.

9. Administrative and physical means have been established for alerting and providing prompt 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 licensees FEMA-approved ANS design report and supporting FEMA approval letter. [5] (RSPS)

11. Systems are established for prompt communication among principal emergency response organizations. [6]

12. Systems are established for prompt communication to emergency response personnel. [6]

13. Emergency preparedness information is made available to the public on a periodic basis within the plume exposure pathway Emergency Planning Zone (EPZ). [7]

14. Coordinated dissemination of public information during emergencies is established. [7]

15. Adequate facilities are maintained to support emergency response. [8]

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) ~

18. A range of public PARs is available for implementation during emergencies. [10] (RSPS) ~

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 authorities. [10] (RSPS)

20. KI is available for implementation as a protective action recommendation in those jurisdictions that chose to provide KI to the public [10]

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] ~

23. Arrangements are made for medical services for contaminated, injured individuals. [12]

24. Plans for recovery and reentry are developed. [13] ~

25. A drill and exercise program (including radiological, medical, health physics and other program areas) is established. [14]

26. Drills, exercises, & training evolutions that provide performance opportunities to develop, maintain, &

demonstrate key skills are assessed via a formal critique process in order to identify weaknesses. [14]

27. Identified weaknesses are corrected. [14]

28. Training is provided to emergency responders. [15] ~

29. Responsibility for Emergency Plan development and review is established. [16]

30. Planners responsible for Emergency Plan development and maintenance are properly trained. [16]

r~ APPLICABILITY CONCLUSION pe,rtorll,a, If no Part V criteria are checked, a 10 CFR 50.54(q) Evaluation is NOT required; complete Part VI. nd perform a 10 Ct-K 50.

~ If any Part V criteria are checked, complete Part VI and                            CFR 50.54(q)   Evaluation.

Part VI. Signatures: Adrian Miron 2/2/23 Preparer Name (Print) (JFG EP109) Preparer Signature Date q""""' H ~ Aug 15, 2023 Jessica Shoup Reviewer Name (Print) (JFG EP109) Reviewer Signature Date Electronic Form EP-102-1 Rev. 6, Page 2 of 2

Enclosure 2 to PLA-8077, Page 42 of 560 S2023-02-02-01 transition to URI Final Audit Report 2023-08-15 Created: 2023-08-14 By: Adrian Miron (Adrian.Miron@TalenEnergy.com) Status: Signed Transaction ID: CBJCHBCAABAAFArGLuWUSUvudgEmv9QKZXevyfPsPDn0 "S2023-02-02-01 transition to URI" History

~ Document created by Adrian Miron (Adrian.Miron@TalenEnergy.com) 2023-08 7:37:42 PM GMT- IP address: 50.122.98.202 g    Document emailed to Jessica Shoup Uessica.shoup@talenenergy.com) for signature 2023-08 7:38:55 PM GMT
~ Email viewed by Jessica Shoup Uessica.shoup@talenenergy.com) 2023-08 8:02:01 PM GMT- IP address: 50.122.98.202
£%   Document e-signed by Jessica Shoup Uessica.shoup@talenenergy.com)

Signature Date: 2023-08 8:28:05 PM GMT - Time Source: server- IP address: 50.122.98.202 C, Agreement completed. 2023-08 8:28:05 PM GMT II Adobe Acrobat Sign

Enclosure 2 to PLA-8077, Page 43 of 560 Attachment B, 10CFR50.54q Evaluation Checklist Evaluation Number: E2023-02-02-01 I Screen Number: S2023-02-02-01 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): The transition from MIDAS to URI involved the following changes: A. Emergency Plan and EP implementing procedures that need to be issued at the same time with the implementation (See Attachment 1 for the markups).

1. SSES Emergency Plan Rev 66 (E-Plan)

2. EP-PS-001, Emergency Planning Forms And Supplementary Instructions, in particular the following forms: EP-PS-001-3, EP-PS-001-4, EP-PS-001-10, EP-PS-001-17, EP-PS-001-19 (deleted), EP-PS-001-22, EP-PS-001-23, EP-PS-001-28, EP-PS-001-34, EP-PS-001-35, EP-PS-001-41, EP-PS-001-42, EP-PS-001-45 (deleted and consolidated information in EP-PS-001-3 and EP-PS-001-17), EP-PS-001-47 (deleted and consolidated information in EP-PS-001-22), EP-PS-001-55, EP-PS-001-56, EP-PS-001-57, EP-PS-001-61 (deleted and consolidated information in EP-PS-001-22), EP-PS-001-62, EP-PS-001-63 (deleted and consolidated information in EP-PS-001-22), EP-PS-001-64, EP-PS-001-65 (new, NOT shown in Attachment 1).

3. EP-PS-102, TSC Technical Support Coordinator

4. EP-PS-104, Radiological Protection Coordinator

5. EP-PS-105, TSC Dose Calculator

6. EP-PS-108, RP I Tech (OSCAR)

7. EP-PS-130, RP II Dose Calculator

8. EP-PS-134, TSC RP Radio Communicator

9. EP-PS-210, NEP Duty Planner

10. EP-PS-222, Field Monitoring Team

11. EP-PS-244, EOF Dose Assessment Staffer

12. EP-PS-245, EOF Dose Assessment Supervisor

13. EP-PS-247, EOF Field Team Director

14. EP-PS-248, EOF Environmental Sampling Director

15. EP-PS-307, Engineering Support Supervisor

16. EP-PS-325, EOF Systems Lead Engineer

17. EP-RM-004, EAL Classification Bases

18. EP-RM-005, MIDAS-NU User Guide (deleted, NOT shown in Attachment 1)

19. EP-RM-009, URI User Guide (new, replaces EP-RM-005, MIDAS-NU User Guide; NOT shown in Attachment 1)

B. Station and E-Plan administrative procedures that are controlled by DPAs (listed in parentheses; changes NOT shown in Attachment 1) and that can be issued soon after, or along with the implementation, as follows:

1. EO-000-105, Radioactivity Release, (DPA-53-DI-2022-01144)

2. EP-11, BDB Program Procedure (DPA-28-DI-2022-01144)

3. EP-101, Generation of EP Technical Basis (DPA-29-DI-2022-01144)

4. EP-104, SSES Drill and Exercise Program (DPA-42-DI-2022-01144)

5. EP-112, Emergency Plan Reference Manual Program (DPA-34-DI-2022-01144)

6. EP-115, Equipment Important to Emergency Response - EITER (DPA-27-DI-2022-01144)

7. EP-00-006, Inventory, Inspection, and Operational Testing of Emergency Equipment and Supplies (DPA-27-DI-2022-01144)

8. CH-ON-002, VERMS Alarm Response (DPA-35-DI-2022-01144)

9. LS-1012, Reportable Action Levels for Loss of Emergency Response Capabilities (DPA-49-DI-2022-01144)

10. NFP-QA-005, Reload Design and Analysis Process (DPA-22-DI-2022-01144)

11. NSEP-QA-504, Process Computer System Security Controls Assessment (DPA-23-DI-2022-01144)

12. NSEP-00-500, Ownership and Responsibilities for Susquehanna Digital Systems (DPA-23-DI-2022-01144)

13. D190737, Unit 2 Block Diagram Plant Computer System, (DPA-23-DI-2022-01144)

Electronic Form EP-102-2, Rev. 4, Page 1 of 4

Enclosure 2 to PLA-8077, Page 44 of 560 C. Training Materials (approved by the Training Department supervision and EP Manager; training material tracked and attached under DPA-14-DI-2022-01144, DPA-17-DI-2022-01144, DPA-19-DI-2022-01144, DPA-44-DI-2022-01144 and DPA-45-DI-2022-01144)

1. EP009, On-shift URI Training

2. EP010, Dose Assessment and Protective Actions (currently under review, not needed for URI implementation)

3. EP064, TSC and EOF Dose Calculator Training

4. EP064R, TSC and EOF Dose Calculator Retraining

5. EP086. Emergency Preparedness Team Training

6. EP090, Dose Assessment and Protective Actions Overview (currently under review, not needed for URI implementation)

7. EP110, EP Annual Training for Control Room Operators D. Supporting technical documentation

1. NEP Technical Basis 02-004, Total Noble Gas to Iodine-131 and Total Noble Gas to Particulate Ratios For Use in MIDAS Evaluations Supporting Emergency Plan (process as historical)

2. NEP Technical Basis 02-005, Noble Gas Release Rate Limits For EALs (discussed and included in Attachment 4 of this evaluation)

3. NEP Technical Basis 04-001, Start of Radiological Release (process as historical)

4. NEP Technical Basis 15-001, SSES Implementation of Protection Action Recommendations (PAR)

Scheme Based on NUREG-0654, Supplement 3, Rev 1 and NEI 12-10, Rev 1 (pertinent pages discussed and included in Attachment 7 of this evaluation)

5. NEP Technical Basis 16-001, Frisker Response in Support of EAL Implementation and Determination of Release in Progress (discussed and included in Attachment 8 of this evaluation)

6. NEP Technical Basis 21-001, MIDAS Input Specification Document (process as historical)

7. NEP Technical Basis 23-001, Unified RASCAL Interface Technical Design Description Version 3.7 (new; approved document, NOT shown in this evaluation)

8. NEP Technical Basis 23-002, Unified RASCAL Interface Requirements Specification - Susquehanna Site Annex Version 3.7 (new; approved document, NOT shown in this evaluation)

9. EC-RADN-1166, Verification & Validation of MIDAS-NU Version 1.5.17 (process as historical)

10. EC-RADN-1150, Justification of 35 Isotope Accident Source Team for the MIDAS Computer Code (process as historical)

11. EC-RADN-1136, MIDAS Dose Correction Factors for Menu D Default LOCA Calc With 15 scfh Secondary Containment Bypass Leakage (process as historical)

12. EC-RADN-1164, Default Accident Activity Releases for the MIDAS Computer Code (process as historical)

E. Code and Other Supporting Equipment

1. Customized SSES URI Code (see DPA-05-DI-2022-01144)

2. Engineering changes and Cyber Security controls to install SSES URI code on SDS computers at appropriate locations in the TSC, Alternate TSC and EOF and automate the inputs from the plant computer (R*Time) (see DPA-03-DI-2022-01144, DPA-04-DI-2022-01144, DPA-18-DI-2022-01144, DPA-20-DI-2022-01144)

3. MSL SQA package for URI (see DPA-30-DI-2022-01144)

4. SQA package for Excel spreadsheet in support of EP-PS-001-28 form (see DPA-26-DI-2022-01144)

5. Update Table R - Abnormal Rad Screen and Emergency Plan Met/Vent Data R*Time screens DPA-25-DI-2022-01144

6. Update R*Time and SPDS screens for both U1 and U2 for any points and screens that reference Alert, Site Area Emergency and General Emergency levels (see DPA-24-DI-2022-01144)

The main differences between MIDAS and URI code are discussed in Attachment 2. Based on these changes, the following Emergency Planning Element / Functions were checked on the related screening form:

Responsibility for emergency response is assigned. [Element in Planning Standard (PS) 10 CFR 50.47(b)(1)] - see Attachment 3 for discussion
Electronic Form A standard EP-102-2, scheme Rev. 4, classification of emergency Page 2 of 4 and action levels is in use. [Element in PS 10 CFR 50.47(b)(4) - RSPS] - see Attachment 4 for discussion

Enclosure 2 to PLA-8077, Page 45 of 560

Administrative and physical means have been established for alerting and providing prompt instructions to the public within the plume exposure pathway. [Element in PS 10 CFR 50.47(b)(5) - RSPS] - see Attachment 5 for discussion
Adequate equipment is maintained to support emergency response. [Element in PS 10 CFR 50.47(b)(8)] -

see Attachment 6 for discussion

Methods, systems, and equipment for assessment of radioactive releases are in use. [Element in PS 10 CFR 50.47(b)(9) - RSPS] - see Attachment 7 for discussion
A range of public PARs is available for implementation during emergencies. [Element in PS 10 CFR 50.47(b)(10) - RSPS] - see Attachment 8 for discussion
The resources for controlling radiological exposures for emergency workers are established. [Element in PS 10 CFR 50.47(b)(11)] - see Attachment 9 for discussion
Plans for recovery and reentry are developed. [Element in PS 10 CFR 50.47(b)(13)] - see Attachment 10 for discussion
Training is provided to emergency responders. [Element in PS 10 CFR 50.47(b)(15)] - see Attachment 11 for discussion Part II. Evaluation of the Proposed Change for Compliance with the requirements of 10 CFR 50.47(b) and 10 CFR 50 Appendix E:

Based on analysis performed in Attachments 3 through 11, SSES remains in compliance with the requirements of 10 CFR 50.47(b) and 10 CFR 50 Appendix E by implementing this change. 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: Based on analysis performed in Attachments 3 through 11, by implementing this change, SSES remains in compliance with the requirements of Emergency Planning Functions, Elements, and Commitments affected by the Proposed Change and the Licensing Basis for those Functions, Elements, and Commitments. Part IV. Evaluation of the Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions: Based on analysis performed in Attachments 2 through 11, by implementing this change, SSES increased the effectiveness of E-Plan due to automation or semiautomated input linked to R*Time computers, networking features and improved graphic design of URI which contains both Inputs and Outputs on one screen. In addition, as discussed in Attachment 2, SSES URI is a better code as compared with the current version and setup of MIDAS at SSES because:

Provides for more precise dose assessment calculations due to:

    -    calculation of PRFs and NG/I-131 and NG/Particulates ratios based on the selected pathway
    - inclusion in the source term of Fission Product isotopes with relatively large half-lives such as Xe-131m, Sr-91, Y-91, Sb-127, Sb-129, and La-140
    - a much-improved atmospheric dispersion model, including pathway dependent release heights and adjusting release based on snow.

Addition of an ISFSI source term, addition of Spent Fuel source term in the monitored path and addition of Blowout panel scenarios in Rapid mode
Much more versatile and flexible model that includes multiple magnitude scaling methods (for potential unmonitored release) in the pathway itself and can characterize all SSES-specific containment vent pathways.
Allows user to see both inputs and dose assessment results in one screen, as well time savings in running the code as it needs to modify only the changing input parameters, without entering those that are not changed in individual runs.
Much more user friendly, and less error prone user input and output due to network connectivity with R*Time computers and data saving capabilities.
Much easier to run from the procedural standpoint.

Electronic Form EP-102-2, Rev. 4, Page 3 of 4

Enclosure 2 to PLA-8077, Page 46 of560 Finally, as discussed in Attachment 4 of this evaluation, Regulatory Guide 1.219 Revision 1 section 4.4.f states: f The following examples would generally not require prior NRG approval: (1) A change to an EAL numeric threshold to reflect an approved change in a technical specification, provided that the basis of the approved EAL is unchanged (e.g., an EAL basis refers to a particular technical specification but not a limiting condition for operation value), and (2) A change to an EAL numeric threshold to reflect a change in a plant design parameter, instrument response characteristics, or design calculation, provided that the meaning or intent of the basis of the approved EAL is unchanged. Both these examples are in line with the change described in Part I as a parameter value is justifiably changed with another value based on a calculation corresponding to the new SSES dose assessment code and its associated methodology (NEP Technical Bases 02-005). Therefore, although it is an EAL change, this does not constitute an EAL scheme change in accordance with Reg. Guide 1.219 Revision 1 section 4.4.f(1) and (2) and therefore the checkbox in the third line in Part Vin E2023-02-02-01 can be marked as "No". Therefore, the proposed change as shown in Part I and Attachment 1 as well as discussed in Attachment 2 through 11 of this evaluation is not a reduction in effectiveness of the Emergency Plan and therefore does not require prior NRC approval. Part V. Evaluation Conclusion Answer the following questions about the proposed change.

1. Does the *ro osed chan e com I with 10 CFR 50.47 b and 10 CFR 50 A endix E? [ZI YES D NO

2. Does the proposed change maintain the effectiveness of the Emergency Plan (i.e., no [ZI YES D NO reduction in effectiveness ?

3. Does the ro osed chan e constitute an emer enc action level scheme chan e? D YES [ZI NO If questions 1 or 2. are answeredNQ,o~{luestion 3_ans~eredYES, obtain~wior t',JRC, app;oyal untjergovJsio~~ of _

tQ_~fJ3.§Q,:~0. If giJ~stions ;1 :and 2 ~~e Anslflereci .YES; and qi.JestiClr:i ;3,aftsw~i"ed NO;irnpJem~ntappliqabl~chang~

roce5$ es ;;

Part VI. Signatures: Adrian Miron 5/22/2023 Preparer Name (Print) (JFG EP109) Date Ao EDTI Oct 26, 2023 Jessica Shau Jessica Shoup (Oct2G, zon Reviewer Name (Print) (JFG EP109) Reviewer Signature Date Electronic Form EP-102-2, Rev. 4, Page 4 of 4

Enclosure 2 to PLA-8077, Page 47 of 560 E2023-02-02-01 transition to URI Final Audit Report 2023-10-26 Created: 2023-10-26 By: Adrian Miron (Adrian.Miron@TalenEnergy.com) Status: Signed Transaction ID: CBJCHBCAABAAuxbMAos2yXWpmPXaJIAwH3O3IkV7oHrA "E2023-02-02-01 transition to URI" History 'El Document created by Adrian Miron (Adrian.Miron@TalenEnergy.com) 2023-10 6:24:42 PM GMT- IP address: 50.122.98.202 ~ Document emailed to Jessica Shoup Uessica.shoup@talenenergy.com) for signature 2023-10 6:26:09 PM GMT 'El Email viewed by Jessica Shoup Uessica.shoup@talenenergy.com) 2023-10 6:26:55 PM GMT- IP address: 50.122.98.202 6-o Document e-signed by Jessica Shoup Uessica.shoup@talenenergy.com) Signature Date: 2023-10 6:30:23 PM GMT-Time Source: server- IP address: 50.122.98.202 0 Agreement completed. 2023-10 6:30:23 PM GMT Adobe Acrobat Sign

Enclosure 2 to PLA-8077, Page 48 of 560

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Enclosure 2 to PLA-8077, Page 56 of 560 Emergency Plan, Rev. 66, Page 1 of 170 SUSQUEHANNA NUCLEAR, LLC SUSQUEHANNA STEAM ELECTRIC STATION EMERGENCY PLAN REVISION 6667 DATE: XX/XX/XXXX10/06/2022 PORC MEETING: TBD22-10-06

Enclosure 2 to PLA-8077, Page 57 of 560 Emergency Plan, Rev. 66, Page 2 of 170 SUSQUEHANNA NUCLEAR, LLC SUSQUEHANNA STEAM ELECTRIC STATION TEAM SUSQU.EHANNA.

           . . ,. .         Generating Excellence THIS DOCUMENT HAS BEEN UPDATED TO INCLUDE REVISIONS THROUGH "66

Enclosure 2 to PLA-8077, Page 58 of 560 Emergency Plan, Rev. 66, Page 3 of 170 AFFECTED PAGES OR SECTIONS NOTE: 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. This revision takes credit for the 2023 Annual Emergency Plan Review per AR-2023-00273.

(S2023-05-24-01)

2. Removed Security/ from title of Manager-Security/Emergency Preparedness throughout the document per DPA-07-DI-2023-02751. (S2023-05-24-01)

3. Changed response pagers to Notification System in section 6.0, Phase I h) step per DPA-36-DI-2021-11192. (S / E2023-08-01-01)

4. Changed section 7.1.1.3 and Appendices B and C and deleted MIDAS from Figure 8.2 in support of URI implementation at SSES per DPA-13-DI-2022-01144. ( S / E2023-02-02-01)

5. Replaced Figure 8.1 with the updated C-2532 Sheet 1 with the new site boundary per ACT-01-CR-2023-02344. (S / E2022-09-08-01)

6. Deleted reference to Hunlock Creek Ambulance Association from Appendix A per DPA-04-DI-2023-01542. (S /E2023-05-04-01)

7. Deleted FSAR Figure 13.1-3 from Section A in Appendix J per DI-2023-02233. ( S2023-05 01)

8. Added EP-00-005, Termination and Restoration procedure to Appendix J Sections M.1 and M.2 per DI-2023-02233. (S2023-05-24-01)

9. Corrected typo in Appendix J section M.4 per DI-2023-02233. ( S2023-05-24-01)

1. Revision 66 takes credit for the 2022 Annual Emergency Plan Review . (S2022-09-06-01)

2. Added definition of primary system per NEI 99-01 guidance per AR-2022-03384. (Editorial)

3. Modify the Emergency Plan to use common terminology for press briefings and news bulletins per AR-2021-10928. (E2022-09-06-01)

4. Added Revision 1 to NUREG-0654 in reference section per AR-2021-01890. (Editorial)

5. Removed population information in Figure 4.1 and 4.2 per AR-2022-13603. (Editorial)

6. Removed reference to Table F in section 5.1.1 of the Emergency Plan as there is no NOUE in respective table per AR-2021-05447 (E2014-10-29-01 and 2016 SER Docket Nos. 50-387 and 50-388)

7. Removed the word Horizontal in 2 places in section 5.2.11 per DPA-01-DI-2019-14058.

(Eval E2019-04-03-01Rev 1)

8. Revise 6.2.2 (C) of Emergency Plan to add "s" to communicator. AR-2022-13655 (Editorial)

9. Removed , and VERMS Maintenance Interface Terminal from section 8.1.3.1 per DPA-02-DI-2020-15633 and E2013-09-03-01 Rev 2.

10. Updated Figure 8.3 to current map of EOF/JIC/ Alt TSC per AR-2022-13660. (Editorial)

11. Revised section 9.1.2 to remove reference to 10 CFR 50.54 (hh)(1) and 10 CFR 50.54 (hh)(2) and replaced with requirements for 10 CFR 50.155 demonstration per DPA-01-DI-2022-00770.

(Conforming Change)

12. Formatted table 9.1 section 6 training with the departments listed per DPA-01-DI-2021-15414.

(Editorial)

Enclosure 2 to PLA-8077, Page 59 of 560 Emergency Plan, Rev. 66, Page 20 of 170 2.46 LLRWHF - Low Level Radwaste Holding Facility 2.47 LOCA - Loss of Coolant Accident 2.48 MOCA - Monitored Owner Controlled Area 1 - 2.49 2.50 MIDAS - MSIV - Meteorological Information and Dose Assessment System Main Steam Isolation Valve 2.51 MSL - Main Steam Line 2.52 NEP - Nuclear Emergency Planning 2.53 NRC - Nuclear Regulatory Commission 2.54 NRP - National Response Plan 2.55 NSRB Nuclear Safety Review Board 2.56 NSSS - Nuclear Steam Supply System 2.57 ODCM - Offsite Dose Calculation Manual 2.58 ORO Offsite Response Organization 2.59 OSC - Operations Support Center 2.60 PAGS - Protective Action Guides from EPA 2.61 PEMA - Pennsylvania Emergency Management Agency 2.62 PORC - Plant Operations Review Committee 2.63 PPL - PPL Corporation 2.64 PSP - Pennsylvania State Police 2.65 RCA - Radiologically Controlled Area 2.66 RCIC - Reactor Core Isolation Cooling 2.67 RDAS - Remote Data Analysis System 2.68 RHR - Residual Heat Removal 2.69 RPS - Reactor Protection System 2.70 RX - Reactor 2.71 SAS - Secondary Alarm Station 2.72 SDE - Shallow Dose Equivalent 2.73 SDS - Satellite Display System 2.74 SEIC - Susquehanna Energy Information Center 2.75 SGTS - Standby Gas Treatment System 2.76 SLC - Standby Liquid Control 2.77 SOCA - Security Owner Controlled Area 2.78 SPDS - Safety Parameter Display System 2.79 SSE - Safe Shutdown Earthquake 2.80 SSES Susquehanna Steam Electric Station 2.81 SSES URI Unified RASCAL Interface customized for SSES 2.81 Susquehanna Susquehanna Nuclear, LLC (subsidiary company of Talen Energy Corporation) 2.82 TEDE - Total Effective Dose Equivalent 2.83 TR - Temperature Recorder 2.84 TSC - Technical Support Center 2.85 UMC - Unit Monitoring Console (PCS) 2.86 UPS - Uninterruptible Power Supply 2.87 USDA - United States Department of Agriculture 2.88 VERMS Vent Effluent Radiation Monitoring System Page 2 of 2

Enclosure 2 to PLA-8077, Page 60 of 560 Emergency Plan, Rev. 66, Page 44 of 170 6.0 ORGANIZATIONAL CONTROL OF EMERGENCIES 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. 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 pagersNotification System 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. Page 1 of 19

Enclosure 2 to PLA-8077, Page 61 of 560 Emergency Plan, Rev. 66, Page 74 of 170 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 offsite doses to the public based on evaluation of isotope specific release rates and 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 3 of 10

Enclosure 2 to PLA-8077, Page 62 of 560 Emergency Plan, Rev. 66, Page 75 of 170 The dose calculation model used is a fast running, time-dependent, variable trajectory plume segment "B" model with the following capabilitieshas the following characteristics typical of a class B model: NOTE: A class "B" model is a numerical model that represents the actual spatial and temporal variations of plume distribution. x Computes The atmospheric dispersion at the site calculation uses real-time site specific meteorological data to compute plume dispersion, deposition, and depletion using a combination of straight line and trajectory puff (LaGrangean) Gaussian models.based on atmospheric stability as a function of site specific terrain conditions with 15-minute upgrades of source term and meteorological conditions. x Estimates release rates by isotope based on atmospheric stabilityreal-time plant measurements and alternate backup methods. Computes plume trajectory 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. x Incorporated in the calculations ispuff model. x Includes wet and dry deposition which enables dose estimates from three pathways - plume, ground shine, and ingestion. x Calculates Total Effective Dose Equivalent (TEDE) and child thyroid Committed Dose Equivalent (CDE) based on the evaluated release rates and the dispersion model. x Provides a summary of offsite consequences with spatial distribution of consequences throughout the planning zone. x Provides estimates of deposition and relative concentration of radioactivity within the plume exposure and ingestion EPZs for the duration of the release. x Incorporated in the calculations is wet and dry deposition which enables dose estimates from three pathways - plume, ground shine, and ingestion. Page 4 of 10

Enclosure 2 to PLA-8077, Page 63 of 560 Emergency Plan, Rev. 66, Page 76 of 170 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 CDE. However adult physiology is used in calculating thyroid CDE for purposes of evaluating the need 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 optionsresults are availableprovided: x 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. x EDE and CDE dosePlume exposure rates for field team management. x Fifty year child thyroid committed dose (CDE), from inhalation of radioactive materials. x Population dose (person rem) out to 50 miles. x Summary print of release rates, projected doses, and calculation basis for each of four projection times. x Plume plotting of the TEDE and CDE thyroid dose distribution. x 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, Alternate TSC and EOF. The dose assessment program also has the capacity to integrate the time dependent releases and local meteorology over the course of a release event and provide a summary of offsite consequence estimates for the entire event. This integrated event assessment includes TEDE, child thyroid CDE and isotope specific deposition spatially distributed throughout the planning zone radius. 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. Page 5 of 10

Enclosure 2 to PLA-8077, Page 64 of 560 Emergency Pia n, Rev. 66, Page 107 of 170

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Enclosure 2 to PLA-8077, Page 66 of 560 Emergency Plan, Rev. 66, Page 109 of 170 MAP OF THE SUSQUEHANNA SES EMERGENCY FACILITIES Page 3 of 3

Enclosure 2 to PLA-8077, Page 67 of 560 Emergency Plan, Rev. 66, Page 110 of 170 NUCLEAR REGULATORY COMMISSION SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 EMERGENCY PLAN Technical Support Center FLOOR PLAN FIGURE 8.2 Typical work station including desk, chair, Field Team telephone as necessary for Radio Indicates telephone-may be a standard telephone. May also represent FTS emergency response for phone. the listed positions. Verms Interface Administrative Coordinator Security Coordinator TSC Dose Calculator HPN Communicator Radiation Protection Coordinator Emergency Director TSC Emergency Plan Communicator TSC NRC Communicator Operations Coordinator Technical Support Coordinator Damage Control Team Coordinator Status Boards and Area Maps-Typical TERMINAL Cabinet Engineering Support Area NSSS Engineer Core thermal Hydraulic Engineer Electrical/I& C Engineer Symbol for Computer Computer Station-WS PICSY Radio SPDS Power Supply (Symbol is not necessarily Engineering indicative of the specific Support Area number of computer installations. The symbol Library designates a typical installation) Elevator Page 1 of 2

Enclosure 2 to PLA-8077, Page 68 of 560 Emergency Plan, Rev. 66, Page 111 of 170 NUCLEAR REGULATORY COMMISSION SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 EMERGENCY PLAN Technical Support Center FLOOR PLAN FIGURE 8.2 Typical work station including desk, chair, Field Team telephone as necessary for Radio Indicates telephone-may be a standard telephone. May also represent FTS emergency response for phone. the listed positions. Verms Interface Administrative Coordinator Security Coordinator TSC Dose Calculator HPN Communicator Radiation Protection Coordinator Emergency Director TSC Emergency Plan Communicator TSC NRC Communicator Operations Coordinator Technical Support Coordinator Damage Control Team Coordinator Status Boards and Area Maps-Typical TERMINAL Cabinet Engineering Support Area NSSS Engineer rnm Core thermal Hydraulic Engineer Computer Electrical/I& C Engineer Symbol for Computer WS Station-PICSY Radio SPDS Power Supply (Symbol is not necessarily Engineering indicative of the specific Support Area number of computer installations. The symbol Library designates a typical installation) Elevator Page 2 of 2

Enclosure 2 to PLA-8077, Page 69 of 560 Emergency Plan, Rev. 66, Page 118 of 170 9.1.3 Overall Coordination of Nuclear Emergency Preparedness 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: x Revising of the SSES Emergency Plan x Revising of EP-PSs and other Emergency Planning Administrative procedures x Conducting of integrated drills and exercises and communication drills x Defining EP training scope for ERO x Defining EOF and JIC EP Training x Coordinating EP interface between State and Federal agencies x Coordinating maintenance and testing of ANS x Coordinating interface between state, county, municipal, and Susquehanna ERO x Assuring operational readiness of Emergency Response Facilities Page 5 of 7

Enclosure 2 to PLA-8077, Page 70 of 560 Emergency Plan, Rev. 66, Page 119 of 170 9.2 REVIEW AND UPDATING 9.2.1 SSES Emergency Plan The Manager- Security/Emergency Preparedness is responsible for the review and revision of the SSES Emergency Plan, ensuring: x 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 10CFR50.54t. x Annual review of the SSES Emergency Plan. x Annual review of Letters of Agreement. x Recommendation of Emergency Plan changes to PORC. x PORC review of Emergency Plan changes and submission of changes to NSRB. x 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). x Perform an annual review of the Evacuation Time Estimate (ETE) to ensure 10CFR50 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. 9.2.2 Emergency Plan Procedures The Manager- Security/Emergency Preparedness is responsible for the review and revision(s) of the Emergency Plan Procedures, ensuring: x The periodic review is accomplished in accordance with established plant procedures. x Revisions to procedures are done in accordance with established plant procedures. x Controlled copies of procedure revisions are issued by station document control programs. x ERO personnel are briefed on revisions as required. Page 6 of 7

Enclosure 2 to PLA-8077, Page 71 of 560 Emergency Plan, Rev. 66, Page 120 of 170 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 Nuclear Emergency Preparedness staff.

9.4.4 Other Distributed Publication(s) 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 7

Enclosure 2 to PLA-8077, Page 72 of 560 Emergency Plan, Rev. 66, Page 124 of 170 LETTERS OF AGREEMENT 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 Volunteer Fire Department Columbia County Commissioners Don E. Bower, Inc Department of Environmental Protection/Bureau of Radiation Protection Federal Radiation Monitoring and Assessment Center (FRMAC) GE BWR Emergency Support Geisinger Ambulance Geisinger Bloomsburg Hospital 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 Construction Equipment Inc. 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

Enclosure 2 to PLA-8077, Page 73 of 560 Emergency Plan, Rev. 66, Page 125 of 170 These letters of agreement provide for: x Coordination of planning efforts by State and local agencies; industry support groups; fire ambulance and hospital support services; and Susquehanna. x Appropriate emergency response to assure employee and public safety during an emergency condition at SSES. x Mutual notification capabilities. x Appropriate training and exercising of emergency response capabilities. x Fire, first aid and medical support. x Environmental monitoring and assessment support. x 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: Reference Action Request 1066721 for why separate LOA is not needed for Pennsylvania State Police. Page 3 of 3

Enclosure 2 to PLA-8077, Page 74 of 560 Emergency Plan, Rev. 66, Page 128 of 170 DOSE/DISTANCE PLOTS The dose/distance plots have been removed and reference to the use of MIDAS SSES URI as the approved methodology/tool for determining magnitude of and for continually assessing the impact of the release. MIDAS SSES URI has the capability to provide assessments using event-specific fuel damage estimates. Additionally, MIDAS the code 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 4

Enclosure 2 to PLA-8077, Page 75 of 560 Emergency Plan, Rev. 66, Page 131 of 170 APPENDIX C SSES EMERGENCY PLAN POSITION SPECIFIC PROCEDURES (TYPICAL) EMERGENCY PLAN POSITION SPECIFIC PROCEDURES (Response Procedures) CR Procedures EOF Procedures Emergency Director Recovery Manager Emergency Plan Communicator EOF Support Supervisor NRC Communicator NEP Duty Planner EOF Emergency Plan Communicator TSC Procedures Environmental Sampling Team Emergency Director Radiological Monitoring 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 Sampling Director TSC Administrative Coordinator EOF Technical Advisor TSC E Plan Communicator Engineering Support Supervisor HPN Communicator Fuels Lead Engineer / Core Thermal Hydraulics Engineer RP II Dose Calculator EOF Systems Lead Engineer Damage Control Team Coordinator EOF Support Engineer TSC NRC Communicator TSC Information Coordinator JIC Procedures Fuels Lead Engineer / Core Thermal Public Information Manager Hydraulics Engineer TSC RP Radio Communicator News Manager JIC Technical Briefer Support Services Manager OSC Procedures Media & Public Officials Contact OSC Coordinator JIC Logkeeper RP Specialist JIC Writer Maintenance Foreman/Field Unit Supervisor JIC Administrative Coordinator Chemistry Coordinator OTHER EMERGENCY PLAN RESPONSE PROCEDURES 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-NUURI User Manual Personnel Accountability Page 2 of 2

Enclosure 2 to PLA-8077, Page 76 of 560 Emergency Plan, Rev. 66, Page 160 of 170 NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN A. Assignment of Responsibility 1.a. Chapter 6, Section 6.0, Table 6.2, Appendix A 1.b. Chapter 4 Table 5.2 Chapter 6 1.c. Chapter 6, Figures 6.2, 6.3, 6.4, 6.6, 6.7 FSAR Figure 13.1-3 1.d. Chapter 6, Sections 6.2.1, 6.3.1.1 1.e. 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

3. Appendix A

4. Chapter 6, Sections 6.2.7, 6.3.1.3 B. Onsite Emergency Organization

1. Chapter 6, Sections 6.0 Phase I, II, III, 6.1, Tables 6.1, Figure 6.2, Figure 6.3

2. Chapter 6, Sections 6.0, 6.1 Appendix E

3. Chapter 6, Section 6.2.1

4. Chapter 6, Section 6.2.1

5. Chapter 6, Tables 6.1

6. Chapter 6, Figure 6.7 7.a. Chapter 6, Section 6.2.6 7.b. Chapter 6, Section 6.2.5, 6.5 7.c. Chapter 6, Section 6.2.1 7.d. Chapter 6, Section 6.3.2.1

8. Chapter 6, Table 6.2 Appendix A

9. Chapter 6, Table 6.2 Appendix A Page 2 of 10

Enclosure 2 to PLA-8077, Page 77 of 560 Emergency Plan, Rev. 66, Page 167 of 170 NUREG-0654 PLANNING STANDARDS AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN APPLICABLE NUREG-0654 SECTION SSES EMERGENCY PLAN

7. Chapter 7, Section 7.3.1.4, 7.4.2 L. Medical and 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:

x Security Coordinator M. Recovery and Reentry Planning and Postaccident Operations

1. Chapter 6, Sections Phase IV, 6.5 Appendix C, Position Specific Instructions for:

x Emergency Director x Recovery Manager x Termination and Restoration

2. Chapter 6, Section 6.5, Figure 6.6 Appendix C, Position Specific Instructions for:

x Emergency Director x Recovery Manager x Termination and Restoration

3. Chapter 6, Section 6.5

4. Section 6.2.45, 6.3.1.4 Appendix C, Position Specific Instructions for:

x Radiation Protection Coordinator x Dose Assessment Supervisor N. Exercises and Drills 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 Page 9 of 10

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                             /                                                                   Forcompeting,independentprocesses,CHOOSEtheSMALLERofthetworeleasedurationtimes.

Yes II Forexample,forareleasefromRBvent,IFOSC_t+1timeisGREATERthanthe6hrsinitialreleasedurationcorrespondingtoOperations performingacontrolledcooldownfollowingasuccessfulRx.SCRAM,CHOOSE6hoursforreleaseduration. Note6:HoldupTime,accountsforthesettlingandplateoutofparticulatesandiodineswhiletheactivityisinthebuildingandrepresentshow 3(5)250D%DFN&DOFXODWLRQXVLQJWKH)LHOG7HDPPHWKRGLQWKHFRUUHVSRQGLQJ longthemajorityoftheactivityhasbeeninthebuilding SDWKZD\ 6HH7DEOHVDQG HolduptimestartswhenactivityreadingsinthebuildingbecomestableORwhenthesourceinputisstopped

                                                                                             Holduptimeisaffectedbyventilation;highvolumeturnoverwillreduceholduptime.Buildingactivityreadingsmayappearstablebut

86(WKHPRVWFRQVHUYDWLYHEHWZHHQWKH%DFN&DOFXODWLRQDQGWKHFDOFXODWLRQ SHUIRUPHGDERYHDVYDOLGFDOFXODWLRQ combinationoffreshinputandhighventilationrateswillresultinshortholduptimes.

                                                                                              HolduptimeisNOTthetimesinceshutdown.

USEarange(<2,224,>24hours)ORtheactualtimebasedonthetimesincetheactivityinputtotheareawaseliminatedORsignificantly reducedastheHolduptime.

                                                                                              IFleakisNOTisolated,SELECTHoldUptime<2hours.

Example:Rx.Shutdownwas6hoursago.CoredamageandRCSleakstarted5hoursago.RCSleakstopped(isolatedORRxdepressurized)4hours ago.Then,atthistime,theHolduptimeis4hours,i.e.,4hourssincetheleakwasisolated. Thereforeselecteither4hoursOR2-24hoursasaholduptime. Note7:SuppressionPool(SP)StatusOptions

                                                                                              Subcooled,SPwatertemperature<212F.
                                                                                              Saturated,SPwatertemperature212F.
                                                                                              Bypassed,i.e.notscrubbed(vacuumbreakerfailureORlossofSPwater).

Note8:ReleaseModeSelection

                                                                                              Leakage1%perday:Containmentintact,DBAleakage.
                                                                                              FailuretoIsolate(100%/24.0hours):Containmentloss,onelinefailuretoisolateorsmallerthan2ft2containmentopening
                                                                                              CatastrophicFailure(100%/1.0hours):Containmentloss,greaterthan2ft2containmentopeningtoatmosphere
                                                                                              CalcdContLeakrate:ENTERestimatedleakrate(incfm)fromEngineering
                                                                                              VentingusingPressureChange(psig):enterStartingcontainmentpressure(psig)andobtainthedesiredEndingcontainmentpressurefrom

Operations Note9:DrywellSprayStatus I SelectSpraysONonlyiftheDWsprayswererunningaftersignificantactivitywaspresentinthedrywell.

Note10:SourceTerm I NormalCoolant

                                                                                              SpikingFactorforautomatic/manualemergencydepressurization(defaultvalueof100timesmoreiodineandparticulatesthanintheNormal

Coolantsourceterm) ReactorCoreAccidentoptionisselectedONLYifEngineeringOROperationsstatesthereisFuel(CladORMelt)Damage.AcalculatedFuel I DamagepercentageisneededforContainmentLeakageORRCSLeakageMethodsANDitisNOTneededforMonitored,ReleasePTSampleOR I FieldTeamMethods. Note11:SteamLeakinTB/RB

                                                                                              SteamleakintotheTBincludesCondenserNOTundervacuumORfeedwaterleakby
                                                                                              SteamleakinRBincludescontainmentbypass(Ex.RCIClinebreak),(LOCAinDWwithDBAleakageorwithprimarycontainmentlossperEAL)OR

SPsteamleakage. Note12:LOCAbypassingtheDWwithdirectblowdowntotheSP(steamsafeties) Example:SRVstuckopenORAutomatic/ManualEmergencyDepressurizationWITHOUTLOCAinDW Note13:MultiplePathways MultiplePathwaysinclude,butareNOTlimitedto:

                                                                                              Concurrentreleasesfrompathwaysinbothunits(ex.U1TBventANDU2TBVent)
                                                                                              Concurrentreleasefrommorethanonepointforthesameunit(ex.U1TBventANDU1RBVent)
                                                                                              Whentherearetwoormoresignificantreleasepathways(i.e.SignificantfilteredreleasefromSGTS/RBventANDunfilteredreleasefromoneor

bothTBvents Note14:SBGTinservice SBGTisusuallyinoperationiftotalstackflowis>10,000cfm.CONFIRMwithOperations/Engineering.

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Enclosure 2 to PLA-8077, Page 106 of 560 EMERGENCY PLANNING FORMS AND SUPPLEMENTARY INSTRUCTIONS Attachment R EP-PS-001 Revision 23 Page 77 of 234 Unit o Table 1 (cont) To complete the calculation: Note: Code DOES NOT RUN if one or more required parameters (identified in the main window by . ) are missing Note: If changing any of the parameters in the Source Term Pane, the code resets and the appropriate Pathway needs to be selected again.

1. VERIFY whether the parameters in the Source Term Pane need to change AND PERFORM the change if necessary.

2. !E not previously performed, ENTER the Reactor Shutdown time, if appropriate.

3. DRAG AND DROP OR ENTER actual and valid Meteorological Data from:

Note: Based on the chosen Pathway, the met tower (10 OR 60 m) release height is automatically selected as follows: 10 m data applies to Pathways C, D, F, I, M, Q, U and Vwhile 60 m data applies to all the other Pathways in Table 1

Primary Tower (10 m OR 60 m data, as applicable for the release point)

          * !E primary met tower data is .!::,!QI valid, ENTER 10 m data from the Backup Tower
          * !E both primary and backup met tower data is NOT available, SEE EP-PS-001-41 for additional options

a. DETERMINE whether it is raining or snowing AND ENTER precipitation value in the dropdown selection using R*Time Precipitation Rate, if available, and table below:

RAININHR in IN/HR URI Value to ENTER for Precfr1itation Tvpe 0 None Uo to 0.089 Liaht Rain Between 0.089 and 0.24 Moderate Rain Greater than 0.24 Heaw Rain Uo to 0.089 LlohtSnow Greater than 0.089 Moderate/ Heaw Snow

4. ENTER OR CHECK if appropriate release duration is entered per Note 5 and, for containment venting, Table 3.

5. CLICK 10 Miles (first) OR 50 Miles, if 10 Miles run is completed A!iQ PAG doses are exceeded at 10 miles, buttons in Process Assessment To:

window to run calculation. Chart 3: Recommended Order for Data Entry in URI

                                         !fcriteria forrunningCalculatlons everylS minutes is met.8.t:W.1:1.Q.data has Step4:AssessmentMethod(SEETable2) changed within this !nterval, PRESS Force Reca/a,/ation Button .8NQ GO TO Step 7 x'

fil~* Vil:'>'!_* ~lculati.~. ~F':t c~J_,;l;;lll :t.llINlil*;".*"~~*"'i I.

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o-~t:~. -1 Step1,soe,~T*~1 ~~~~~-:. t~~:~;. *.:~~*. b.,~- Se]ectlon,if.NQI already entered.QB. changed{SEE Pathway Selection ~?,~~,,.-d~f.....s:.iD.-,,~:~c:, Flowchart) s:~~;~:;~~~:ir{. Step2:ReaetorStat~: ReactorShutdownlf appllcableANJ2.N.QI ~ alreadyentered/Last~ lmidfated{forSpent Fuel Accident selection In Step 1), If.NQI already entered Step3:Pathway(SEE~ PathwaySelett!onChart, Charts1or2ANQ.Tables 1and3,-sapplicab!e) Steps: Release Duration Step 7: RUN 10 Mile calc first (SEETableslandS,as .rum.,JElO mne PAGs are applicable, AND. Note 5) exceeded, RUN SO mile calcs FORM EP-PS-001-22, Rev. 15, Page 7 of 10 FORM EP-PS-001-22, Rev. 14, Page 8 of 1

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Enclosure 2 to PLA-8077, Page 130 of 560 EMERGENCY PLANNING FORMS AND SUPPLEMENTARY INSTRUCTIONS Attachment CC EP-PS-001 Revision 23 Page 123 of 234 Unit 0 MIDAS FIELD TO PROJECTION MEASUREMENT COMPARISON

1. Data Collection Time --===== 2. Affected Sector/Distance .>.:.(m.:. :;i"-)- - - - ' - ' - - -

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Enclosure 2 to PLA-8077, Page 133 of 560 EMERGENCY PLANNING FORMS AND SUPPLEMENTARY INSTRUCTIONS Attachment EE EP-PS-001 Revision 23 Page 130 of 234 Unit 0 ONSITE EMERGENCY MONITORING LOCATIONS 0.29 mi mi 1 To Shickshinny

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EPB distances established at Exclusion Area Boundary distance of 1800 ft (0.34 miles in each sector).

FORM EP-PS-001-43, Rev. 3, Page 3 of 3

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Enclosure 2 to PLA-8077, Page 193 of 560 TSC TECHNICAL SUPPORT COORDINATOR Attachment B EP-PS-102 Revision: 43 Page 20 of 23 Unit: 0 Attachment B1 GUIDANCE FOR ALIGNMENT TSC ELECTRICAL LOADS TO VITAL UPS POWERED OUTLETS, Continued NQIE Number in parenthesis indicates the available continuous duty load for the designated Y panel breaker. If a breaker trips during the transfer of loads reduce the loads being transferred to that outlet and reset the tripped breaker. Extension cords are available in the TSC Admin Coordinator's file cabinet.

- Suggested Connection of Loads. [Copy machine NOT used]                                                                                           'I i

TSC outlets powered from: TSC outlets powered from: 1Y629-06 (6.5 A) TSC outlets powered from TSC outlets powered 1Y629-04 (7.5 A) (Next to TSC RP Radio Communicator's Desk) 1Y629-20 (18 A) from 2Y629-02 (20.6 A) (West Wall of TSC) (TSC engineering area back (TSC behind the copy room-south wall) machine) Continuous-Duty:_Loads: j I Flat screen monitors R*Time Computers R*Time Computers R*Time Computers (2) - 3.1A each _..(?)- 2.4A each J.1:} 2.4A each (_?)- 2.4A each Network PC (1) - 4A Miaa&URl:PCA 3;9A RMS PC (!) - 4A Intermittent-Duty loads: Radio (1_}- 0.5A Printer (1) - 4A Fax machine - SA Printer L1) - 4A **--*-*-*****-*-*-*-* Printers (~} - 4A (Assumed} RMS Printer - 0.4A Radio (1)- 0.5A Total Connected Load= 58.7A (37.4 A continuous duty load) i' Page 3 of 6

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Enclosure 2 to PLA-8077, Page 195 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 7 of 54 Unit: 0 2.2.4 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2.2.5 NEP Technical Basis #02-004 - Total Noble Gas to Iodine-131 and Total Noble Gas to Total Particulate Ratios for Use in MIDAS Evaluations Supporting SSES Emergency Plan 2.2.62.2.5 NEP Technical Basis #02-005 - Noble Gas Release Rate Limits for EALs 2.2.72.2.6 NEP Technical Basis #03-001 - Measured to Projected Ratio 2.2.8 NEP Technical Basis #04-001 - Start of Radiological Release 2.2.92.2.7 NEP Technical Basis #04-003 - Classification of Dose During Declared Emergency 2.2.102.2.8 NEP Technical Basis #04-004 - Rationale for Selection of Release Duration for Dose Assessments for Selected, Common Plant Conditions 2.2.9 NEP Technical Basis 16-001 - Frisker Response in Support of EAL Implementation and Determination of Release In Progress 2.2.10 NEP Technical Basis 23-001 - Unified RASCAL Interface Technical Design Description Version 3.7 2.2.11 NEP Technical Basis 23-002 - Unified RASCAL Interface Requirements Specification, Susquehanna Site Annex Version 3.7 2.2.112.2.12 Letter from R.V. Guzman of the NRC to B.T. McKinney of PPL, dated January 31, 2007, Issuance of Amendment, Implementation of Alternate Radiological Source Term 2.2.122.2.13 EC-RADN-1129, DBA LOCA Total Control Room Dose 2.2.132.2.14 EC-RADN-1125, CHRE and Offsite Post LOCA Dose 2.2.142.2.15 EC-ENVR-1047, Protective Action Guides, (PAGs), for the Evaluation of Abnormal, Unusual, or Unplanned Liquid Releases to the Susquehanna River 2.2.15 EC-RADN-1002, MIDAS Source Term Calculation 2.2.16 EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA 400-R-92-001 May 1992) 2.2.17 FDA Guidance: "Accidental Radioactive Contamination of Human Food and Animal Feed and Recommendations for State and Local Governments." Federal Register, pages 47073-47083, October 22, 1982 2.2.18 ICRP Publication 28, The Principles and General Procedures for Handling Emergency and Accidental Exposures of Workers. International Commission on Radiation Protection. (1978) 2.2.19 IE Notice 83 28

Enclosure 2 to PLA-8077, Page 196 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 10 of 54 Unit: 0 5.0 INSTRUCTIONS 5.1 Initial Actions (Information Use) 5.1.1 SIGN IN on TSC Access Log. 5.1.2 SIGN IN on TSC On Duty Personnel Board 5.1.3 NOTIFY Emergency Director of arrival. 5.1.4 IF available, THEN OBTAIN current x Meteorological AND vent data, x Dose calculations AND MIDAS reports x ARMs data from Plant System Server (PSS), 5.1.5 OBTAIN copies of the following forms from EP-PS-001, Emergency Planning Forms and Supplementary Instructions: x Dose Assessment Data Gathering Form x Emergency Exposure Extension Request x Emergency Personnel Dose Assessment and Protective Action Guide x Field to Projection Measurement Comparison Form x Logkeeping Instructions and Paper Log Form x Meteorological Data Acquisition Options x MIDAS Field to Projection Measurement Comparison Form x Potassium Iodide (KI) Tracking Form x Protective Action Recommendation Determination (White board in ED area) x Radiological Release Duration Guidance x Radiological Release in Progress Guidance (White board in RP area) x Return of NERO Personnel x SSES Contamination Response Plan x TSC Command and Control Briefing (White board in ED area)

Enclosure 2 to PLA-8077, Page 197 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 11 of 54 Unit: 0 x TSC/EOF Dose Assessment Flowchart (White board in RP area) x Vent Monitor Data Acquisition 5.1.6 INITIATE a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001. NOTE The Radiation Protection Coordinator position is required for TSC activation. TSC Dose Assessment positions (NOT required for TSC activation) are: x One RP Tech 1 (OSCAR) x RP II Dose Calculator x TSC Dose Calculator x RP Radio Communicator x HPN Communicator x One field team on location and ready to be dispatched OR in the process of completing equipment setup in preparation for dispatch For a beyond design basis event, if all other forms of phone communications are NOT available, a Satellite phone is available to use. Refer to EP-RM-007 for instructions on using the Satellite phone. 5.1.7 CONFIRM staff is ready to assume control of Dose Assessment including the following:

a. Prepared to perform AND evaluate dose calculations x MIDAS available x Dose assessment software operational x Plant System Server (PSS or R*Time) OR communications with Control Room available

b. Prepared to assume control of field team x Communications link established

c. Prepared to assume communications with NRC HPN x HPN communications link available 5.1.8 With the Operations Support Center (OSC) Radiation Protection (RP) Specialist, ENSURE that OSC is prepared to support TSC.

a. DETERMINE location of 2 RP technicians on shift

b. DETERMINE if RP technician call out process was initiated.

Enclosure 2 to PLA-8077, Page 198 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 12 of 54 Unit: 0 x 4 additional qualified RP personnel within 60 minutes x 4 additional qualified RP personnel within 90 minutes

Enclosure 2 to PLA-8077, Page 199 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 13 of 54 Unit: 0 5.1.9 DETERMINE OSCAR status

a. IF NOT already dispatched by Control Room, THEN DISPATCH OSCAR using either the RP technician on shift or another qualified RP personnel from OSC.

5.1.85.1.10 IF staffing issues arise, THEN NOTIFY TSC Administrative Coordinator to call out additional offsite monitoring teams OR Dose Assessment Staff. 5.1.95.1.11 OBTAIN briefing from Emergency Director (ED) including the following: x Current plant conditions x Plant prognosis x Type(s) AND magnitude(s) of release(s) x Status of the emergency 5.1.105.1.12 BRIEF TSC Dose Assessment staff on the following: x Radiological conditions in plant x Status of accountability OR evacuation, if in progress OR completed x Accident type x Release in progress declaration status 5.1.11 With the Operations Support Center (OSC) Radiation Protection Specialist, ENSURE that OSC is prepared to support TSC.

a. ENSURE TSC / RP II Dose Calculator fills in the Dose Assessment Data Gathering Form 5.1.13 AFTER TSC assumes control of the emergency, COMMUNICATE TSC is in control to the DEP / BRP.

a. DETERMINE location of 2 RP technicians on shift b.a. DETERMINE if RP technician call out process was initiated.

x 4 additional qualified RP personnel within 60 minutes x 4 additional qualified RP personnel within 90 minutes

Enclosure 2 to PLA-8077, Page 200 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 14 of 54 Unit: 0 5.1.121.1.1 DETERMINE OSCAR status

a. IF NOT already dispatched by Control Room, THEN DISPATCH OSCAR using either the RP technician on shift or another qualified RP personnel from OSC.

5.1.135.1.14 IF required to assist an emergency medical response OR a Search and Rescue team, THEN REFER TO SP-00-308, Emergency Medical Response. 5.1.145.1.15 Using RPC section in TSC Command And Control Briefing in EP-PS-001 for guidance, PARTICIPATE in periodic TSC briefings as established by ED.

Enclosure 2 to PLA-8077, Page 201 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 16 of 54 Unit: 0 5.2.3.a (continued) x Wind direction x Available monitoring or sampling results provided by RP Technicians 5.2.4 Upon habitability assessment in step 5.2.3 OR upon recommendations from OSC RP Specialist, RECOMMEND local area OR Radiologically Controlled Area (RCA) evacuation to ED if appropriate. 5.2.5 IF ALL of the following occur, x Fuel clad barrier has been declared lost x Core Spray was used to mitigate event THEN ENSURE surveys are performed or area entrance points are controlled for areas adjacent to east wall of the Control Structure within the following rooms: x C-401 Operations Work Control office (El 729) x C-402 Operations Shift Manager office (El 729) x C-413 TSC Library/Emergency Lighting Room (El 741) x C-414 NRC Conference Room (El 741) x C-203 Unit #1 Relay Room (El 698) x C-201 Unit #2 Relay Room (El 698) x C-300 Unit #1 Lower Cable Spreading Room (El 714) x C-301 Unit #2 Lower Cable Spreading Room (El 714) x C-501 Unit #1 Upper Relay Room (El 754) x C-502 Unit #2 Upper Relay Room (El 754)

a. IF exposure rates in these areas are greater than 5 mR/hr, THEN ENSURE area entrances are posted as RPC Approval Required for Entry.

b. IF personnel access to areas within 5 feet of east wall of Control Structure in these rooms is requested by RP Specialist, THEN PRESCRIBE requirements for access PER Attachment B, Guidance For Access Control For Areas Near East Wall Of Control Structure.

Enclosure 2 to PLA-8077, Page 202 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 17 of 54 Unit: 0 5.2.6 With OSC RP Specialist, ESTABLISH contamination controls AND survey frequency.

a. DIRECT performance of routine smears AND air samples.

(1) IF survey results warrant, THEN DIRECT placement of step-off pads AND friskers at doorways during releases. (2) DIRECT set up of frisking pads at stairwell door, north end of TSC, with frisker located in a low background area, near the point of access. (a) DIRECT access control to TSC from elevator by placing signs in elevator. (b) HANG FRISKING REQUIREMENTS signs at each end of TSC. (c) At a minimum, REQUIRE hand and foot survey for TSC access (d) IF release conditions warrant, i.e. free-released, THEN DIRECT RP personnel located on elevation 676 of control structure to ensure personnel reporting to TSC from tunnel access use contamination monitors. (e) IF TSC personnel arrive contaminated OR surveys indicate contamination in TSC, THEN DIRECT decontamination of TSC OR arriving personnel. x IF necessary, DISPATCH RP techstechicians to obtain supplies from the CS egress area AND TB central area decontamination room (3) IF radiological conditions change, THEN UPDATE access signs with new protective clothing AND survey requirements. 5.2.7 DISCUSS habitability at other occupied areas listed in Step 5.6.2c with OSC RP Specialist. 5.2.8 IF notified by OSC RP Specialist of OSC relocation, THEN PROVIDE support OR clarifications to this effort, as requested.

Enclosure 2 to PLA-8077, Page 203 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 18 of 54 Unit: 0 5.2.9 WHEN notified by chemistry that site samples are to be taken to offsite chemistry lab for analysis, THEN ASSESS habitability of that facility. 5.2.10 IF radiological conditions warrant, THEN, with the TSC Security Coordinator, RELOCATE Security personnel to minimize personnel dose.

a. CONSIDER release pathway AND required duration for occupying Security posts outside plant to determine if sheltering is an appropriate protective action.

NOTE Five Self Contained Breathing Apparatus (SCBAs) with five hours of air supply are staged in the Control Room/ (CR) / TSC area for deployment during a Control RoomCR Habitability event. 5.2.11 For an event that is expected to last more than five hours AND SCBA are deployed for operators to remain in the control room, INITIATE SCBA cylinder replenishment OR refilling. 5.2.12 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 204 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 19 of 54 Unit: 0 NOTE This section is applicable when TSC is in control of the emergency event; peer checks at the request of EOF or in support of EOF response can be performed, if time allows. 5.3 Offsite Dose Assessment (Reference Use) 5.3.1 EVALUATE offsite radiological conditions by reviewing available data such as: x Valid release rates (airborne AND liquid) x Field measurements x Meteorological data x Dose calculations x Affected sectors 5.3.2 EVALUATE onsite radiological conditions by reviewing available data such as: x ARMs x Possible release pathways x Drywell radiation levels measured by Containment High Rad Monitor(s) (CHRMs) x Liquid release x HVAC status AND conditions x Status of blow out panels x Fuel clad integrity

Enclosure 2 to PLA-8077, Page 205 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 20 of 54 Unit: 0 5.3.3 EVALUATE data reliability NOTE x PSS displays provide information regarding various plant parameters. If PSS data turns to a white color, that information may be suspect OR invalid AND other sources of data should be sought. x White data may be normal and acceptable due to low OR no system flow in the vent stack monitor (Ex. If SBGT is operating, the affected RB vent release rate data becomes white due to no flow) OR may indicate a release exceeding the range of the instrument OR an indication of instrumentation OR computer interface problems. x Another source of data that may be available is SPDS data display via PSS SPDS Menu. It should be noted that not all PSS data points are available on SPDS. However, for those parameters that are available on both SPDS AND PSS, SPDS may provide alternate source of required information. x If all PSS data sources become unavailable, i.e. both PSS and SPDS data displays turn to a white color, additional alternate data sources should be sought such as data availability via hard wired OR independent data sources in control room OR locally in the plant. x White vent data should be considered as a potential unmonitored release condition unless Engineering or Operations indicates otherwise.

a. IF low confidence (white) vent release rate OR meteorological data PSS data exists, THEN CONSULT with Engineering to determine if condition is normal (i.e.,

per design) AND if vent release rate data are valid from Engineering OR Dose Assessment perspective.

b. IF vent release rate OR meteorological data is suspect, THEN (1) REQUEST Engineering to promptly pursue corrective actions (2) USE a RP Technician to communicate vent data from Control Room OR local VERMS terminals, if available, PER Vent Monitor Data Acquisition in EP-PS-001.

(a) WHEN EOF takes control of emergency, ENSURE vent release rate data is communicated to the EOF. (3) DIRECT Chemistry to obtain to obtain Chemistry vent sample data as often as possible AND DISCUSS alternate methods to obtain release data (e.g., HP air samples) (a) USE vent sample data to verify previous URI dose assessment calculation PER TSC/EOF Dose Assessment Flowchart in EP-PS-001

Enclosure 2 to PLA-8077, Page 206 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 21 of 54 Unit: 0 5.3.3.b (continued) (4) IF vent data for the respective pathway is still not available, THEN DIRECT TSC Dose Calculator to use appropriate alternate data such as grab sample (vent, HP air samples) results, default noble gasURI methods (other than Monitored and Field Team) to iodine/particulate ratios, OR noble gas to iodine ratios judged by Engineering to be consistent with current release rate conditionscomplete required calculations PER the TSC/EOF Dose Assessment Flowchart in affected unit(s) in Forward CalculationEP-PS-001. (4)(5) ENSURE field monitoring teams (FMTOSCAR) are taking air samples as often as possible. (5)(6) REPORT conditions as a potential unmonitored OR unfiltered release, until Chemistry sample or field team data are confirmed. (7) IF meteorological data is not reliable, THEN DIRECT TSC Dose Calculator AND RadiocommunicatorTSC RP Radio Communicator to use alternate meteorological data PER Meteorological Data Acquisition Options in EP-PS-001, if necessary.

Enclosure 2 to PLA-8077, Page 207 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 22 of 54 Unit: 0 NOTE Data is suspect if the NG/I-131 release rate ratio is less than 1,000 for a filtered release through a given vent. 5.3.4 CHECK if reported Iodine-131 release rates from Chemistry OR other analyses seem reasonable when compared with NG, for current plant conditions, AND TAKE appropriate actions for additional dose assessment or FMTs. NOTE Data is suspect if the NG/Particulates release rate ratio is less than 10,000 for a filtered release through a given vent. 5.3.5 CHECK if reported particulate release rates from Chemistry OR other analyses seem reasonable when compared with NG, for current plant conditions, AND TAKE appropriate actions for additional dose assessment OR directing FMTs. 5.3.6 ASSIST in obtaining release characteristics AND pathways on Engineering Dose Assessment Support Information Worksheet from Engineering. 5.3.7 SUPPORT TSC Dose Calculator to determine type of MIDAS dose calculation to be performed by consulting TSC/EOF Dose Assessment Flowchart in EP-PS-001

a. IF TSC Dose Calculator is NOT present in the TSC, THEN ASSIST RP II Dose Calculator with performing appropriate dose calculation PER TSC/EOF Dose Assessment Flowchart in EP-PS-001.

5.3.85.3.4 IF a release in progress is declared, THEN

a. ENSURE OSCAR OR FMT A, as appropriate, are taking air samples as often as possible.

(1) IF Oscar is NOT available, THEN ENSURE FMT A is dispatched on OSCAR route per Field Monitoring Team Strategy Notes in EP-PS-001.

Enclosure 2 to PLA-8077, Page 208 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 23 of 54 Unit: 0 NOTE A Forward calculation is the preferred choice for valid calculations unless the release is unmonitored, there are multiple sources (use Multiple Menu), OR a back calculation provides more conservative results.

b. ENSURE TSC / RP II Dose Calculator performs at least one valid dose calculation.

(1) IF TRM limits shown in Note 41 of TSC/EOF Dose Assessment Flowchart in EP-PS-001 are exceeded, OR IF General Emergency is declared, THEN DIRECT AND SUPPORT TSC / RP II Dose Calculator to perform MIDAS dose calculations every 15 minutes.

Enclosure 2 to PLA-8077, Page 209 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 24 of 54 Unit: 0 5.3.5 ASSIST TSC Dose Calculator to determine release characteristics AND pathways to be used in URI dose assessment calculation PER TSC/EOF Dose Assessment Flowchart in EP-PS-001

a. IF TSC Dose Calculator is NOT present in the TSC, THEN DIRECT AND SUPPORT RP II Dose Calculator with performing appropriate dose calculation PER TSC/EOF Dose Assessment Flowchart in EP-PS-001.

NOTE S.B. line in URI report and screen is equivalent with SSES EPB.

b. REVIEW input AND calculation results AND RECORD name, signature, date AND time the review was complete in the Review By field on the URI Dose Assessment report.

NOTE A valid calculation is to be used for EAL Classification, Initial PAR determination OR a PAR upgrade. 5.3.95.3.6 IMMEDIATELY INFORM ED on potential EAL AND PAR changes based on Dose Assessment results 5.3.105.3.7 IF containment venting is needed as determined by Engineering OR Control Room OR Engineering, THEN

a. ENSURE TSC / RP II Dose Calculator performsthat a dose assessment for venting the containment PER TSC/EOF Dose Assessment Flowchart in EP-PS-001 is performed.

b. ENSURE dose assessment results are immediately communicated to:

(1) TSC Operations Coordinator OR Shift Manager of affected unit for potential entries into EOP procedures (2) ED

c. IF necessary THEN RECOMMEND to ED a PAR based on dose assessment results PER Step 0.

5.3.115.3.8 REVIEW measured/ / projected EDE or CDE doseexposure rate OR Thyroid CDE ratios AND TAKE appropriate actions for additional dose assessment OR directing FMTs per instructions in MIDAS Field to Projection Measurement Comparison Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 210 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 25 of 54 Unit: 0 NOTE NG / Iodines and NG / Particulates release rate ratios are identical in URI and their ratios are shown in the URI dose assessment report. 5.3.9 CHECK if reported Iodine and Particulates release rates from Chemistry OR other analyses seem reasonable when compared with NG, for current plant conditions, AND TAKE appropriate actions for additional dose assessment OR FMT repositioning. 5.3.125.3.10 ENSURE Dose Assessment resultsPackages are communicated to EOF AND, it TSC is in control, to Offsite organizations (NRC, DEP/BRP) per their request. 5.3.135.3.11 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001. I 5.41.1

 =  _ = Support = for Determination
                          = =          of Radiological
                                                 =Release  =       In=Progress=    (Reference
                                                                                            =   Use)

Enclosure 2 to PLA-8077, Page 211 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 26 of 54 Unit: 0 NOTE x Emergency Director (ED) has the responsibility to declare a release in progress due to event. x This section is applicable when TSC is in control of the emergency event; peer check at the request of EOF or in support of EOF response can be performed, if time allows. 5.4 Support for Determination of Radiological Release In Progress (Reference Use) 5.4.1 ASSESS if there is ana radiological release in progress due to event PER Radiological Release in Progress Guidance in EP-PS-001

a. IF it is believed that an airborne radiological release is in progress, THEN (1) OBTAINCONSULT with Engineering concurrence AND ASK Engineering to characterize release on Engineering Dose Assessment Support Information Worksheet (2) Withor TSC Dose Calculator AND Engineering, ESTABLISH at least the following:

x MonitoredOperations Coordinator OR Unmonitored x Filtered OR Unfiltered; x If unfiltered, appropriate filtration ratios x Estimated Release duration PER Radiological Release Duration Guidance in EP-PS-001 or MIDAS Hard Cards, and basis for this estimation IMMEDIATELY COMMUNICATE information AND RECOMMEND ED to declare an airborne radiological release in progress due to event

b. IF OSC Chemistry Coordinator OR OSC Coordinator reports, OR it is believed that a liquid radiological release is in progress due to event PER Radiological Release in Progress Guidance OR Protective Action Recommendation (PAR) Determination (Liquid PAR chart) in EP-PS-001.

THEN IMMEDIATELY COMMUNICATE information AND RECOMMEND ED to declare a liquid radiological release in progress due to event. 5.4.2 IF ED declares an airborne radiological release in progress due to event, THEN,

a. IF Engineering Dose Assessment Support Information Worksheet is NOT available,

Enclosure 2 to PLA-8077, Page 212 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 27 of 54 Unit: 0 THEN ASK Engineering to characterize the release in accordance with Step 5.4.1a(1). b.a. DIRECT TSC / RP II Dose Calculator to initiate dose calculations in accordance with their procedures AND TSC/EOF Dose Assessment Flowchart in EP-PS-001. c.b. ENSURE TSC E-Plan Communicator to indicateindicates an airborne radiological release in progress AND the wind speed and direction from the appropriate meteorological tower (10 OR 60 m) on Emergency Notification Report (ENR) OR Follow-up Notification Report (FNR) form. d.c. PROVIDE information to DEP/BRP. e.d. ENSURE OSCAR OR FMT A, as appropriate, periodically perform radiation surveys AND collect air samples throughout release duration in support of EAL changes AND release characterization. f.e. DETERMINE appropriate radiological Emergency Classification using EP-RM-004, EAL Classification Bases in accordance with stepsection 5.55.5.

Enclosure 2 to PLA-8077, Page 213 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 28 of 54 Unit: 0 5.4.3 IF event is still in progress AND aan airborne release in progress was previously declared, THEN ADVISE ED that release is terminated when:

a. Radiological Release in Progress Guidance in EP-PS-001 shows that No (Airborne) Release is in Progress AND

b. Emergency event is downgraded or terminated PER EP-00-003.

AND

c. Any releases have been reduced to levels allowed by plant Technical Specifications AND are below TRM values.

5.4.4 IF ED declares a liquid radiological release in progress due to event, THEN

a. ENSURE TSC E-Plan Communicator indicates liquid radiological release in progress AND the 10 m met tower wind speed and direction on ENR OR FNR form.

(1) IF both airborne AND liquid releases are in progress, THEN USE the met tower applicable to the airborne release in progress. a.b. Using telephone numbers in EP-RM-007, Emergency Telephone Instructions and Directory, to NOTIFY Danville Water Authority of liquid release AND activation of SSES Emergency Plan. b.c. USEUsing telephone numbers in EP-RM-007 to, NOTIFY DEP/BRP of liquid release. c.d. ENSURE NRC is notified through the HPN line that a liquid release has occurred. d.e. ENSURE OSC Chemistry Coordinator performs calculations to determine potential liquid PAR. (1) IF NO PAR is required from step 5.7.6a, THEN NOTIFY DEP/BRP AND NRC that no liquid PAR is required.

e. ENSURE TSC E-Plan Communicator indicates liquid radiological release in progress on Emergency Notification Report (ENR) form.

Enclosure 2 to PLA-8077, Page 214 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 29 of 54 Unit: 0

f. REQUEST OSC Chemistry Coordinator to activate SSES Environmental Sampling Teams to perform monitoring AND sampling in Susquehanna River PER EP-PS-221 AND EP-PS-248 procedures, until liquid releases are terminated AND release passed Danville.

5.4.5 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001. NOTE This section is applicable when TSC is in control of the emergency event; peer check at the request of EOF or in support of EOF response can be performed, if time allows. 5.5 Support for Emergency Classifications (Reference Use) 5.5.1 EVALUATE available radiological airborne OR liquid release information. NOTE x Trending may involve evaluating the rate of change of measured data. For example, what is the rise or fall in CHRM exposure rates for a given unit of time (15 min, 30 min, etc.) x Radiological Emergency Classification triggers include ARM data in Table R, entry conditions in rows B and D in Table F and in CG1.1, CG1.2, EU1.1, SU4.1 and SU4.2 EALs 5.5.2 IF triggers for radiological emergency classification PER EP-RM-004 are met, THEN IMMEDIATELY RECOMMEND changes in classification to Emergency Director (ED)

a. WHEN evaluating radiological data, THEN DETERMINE rate of change, if possible, to assist with determining when an EAL upgrade (OR downgrade) may occur.

Enclosure 2 to PLA-8077, Page 215 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 30 of 54 Unit: 0 NOTE Control Room needs radiological data to evaluate entry conditions AND action levels for EOP Procedures. For example, EO-000-105 procedureEOP procedures may require reactor SCRAM AND RPV control when an Alert based on radiological conditions is met, OR rapidemergency depressurization if a General Emergency based on radiological conditions is met. 5.5.3 IF following are met,

a. Conditions are trending towards an Alert declaration, an Alert is declared OR a concurrent EAL at Alert level is identified, all based on Table R in EP-RM-004, EAL Classification User Manual OR

b. Conditions are trending towards a General Emergency declaration, a GE is declared OR a concurrent EAL at GE level is identified, all based on Table R in EP-RM-004, EAL Classification Bases THEN PROVIDE release and dose assessment information to Operations Coordinator to request Shift Manager to evaluate a potential entry in EO-000-105 procedure.

5.5.4 IF ED declares a change in Emergency Classification level, THEN

a. INFORM TSC E-Plan Communicator OR ED of the met tower (10 OR 60 m) used OR potentially used in a dose assessment calculation AND ENSURE the ENR form contains appropriate data on wind direction and speed.

a.b. COMMUNICATE informationclassification change to DEP/BRP. 5.5.5 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 216 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 31 of 54 Unit: 0 5.6 On Site Protective Actions (Reference Use) 5.6.1 EVALUATE radiological status of plant and releases by reviewing available data such as: x ARMs x Possible release pathways x Drywell radiation levels measured by Containment High Rad Monitor(s) (CHRMs) x Liquid release x CAMs x INDIA Teams survey data x HVAC status AND conditions x Status of Turbine Building doors x Status of blow-out panels x Fuel clad integrity 5.6.2 WHEN Site Evacuation is initiated, THEN

a. With TSC Security Coordinator and Emergency Director, (ED), DISCUSS notification of occupied buildings AND areas in Exclusion Zone.

b. DISCUSS route of egress from Protected Area

Enclosure 2 to PLA-8077, Page 217 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 32 of 54 Unit: 0 5.6.2 (continued)

c. IF following areas are occupied:

x Warehouse #2 (500kV yard) x 500 KV Switchyard x Site Garage x Hazardous Waste Yard x SSES Access Processing Facility x SSES Learning Center x West Building / Towers Club x Information Center x Riverlands x SSS Shed / Security Training Trailer / Firing Range x Sewage Treatment Plant x River Intake Structure x Environmental Lab x Offsite loading (warehouse) THEN ENSURE personnel is notified to evacuate site. NOTE Two bull horns are located near the Security Coordinators desk. One bull horn is located in A Field Monitoring Team van. (1) SEND extra staff, (example: Security personnel OR Field Monitoring Teams (FMT) OR OSC personnel), with a bull horn to notify these facilities of Site Evacuation. (2) IF the EOF is activated AND a Field Team Director (FMT) is to be usedrequired to perform notifications, THEN REQUEST Field Team DirectorASSIST FMT to coordinate notifications.

Enclosure 2 to PLA-8077, Page 218 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 33 of 54 Unit: 0 5.6.4.c (continued) (3) IF OSC personnel are used to make notifications, THEN REQUEST TSC Damage Control Team Coordinator to dispatch personnel from OSC to perform notifications. 5.6.3 EVALUATE AND RECOMMEND protective action for SSES personnel.

a. WHEN evaluating protective actions, THEN CONSIDER the following:

x REDUCE projected release time based on weather conditions, total inventory, OR damage control measures. x RESTRICT eating and drinking for OSC, security AND other staff working in contaminated area, including TSC and Control Room, if appropriate. x DO NOT REACT on one piece of information until it can be verified to be correct.

b. EVALUATE anticipated or actual emergency exposures.

NOTE Radiation Protection Specialist will: x Evaluate emergency exposures prior to approval; x Brief on the use of KI and issuance once approved.

c. ASSESS emergency exposures which may have occurred in excess of station limits.

d. ASSESS AND RECOMMEND local OR Radiologically Controlled Area (RCA) evacuation to ED if necessary.

e. DETERMINE actions per Emergency Personnel Dose Assessment and Protective Action Guide in EP-PS-001.

5.6.4 IF vehicles or personnel are suspected to be contaminated, THEN with OSC RP Specialist, DETERMINE which remote assembly area(s) to be used based upon plume exposure pathway.

a. DIRECT RP Specialist to set up a remote assembly area PER EP-00-005, Remote Assembly Area Contamination Control.

b. DETERMINE recommended evacuation route to remote assembly.

Enclosure 2 to PLA-8077, Page 219 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 34 of 54 Unit: 0 5.6.5 IF TSC is in control of emergency, TNEN ENSURE Field Monitoring Teams (FMTFMTs) are maintaining their exposure ALARA.

a. IF affected FMT ED exceeds 400 mrem OR NOTE An Adult Thyroid CDE rate of 1,000 mrem/hr (4,000 ccpm) would imply a CDE greater than 5 rem/shift assuming 50% affected area occupancy factor.

IF Cartridge Readings are greater than 4,000 ccpm, THEN ENSURE TSC RP Radio Communicator initiated dose tracking and is using effective exposure control measures for the affected FMT a.b. IF feasible, THEN ENSURE teams are rotated, OR new teams are called out to minimize exposure AND MAINTAIN adult thyroid exposure under 10 rem CDE AND TEDE under 4 rem. b.c. Using Field Team Monitoring Strategy Notes in EP-PS-001 AND TSC RadiocommunicatorRP Radio Communicator input, EVALUATE the risk of moving FMTs further away from plant vs. need for a reading in high radiation fields in determining whether an emergency dose extension is warranted for a FMT, particularly for OSCAR.

c. IF measured exposure rate exceeds 800 mR/h OR NOTE An Adult Thyroid CDE rate of 1,000 mrem/hr (7,500 ccpm) would imply a CDE greater than 5 rem/shift assuming 50 % affected area occupancy factor.

IF Cartridge Readings are greater than 7,500 ccpm, THEN ENSURE TSC Radiocommunicator initiated dose tracking and is using effective exposure control measures for the appropriate Field Monitoring Team (FMT) 5.6.6 IF Adult Thyroid CDE is determined to be potentially greater than 10 rem, as reported by OSC RP Specialist OR, if TSC is in control, by TSC RadiocommunicatorRP Radio Communicator,

Enclosure 2 to PLA-8077, Page 220 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 35 of 54 Unit: 0 x DIRECT OSC RP specialist to fill in the names of affected INDIA team personnel on a Potassium Iodide (KI) Tracking Form in EP-PS-001 AND FAX the form to the TSC, if applicable. x WithIF TSC Radiocommunicator,is in control AND applicable, THEN DIRECT TSC RP Radio Communicator to fill in the names of affected FMT personnel on a Potassium Iodide (KI) Tracking Form in EP-PS-001, if applicable. (1) HAND IN a Potassium Iodide (KI) Tracking Form in EP-PS-001 to the TSC Security Coordinator AND DIRECT them to fill in the required information for Security personnel positioned in outside stationary or roving security posts.

a. OBTAIN ED approval for affected personnel to use KI tablets on Potassium Iodide (KI) Tracking Forms in EP-PS-001.

Enclosure 2 to PLA-8077, Page 221 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 36 of 54 Unit: 0 5.6.6 (continued) NOTE Potassium Iodide (KI) is stored in the Control Room for Operations use and in the U2 RP Control Point for other personnel.

b. IF applicable, THEN OBTAIN KI tablets for affected Security personnel.

(1) HAND INOUT the required number of KI tablets to the TSC Security Coordinator with instructions on precautions listed on the form.

c. Once approval from ED is received, x DIRECT OSC RP Specialist to recommend issuance of KI to affected INDIA team personnel, asif applicable.

x IF TSC is in control AND applicable, THEN DIRECT TSC RadiocommunicatorRP Radio Communicator to recommend issuance of KI to affected FMT personnel, as applicable. (a) DIRECT TSC Security Coordinator to recommend issuance of KI to affected Security personnel. (1) ENSURE all personnel is notified of precautions regarding interactions with other drugs PER Emergency Personnel Dose Assessment and Protective Action Recommendation (PAR) Guide. 5.6.7 FOLLOWING a Site Area Emergency (SAE) declaration AND AFTER site evacuation is complete, PREPARE for potential KI issuance for ALL personnel onsite. x DIRECT OSC RP Specialist to fill in the names of ALL INDIA teams AND OSC personnel on a Potassium Iodide (KI) Tracking Form in EP-PS-001 AND FAX the form to the TSC. x HAND INOUT a Potassium Iodide (KI) Tracking Form in EP-PS-001 to the TSC Security Coordinator AND DIRECT them to fill in ALL Security personnel remaining onsite to this form. x FILL IN the names of ALL Control Room AND TSC personnel on a Potassium Iodide (KI) Tracking Form in EP-PS-001, OR ASK TSC Administrative Coordinator to perform this operation AND return the form. x IF TSC is in control, THEN DIRECT TSC RP Radio Communicator to fill in the names of ALL FMTs personnel on a Potassium Iodide (KI) Tracking Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 222 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 37 of 54 Unit: 0 5.6.8 IF a General Emergency with a release in progress is declared OR a General Emergency is declared, and a release is imminent, THEN,

a. IF NOT already completed, THEN PERFORM step 5.6.7.

b. OBTAIN ED approval for ALL onsite personnel, including FMTs if TSC is in control, to use KI tablets on Potassium Iodide (KI) Tracking Forms in EP-PS-001.

NOTE Potassium Iodide (KI) is stored in the Control Room for Operations use and in the U2 RP Control Point for other personnel.

c. OBTAIN KI tablets for ALL TSC AND Security personnel onsite.

d. HAND INOUT the required number of KI tablets to the TSC Security Coordinator with instructions on precautions listed on the form.

e. Once approval from ED is received, x DIRECT OSC RP Specialist to recommend issuance of KI to ALL INDIA teams AND OSC personnel.

x DIRECTIF TSC Radiocommunicatoris in control, THEN DIRECT TSC RP Radio Communicator to recommend issuance of KI to ALL -FMTFMTs personnel. x DIRECT TSC Security Coordinator to recommend issuance of KI to ALL Security personnel onsite. x ENSURE KI is recommended for ALL TSC AND CR personnel. x ENSURE ALL personnel is notified of precautions regarding interactions with other drugs PER Emergency Personnel Dose Assessment and Protective Action Recommendation (PAR) Guide.

Enclosure 2 to PLA-8077, Page 223 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 38 of 54 Unit: 0 5.6.9 IF assistance with KI issuance is required, THEN, using contact information in EP-RM-007, CONTACT Consulting Radiological Physician for input regarding the following: x Administration of subsequent doses of KI x Potential drug interaction x Cessation of KI intake NOTE RWP 8000 applies to INDIA team activities, RWP 8001 applies to OSCAR activities, RWP 8002 to Field Monitoring Teams activities AND RWP 8888 is for drills and exercises. 5.6.10 ENSURE necessary changes to RWPs are implemented.

a. COORDINATE changes with OSC RP Specialist OR DASU 5.6.11 Upon recommendation from OSC RP Specialist OR, if TSC is in control, TSC RadiocommunciatorRP Radio Communicator, IF estimated doses are greater than 4 rem TEDE OR 50 rem Adult Thyroid CDE, THEN

a. PROCESS AND OBTAIN ED approval on Emergency Exposure Extension Request in EP-PS-001 for dose extensions for required personnel.

b. Once approval from ED is received, REQUEST OSC RP Specialist OR, if applicable, TSC RadiocommunicatorRP Radio Communicator, to communicate new dose allowance and applicable ALARA information from Emergency Exposure Extension Request form AND Emergency Personnel Dose Assessment and Protective Action Guide in EP-PS-001 to the required personnel.

5.6.12 RESPOND to requests from EOF Dose Assessment staff for occupational exposure control information. 5.6.13 DIRECT OSC RP Specialist OR TSC Radiocommunicator, if TSC is in control, TSC RP Radio Communicator, to ensure that bioassay for exposed INDIA team AND FMT members to determine actual internal exposure is performed PER Section C in Emergency Personnel Dose Assessment and Protective Action GuideExposure Extension Request form in EP-PS-001. 5.6.14 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 224 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 39 of 54 Unit: 0 NOTE This section is applicable when TSC is in control of the emergency event; peer check at the request of EOF or in support of EOF response can be performed, if time allows. 5.7 Support for Off Site Protective Actions Recommendations (Reference Use) 5.7.1 OBTAIN the following data needed to assess magnitude and anticipated duration of offsite releases: x Release rates AND trends x Prognosis for release AND continued release using Radioactive Release Duration Guidance x In plant source terms AND leakage pathway(s) x Meteorological OR river flow data x Dose calculations x Field data x Plume direction AND affected sectors 5.7.2 Following a General Emergency (GE) declaration, RECOMMEND Initial Protective Action Recommendations (PAR) to Emergency Director PER Protective Action Recommendation Determination in EP-PS-001. NOTE PARs are evaluated by the Emergency Director, Operations Coordinator, Technical Support Coordinator AND Radiation Protection Coordinator in the TSC as well as by the Shift Manager in the Control Room.

a. PROVIDE radiological input required to determine the appropriate protective actions using the following:

(1) Dose at Emergency Plan Boundary (EPB), 2 AND 5 miles (2) Type of calculationRelease Pathway AND method OR field monitoring results used to estimate dose including key assumptions OR limitations. (3) Release height (10 OR 60 m) used in dose assessment calculations. 5.7.3 AFTER ED declares a PAR due to an airborne release OR a PAR change, COMMUNICATE information to DEP/BRP.

Enclosure 2 to PLA-8077, Page 225 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 40 of 54 Unit: 0 NOTE x Based on data availability, completion of Step 5.7.35.7.4 may require more than 15 minutes. x When such data is available, PARs beyond 10-mile EPZ should be based on vent sample calculations OR verified field data. 5.7.4 EVALUATE if an airborne release PAR beyond 10 miles is appropriate. 5.7.55.7.4 IF 10001,000 mrem TEDE OR 50005,000 mrem child Thyroid CDE is exceeded at 10 miles, THEN THEN EVALUATE if an airborne release PAR beyond 10 miles is appropriate.

a. DIRECT TSC Dose Calculator to identify affected sectors AND associated distance downwind for which PAGs are exceeded.

NOTE URI does not provide for analysis beyond 50 miles for the filed team (back calculation) method.

b. IF PAR is based on a Back Calculation AND an Air Sample is NOT provided, THEN, DIRECT RP Radio Communicator to request applicable Field Team to obtain andata at the plume edge, including air samplesamples (a) ENSURE dose assessment is redone to include this information AND CHANGE OR VALIDATE previous PAR (3) IMMEDIATELY COMMUNICATE need to consider PARs beyond 10-mile EPZ to ED.

c. CONSULT with Engineering, Operations AND ED to communicate the need to consider PARs beyond 10-mile AND to verify that dose projections are consistent with plant conditions.

Enclosure 2 to PLA-8077, Page 226 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 41 of 54 Unit: 0 5.7.4 (continued)

d. ENSURE dose assessment is re-performed to include new information AND CHANGE OR VALIDATE previous PAR d.e. DISCUSS PAR beyond 10-mile EPZ with TSC Dose Calculator, Engineering, Operations, ED AND State representatives, considering at least the following x Model uncertainty x Wind shifts x Methodology uncertainty with distance x Release characteristics x Plant status x Placement of FMT x Field data x Reanalysis of questionable data

Enclosure 2 to PLA-8077, Page 227 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 42 of 54 Unit: 0 5.7.4 (continued) e.f. IF a PAR beyond EPZ is confirmed, THEN IMMEDIATELY RECOMMEND ED to issue a PAR beyond 10 miles in accordance with the PAR Determination flowchart. 5.7.65.7.5 Following initial PAR, CONTINUE to evaluate for PAR changes AND RECOMMEND revising airborne release PARs based on increasing dose levels OR wind shifts in accordance with PAR Determination Flowchart.

a. INFORM ED if release height (10 OR 60 m met tower) changes in dose calculation.

5.7.75.7.6 IF OSC Chemistry Coordinator identifies need for liquid release protective action recommendations, THEN:

a. DETERMINE Liquid PAR PER Protective Action Recommendation Determination guidance (Liquid PAR chart) in EP-PS-001.

b. IMMEDIATELY NOTIFY ED of potential Liquid PARs.

5.7.85.7.7 IF ED declares a Liquid PAR, THEN

a. ENSURE TSC E-Plan Communicator indicates liquid PAR AND the 10 m met tower wind speed and direction on ENR.

(1) IF both airborne AND liquid releases are in progress, THEN USE the met tower applicable to the airborne release in progress on the ENR. a.b. Using telephone numbers in EP-RM-007, NOTIFY DEP/BRP of liquid release PAR to divert drinking water at Danville. (1) DO NOT COMMUNICATE liquid PAR to Danville Water Authority b.c. NOTIFY NRC through the HPN line that a liquid release PAR to divert drinking water at Danville was recommended to the State of Pa. 5.7.95.7.8 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001. 5.8 DEP/BRP Communications (Information Use) 5.8.1 WHEN TSC is in control of the emergency THEN COMMUNICATE the following information to DEP/BRP as they occur:

Enclosure 2 to PLA-8077, Page 228 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 43 of 54 Unit: 0 x TSC in control x Radiological Release in Progress (airborne AND liquid) x Emergency Action Level Declarations x Protective Action Recommendations

Enclosure 2 to PLA-8077, Page 229 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 45 of 54 Unit: 0 5.11 Shift Turnover (Information Use) 5.11.1 REMAIN at duty station with full responsibility until properly relieved. 5.11.2 IF State has issued a PAR, THEN REFER TO Return of NERO Personnel in EP-PS-001 for guidance in returning personnel to site.

a. COORDINATE return of personnel through the Administrative Coordinator.

5.11.3 ENSURE TSC Radiation Protection personnel provide briefings to replacement personnel. 5.11.4 Using an updated Dose Assessment Data Gathering Form in EP-PS-001, BRIEF On-coming RPC on status of both emergency AND shift turn over status including the following: x Current status of plant x Emergency classification x Big Picture x Assigned open items AND priority of each x Actions taken AND results x Current radiological conditions x Initial AND long term manning schedules in TSC 5.11.5 ADVISE off going TSC staff of protective actions that should be taken when leaving the facility. NOTE SSES badge and Dosimeters of Legal Records (DLR) are needed to return to site after State has issued a Protective Action Recommendation. 5.11.6 ADVISE personnel to take SSES badge AND DLR when leaving facility.

a. IF personnel doses were estimated to exceed 100 mrem for shift, THEN ENSURE DLR are processed.

5.11.7 WHEN shift turnover is complete, THEN NOTIFY Emergency Director. 5.11.8 LEAVE a contact telephone number with Administrative Coordinator.

Enclosure 2 to PLA-8077, Page 230 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 46 of 54 Unit: 0 5.12 Event Termination (Information Use) 5.12.1 PARTICIPATE in emergency event debriefing. 5.12.2 ENSURE Computer Engineering provides URI input / output data to NEP Department. 5.12.21.1.1 FORWARD forms, logs, data, AND other documentation to: x TSC Administrative Coordinator OR x A Drill controller 5.12.3 RETURN work area to a ready condition. 5.12.4 IF personnel doses were estimated to exceed 100 mrem for shift, THEN ENSURE DLR are processed. 5.12.5 FORWARD forms, logs, data, AND other documentation to: x TSC Administrative Coordinator OR x A Drill controller END of Instructions

Enclosure 2 to PLA-8077, Page 231 of 560 RADIATION PROTECTION COORDINATOR EP-PS-104 Revision: 44 Page 47 of 54 Unit: 0 6.0 RECORDS x Dose Assessment Summary Sheets x Engineering Dose Assessment Support Information Worksheet x MIDAS Field to Projection Measurement Comparison FormForms x NUREG 1228 Event Tree Parameters for Dose Assessment x Potassium Iodide (KI) Tracking Form x Emergency Exposure Extension Request x All logs, data and documented communications generated.

Enclosure 2 to PLA-8077, Page 232 of 560 RADIATION PROTECTION COORDINATOR Attachment A EP-PS-104 Revision: 44 Page 48 of 54 Unit: 0 Attachment A, RPC Hard Card MAINTAIN a chronological event log for activities in this procedure including: Facility Habitability (Section 5.2) WHEN evaluating facility habitability, CONSIDER radiological and non-radiological conditions. CONSIDER mobilizing remote ARMs or CAMs to assess onsite habitability areas OR in support of EAL entries. ENSURE habitability is assessed in plant, control structure AND accountability areas. RECOMMEND local area or RCA evacuation to ED if appropriate MONITOR fuel clad barriers and use of core spray to determine impacts AND controls for control structure. ESTABLISH contamination controls and survey (routine smears AND air samples) frequency. DISCUSS habitability at other occupied areas with OSC RP Specialist. IF necessary, PROVIDE support OR clarifications for OSC relocation. IF necessary, ENSURE habitability is assessed at off-site chem lab. IF radiological conditions warrant, ENSURE Security personnel is relocated. ID For an event that is expected to last more than -five5 - hours AND SCBA are deployed for operators to remain in the control room, INITIATE SCBA cylinder replenishment OR refilling. Offsite Dose Assessment, if TSC is in control (Section 5.35.3) EVALUATE AND REVIEW available offsite and onsite dataradiological conditions EVALUATE data reliability AND IMPLEMENT countermeasures if questionable data exists IF white data exists, with Engineering support, VALIDATE if condition is normal IF vent release rate and meteorological data is suspect, REQUEST Engineering to promptly pursue corrective actions; SEND a Technician to communicate vent release rate data from Control Room or local VERMS terminals, if applicable; REQUEST Chemistry to obtain or confirm vent sample data; DIRECT staff to use appropriate alternate data results in Forward Calculation; ENSURE OSCAR is taking air samples; REPORT conditions as a potential unmonitored or unfiltered release until confirmed otherwise; OR DIRECT staff to use alternate meteorological data, if necessary. CHECK if reported NG/I-131 and NG/Particulates ratios seem reasonable for plant conditions AND, if necessary, TAKE actions for additional dose assessment OR directing FMTs FORM EP-PS-104-1 Rev. 11, Page 1 of 5

Enclosure 2 to PLA-8077, Page 233 of 560 RADIATION PROTECTION COORDINATOR Attachment A EP-PS-104 Revision: 44 Page 49 of 54 Unit: 0 ASSIST in obtaining release characteristics and pathway from Engineering ASSIST in determining the appropriate dose calculation to be run ENSURE TSC / RP II Dose Calculator performs valid dose calculation, if necessary FollowingIF vent release rate AND meteorological data is suspect, IMPLEMENT countermeasures, as necessary. If a release in progress declarationis declared, ENSURE FMT, as appropriate,OSCAR is taking air samples as often as possible and as necessary AND ENSURE TSC / RP II Dose Calculator performs one valid dose calculation IF site total release rates exceed TRM limits or GE is declared, DIRECT TSC / RP II Dose Calculator to perform dose calculations every 15 minutes ASSIST in determining the appropriate dose calculation to be run, REVIEW AND SIGN ON the calculation performed. IMMEDIATELY INFORM ED on potential EAL AND PAR changes based on Dose Assessment calculations IF conditions are metneeded, ENSURE TSC Dose Calculator performs a dose assessment for containment venting is performed, COMMUNICATE results to TSC Operations Coordinator or Shift Supervisor AND ED AND RECOMMEND ED a PAR, if necessary. CHECK if measured / projected exposure rate OR Thyroid CDE ratios OR reported NG/I or NG/Particulates release ratios seem reasonable for plant conditions AND, if necessary, TAKE actions for additional dose assessment OR directing FMTs ENSURE Dose assessment results are communicated to EOF AND, if requested, to NRC, AND DEP/BRP. Support for Determination of Radiological Release In-Progress, if TSC is in control (Section 5.45.4) ASSESASSESS if there is a radiological release in progress due to an event IF believed an airborne radiological release is in progress, OBTAIN concurrence AND ASKapplicable, CONSULT with TSC Operations Coordinator or Engineering to characterize release AND, IF in agreement,OR IMMEDIATELY RECOMMEND ED to declare an airborne release in progress due to event IF OSC Chemistry Coordinator reports, OR it is believed that a liquid radiological release is in progress due to event, IMMEDIATELY COMMUNICATE information ANDIF applicable, IMMEDIATELY RECOMMEND ED to declare a liquid radiological release in progress due to event IF ED declares an airborne radiological release in progress, IF not already performed, CHARACTERIZE release with Engineering support FORM EP-PS-104-1 Rev. 11, Page 2 of 5

Enclosure 2 to PLA-8077, Page 234 of 560 RADIATION PROTECTION COORDINATOR Attachment A EP-PS-104 Revision: 44 Page 50 of 54 Unit: 0 DIRECT Dose Assessment personnel to initiate dose calculations AND field monitoring ENSURE TSC E-Plan Communicator indicates an airborne release in progress AND appropriate wind speed and direction (10 OR 60 m met tower) on ENR OR FNR form PROVIDE information to DEP/BRP. DIRECT FMTs (OSCAR) to periodically collect air samples throughout release duration IF applicable, DETERMINE appropriate radiological Emergency Classification AND OBTAIN concurrence from Engineering ADVISE ED when airborne radiological release is terminated IF ED declares a liquid radiological release in progress due to event, ENSURE TSC E-Plan Communicator indicates liquid release AND the appropriate met tower wind speed and direction on ENR form NOTIFY Danville, DEP/BRP AND NRC of liquid release ENSURE OSC Chemistry Coordinator performs calculations to determine a potential liquid PAR ENSURE TSC E-Plan Communicator indicates liquid release on ENR form DIRECT activation of Environmental teams to monitor for liquid releases Support for Emergency Classifications, if TSC is in control (Section 5.55.5) ID EVALUATE available radiological airborne or liquid release information ID MONITOR for radiological EAL changestriggers AND if necessary, IMMEDIATELY RECOMMEND potential classification changes to ED IF conditions for an Alert or GE is approaching or declared OR a concurrent EAL at Alert or GE level is identified, all based on radiological conditions, PROVIDE release and dose assessment information to Operations Coordinator for SM evaluation of a potential entry in EO-000-105. IF ED declares a change in classification level, COMMUNICATE information to DEP/BRPINFORM TSC E-Plan Communicator OR ED of appropriate met tower (10 OR 60 m) to use for wind direction and speed on the ENR AND COMMUNICATE classification change to DEP/BRP. Onsite Protective Actions (Section 5.6) EVALUATE radiological status of plant and releases FORM EP-PS-104-1 Rev. 11, Page 3 of 5

Enclosure 2 to PLA-8077, Page 235 of 560 RADIATION PROTECTION COORDINATOR Attachment A EP-PS-104 Revision: 44 Page 51 of 54 Unit: 0 WHEN Site Evacuation is initiated, DISCUSS notification of occupied buildings and areas, and egress routes with TSC Security Coordinator AND ED AND ENSURE affected staff is notified EVALUATE AND RECOMMEND changes in protective action for SSES personnel IF vehicles OR personnel are suspected to be contaminated, DETERMINE which remote assembly area(s) to be used IF TSC is in control of the emergency, ENSURE FMTs are maintaining their exposure ALARA, and EVALUATE OSCAR risk IF exposure rateFMT ED exceeds 800 mR/h400 rem OR Cartridge Readings are greater than 7,5004,000 ccpm, ENSURE TSC RadiocommunicatorRP Radio Communicator initiated FMT exposure control. IF Adult Thyroid CDE is determined to be potentially greater than 10 rem, OBTAIN ED approval for affected personnel, DIRECT affected personnel to take KI AND ENSURE affected personnel is notified of precautions regarding interactions with other drugs FOLLOWING a Site Area Emergency (SAE) declaration AND AFTER site evacuation is complete, PREPARE for potential KI issuance for ALL personnel on site. IF a GE with release in progress is declared OR a GE is declared and release is imminent, OBTAIN ED approval for ALL onsite personnel to take KI, DIRECT ALL onsite personnel to take KI AND ENSURE personnel is notified to take KI AND on other required precautions IF assistance with KI issuance is required, CONTACT Consulting Radiological Physician IF necessary, ENSURE changes to Emergency RWPs are implemented Upon recommendation from OSC RP Specialist or TSC Radiocommunciator, if TSC is in control, IF estimated personnel doses are greater than 4 rem TEDE and 50 rem thyroid CDE, PROCESS AND OBTAIN ED approval for SSES personnel emergency exposure extensions RESPOND to requests from EOF staff for occupational exposure control information. ID DIRECT OSC RP Specialist or TSC RadiocommunicatorRP Radio Communication to ensure bioassay for exposed field team members is performed, if necessary Support for Off Site Protective Actions Recommendations, it TSC is in control (Section 5.75.7) OBTAIN data needed to assess magnitude AND anticipated duration of offsite releases WHENFOLLOWING a GE is declareddeclaration, RECOMMEND initial PAR to ED AND PROVIDE radiological input required to determine appropriate PAR, if necessaryincluding release height (10 OR 60 m met tower) FORM EP-PS-104-1 Rev. 11, Page 4 of 5

Enclosure 2 to PLA-8077, Page 236 of 560 RADIATION PROTECTION COORDINATOR Attachment A EP-PS-104 Revision: 44 Page 52 of 54 Unit: 0 WHENAFTER ED declares a PAR due to an airborne release OR a PAR change, COMMUNICATE information to PA DEP/BRP EVALUATE if an airborne releases PAR beyond 10 miles is appropriate DIRECT staff to identify affected sectors IF PAR is based on a Back Calculation AND an Air Sample is not provided, ENSURE calculation is redone and an air sample results is includedDIRECT FTD to obtain data at the plume edge, including air samples CONSULT with DA staff, Engineering, Operations, ED AND State representatives for PAR issuance and verification of dose projections AND, IF required, RECOMMEND appropriate PAR to ED CONTINUE to evaluate for PAR changes AND RECOMMEND revising airborne release PARs based on increasing dose levels or wind shifts AND INFORM ED if release height (10 OR 60 m met tower) changes in dose calculation. IF liquid releases are identified, DETERMINE liquid PAR AND NOTIFY ED of potential liquid PAR, if necessary IF ED declares a liquid PAR, COMMUNICATE PAR to DEP/BRP and NRCENSURE the liquid PAR is checked AND appropriate met tower wind speed and direction are entered on the ENR form COMMUNICATE liquid PAR to DEP/BRP AND NRC FORM EP-PS-104-1 Rev. 11, Page 5 of 5

Enclosure 2 to PLA-8077, Page 237 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 4 of 28 Unit: 0 1.0 PURPOSE AND SCOPE 1.1 Purpose 1.1.1 This procedure describes actions to be taken by the Technical Support Center (TSC) Dose Calculator during an event at Susquehanna Steam Electric Station (SSES). 1.2 Scope 1.2.1 This procedure is used by TSC Dose Calculator upon arriving at TSC until the termination of the emergency event or until relieved by another TSC Dose Calculator. 1.2.2 Step 5.6, Facility Turnover may be completed at any time during the implementation of this procedure. 1.2.3 Attachment A, TSC Dose Calculator Hard Card, may be used to perform placekeeping for reference-use sections in this procedure. It is laminated and therefore, it may be used to handle placekeeping of cyclic activities or placekeeping in the situation the TSC Dose Calculator is in different reference-use sections of procedure at the same time. 1.2.4 This procedure ensures that SSES commitments delineated in Emergency Plan Sections 6 and 7, and regulatory requirements 10CFR50.47(b) and Appendix E are fulfilled. 1.2.5 Expectation is to complete procedure steps in a way that ensures continuous operation during time critical evolutions during emergencies or drills.

2.0 REFERENCES

AND COMMITMENTS 2.1 Performance References 2.1.1 EP-PS-001, Emergency Planning Forms and Supplementary Instructions 2.1.2 EP-RM-004, EAL Classification Bases 2.1.3 EP-RM-005009, SSES MIDAS-NUURI User Manual 2.2 Developmental References 2.2.1 SSES Emergency Plan 2.2.2 EP-PS-134, TSC Radiation Protection Radio Communicator 2.2.3 NUREG 0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2.2.4 NEP Technical Basis #02-004 - Total Noble Gas to Iodine 131 and Total Noble Gas to Total Particulate Ratios for Use in MIDAS Evaluations Supporting SSES Emergency Plan

Enclosure 2 to PLA-8077, Page 238 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 5 of 28 Unit: 0 2.2.52.2.4 NEP Technical Basis #02-005 - Noble Gas Release Rate Limits for EALs 2.2.62.2.5 NEP Technical Basis #03-001 - Measured to Projected Ratio 2.2.7 NEP Technical Basis #04-001 - Start of Radiological Release 2.2.82.2.6 NEP Technical Basis #04-003 - Classification of Dose During a Declared Emergency 2.2.7 NEP Technical Basis #04-004 - Rationale for Selection of Release Duration for Dose Assessments for Selected, Common Plant Conditions 2.2.8 NEP Technical Basis 16-001 - Frisker Response in Support of EAL Implementation and Determination of Release In Progress 2.2.9 NEP Technical Basis 23-001 - Unified RASCAL Interface Technical Design Description Version 3.7 2.2.10 NEP Technical Basis 23-002 - Unified RASCAL Interface Requirements Specification, Susquehanna Site Annex Version 3.7 2.2.92.2.11 EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-400-R-92-001 May 1992) 2.2.102.2.12 IE Notice 83-28 2.2.112.2.13 NCRP Report 55, Protection of the Thyroid Gland in the Event of Releases of Radioiodine, National Council Radiation Protection and Measurements. (1977) 2.2.122.2.14 NCRP Report 91, Recommendations on Limits for Exposure to Ionizing Radiation, National Council on Radiation Protection and Measurements. (1987) 2.2.132.2.15 NCRP Report 116, "Limitation of Exposure to Ionizing Radiation, National Council on Radiation Protection and Measurements." (1993) 2.2.142.2.16 NUMARC Graded Response Study 2.2.152.2.17 Radiological Assessment Reference Book 2.2.162.2.18 NDAP-QA-0620, Conduct of Radiation Protection 2.2.172.2.19 NDAP-QA-1191, ALARA Program and Policy 2.2.182.2.20 CH-RM-001, Conduct of Radiological Environmental Monitoring Program 2.2.192.2.21 BRP Technical Assessment of Protective Actions, Appendix 6, Annex E 2.2.202.2.22 Guidance Potassium Iodide as a Thyroid Blocking Agent in Radiation Emergencies, HHS/FDA, December 2001. 2.2.21 EC-RADN-1002 - SSES Plant Specific Input for the MIDAS Computer Program.

Enclosure 2 to PLA-8077, Page 239 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 6 of 28 Unit: 0 2.2.22 SQAP MIDAS-NU. 2.3 Commitments 2.3.1 None 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions 3.1.1 None 3.2 Limitations 3.2.1 None 4.0 PREREQUISITES AND INITIAL CONDITIONS 4.1 Prerequisites 4.1.1 IF relieving an on-shift TSC Dose Calculator, THEN OBTAIN a shift turnover from the current TSC Dose Calculator using shift turnover process described in Step 5.6. 4.2 Initial Conditions x An Emergency Plan entry has been declared x Facility has been precautionary staffed x An emergency tabletop, drill OR exercise

Enclosure 2 to PLA-8077, Page 240 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 7 of 28 Unit: 0 5.0 INSTRUCTIONS 5.1 Initial Actions (INFORMATION USE) 5.1.1 SIGN IN on TSC Access Log. 5.1.2 SIGN IN on TSC On Duty Personnel Board. 5.1.3 NOTIFY the Radiation Protection Coordinator (RPC) of arrival. 5.1.4 DETERMINE status of MIDASURI program, printer AND Plant System Server (PSS) equipment.

a. ALIGN MIDASURI computer time with the R*Time time, if necessary.

b. IF equipment is NOT functional, THEN NOTIFY RPC.

NOTE A backup laptop computer with the MIDAS program is located in the cabinet at the TSC Dose Calculator desk below the MIDAS desk top computer.

c. In the event of Loss of AC power in TSC, CONTACT Technical Support Coordinator to determine UPS-powered outlets OR USE backupto use with the URI computer with MIDAS program.

5.1.5 OBTAIN copies of the following forms/instructions from EP-PS-001, Emergency Planning Forms and Supplementary Instructions: x Dose Assessment Data Gathering Form x Field Team Monitoring Strategy Notes x Field to Projection Measurement Comparison x Logkeeping Instructions and Paper Log Form x Meteorological Data Acquisition Options x MIDAS Field to Projection Measurement Comparison x NUREG 1228 Event Tree Parameters for Dose Assessment x Protective Action Recommendation Determination (White board in RP/ED area) x Radiological Dose Assessment Phone Log x Radiological Release Duration Guidance

Enclosure 2 to PLA-8077, Page 241 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 8 of 28 Unit: 0 x Radiological Release in Progress Guidance (white board in RP/ED area) x Status of Dose Calculations (White board in RP area) x TSC/EOF Dose Assessment Flowchart (White board in RP area) x Vent Monitor Data Acquisition 5.1.6 OBTAIN a copy of EP-RM-005, SSES MIDAS-NU User Manual.

a. VERIFY that MIDAS Hard Cards are available in working area.

(1) IF MIDAS Hard cards are not available, THEN OBTAIN copies OR USE MIDAS Hard cards in SSES MIDAS User Manual

Enclosure 2 to PLA-8077, Page 242 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 9 of 28 Unit: 0 5.1.75.1.6 USE RP II Technician on shift (RP II Dose Calculator) as a TSC RadiocommunicatorRP Radio Communicator.

a. IF RP II Dose Calculator was reassigned during the shift, THEN REQUEST for another RP technician to fulfill the role of the TSC RP Radio Communicator from RPC.

5.1.85.1.7 INITIATE a chronological event log using the Logkeeping Instructions and Paper Log Form in EP-PS-001. 5.1.95.1.8 OBTAIN a briefing from Radiation Protection Coordinator (RPC) OR RP II Dose Calculator including the following: x Emergency classification x Release in progress declaration status x Dose Calculations completed x Affected sector(s) x OSCAR status x Field Monitoring Team status 5.1.10 REVIEW instructions in Status of Dose Calculation and Section N in EP-RM-005.

Enclosure 2 to PLA-8077, Page 243 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 10 of 28 Unit: 0 5.1.9 With RPC, RP II Technician, TSC Ops Coordinator OR Engineering, FILL IN the Dose Assessment Data Gathering Form in preparation for dose assessment.

Enclosure 2 to PLA-8077, Page 244 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 12 of 28 Unit: 0 5.2.1.b (continued) (3) OBTAIN Chemistry vent sample data as often as possible (CH-ON-003, CH-ON-007, or CH-TP-016).) AND DISCUSS alternate methods to obtain release data (e.g., HP air samples) (4) USE alternate data such as grab sample (vent) results in Forward Calculation. (a) USE vent sample data to verify previous URI dose assessment calculation PER TSC/EOF Dose Assessment Flowchart in EP-PS-001 (4) DIRECT TSC RP Radio Communicator to take air samples (especially OSCAR) as often as possible. (5) IF vent data for the respective pathway is still NOT available, THEN USE alternate URI methods (other than Monitored and Field Team) to complete required calculations PER the TSC/EOF Dose Assessment Flowchart in EP-PS-001. (6) IF meteorological data is NOT reliable, THEN USE alternate meteorological data PER Meteorological Data Acquisition Options in EP-PS-001, if necessary. 5.2.2 MONITOR available plant data for changes indicative of a radiological release AND CHARACTERIZE release PER Radiological Release in Progress Guidance, TSC/EOF Dose Assessment Flowchart AND Meteorological Data Acquisition Options in EP-PS-001.

a. IF a Release in Progress is declared, THEN (1) CONTACT NSSS Engineer OR Technical Support Coordinator AND OBTAIN a copy of the Engineering Dose Assessment Support Information Worksheet, (2)(1) IF criteria for Airborne Release in progress due to an Event below TRM Values PER Note 41 in TSC/EOF Dose Assessment Flowchart in EP-PS-001 are met, THEN REFER to Step 5.3 AND COMPLETE at least one MIDAS dose calculation.

(3)(2) IF criteria for Airborne Release in Progress above TRM Values PER Note 41 of TSC/EOF Dose Assessment Flowchart in EP-PS-001 are met, OR

Enclosure 2 to PLA-8077, Page 245 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 13 of 28 Unit: 0 IF General Emergency is declared, THEN REFER to Step 5.3 AND COMPLETE a MIDAS-NUvalid dose calculationscalculation every 15 minutes. 5.2.3 MAINTAIN a chronological event log using the Logkeeping Instructions and Paper Log Form in EP-PS-001. NOTE x Sub-steps in Step 5.3 are cyclic when a Release in Progress is declared AND release is greater than TRM limits or a General Emergency is declared. Some steps may be performed out of sequence or skipped under a 15-minute time constraint. x Placekeeping in Section 5.3 may be performed on Attachment A, TSC Dose Calculator Hard Card. 5.3 Dose Calculations (REFERENCE USE) DETERMINE applicable pathway AND magnitude scaling method to perform a valid dose assessmentNOTE A Forward calculation is the preferred choice for valid calculations unless the release is unmonitored, there are multiple sources (use Multiple Menu), OR a back calculation provides more conservative results: 5.3.1 REFER TOfor current plant conditions PER TSC/EOF Dose Assessment Flowchart in EP-PS-001 AND Engineering Dose Assessment Support Information Worksheet provided by Engineering to determine type of valid calculation to perform for current plant conditions.

a. IF type of calculation necessary is unclear, THEN CONSULT with RPC to verify selection of MIDAS accident type

b. IF a NUREG-1228 menu calculation is identified as a valid calculation, THEN prior to performing the calculation, COMPLETE the NUREG 1228 Event Tree Parameters for Dose Assessment form in EP-PS-001 with Engineering.

c. IF directed by RPC or Engineering to perform dose assessment for direct, controlled containment venting, THEN USE EP-RM-005, SSES MIDAS-NU User ManualURI pathway AND Engineering input to perform these calculationsscaling method.

d.b. IF supplementary information to perform MIDAS dose assessment calculation is necessary, THEN

Enclosure 2 to PLA-8077, Page 246 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 14 of 28 Unit: 0 (1) CONSULT RPC OR TSC Operations Coordinator OR Engineering. (2) REFER TO Meteorological Data Acquisition Options in EP-PS-001. (3) REFER TO Radiological Release Duration Guidance in EP-PS-001. (4)(3) REFER TO EP-RM-005009, SSES MIDAS-NUURI User Manual. NOTE x URI saves the dose assessment report files in pdf on C:\Dose Assessment Reports folder of the SDS computer. x S.B. line in URI report and screen is equivalent with SSES EPB. 5.3.2 PERFORM calculation identified in Step 0 PER MIDAS Hard Card Information Sheets. AND PRINT aNOTE 5.3.2 MIDAS prints one copy atof the end of Dose Assessment Report REVIEW input and calculation automatically.

a. WHEN MIDAS Dose Assessment Summary Sheet is printed, REVIEW report results for accuracy.

(1) IF MIDASURI Dose Assessment Summary SheetReport is satisfactory AND no input data errors are identified, THEN RECORD signature AND time the calculation was completed on MIDAS Dose Assessment Summary Sheet as OriginatorReport above the Review By field.

Enclosure 2 to PLA-8077, Page 247 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 15 of 28 Unit: 0 5.3.2.a (continued) (2) IF MIDASURI Dose Assessment Report is unsatisfactory OR data input errors are identified, THEN REDO Step 5.3.21.1.1 with correct data inputs as applicable. 5.3.3 ASK RPC to review input and calculation results for accuracy AND RECORD Reviewer/ Approver name, signature AND time review was completed on MIDAS Dose Assessment Summary Sheet AND time Report in the Review was completedBy Field. NOTE x Trending may involve evaluating the rate of change of measured data. For example, what is the rise or fall in CHRM exposure rates for a given unit of time (15 min, 30 min, etc.) x Radiological Emergency Classification triggers include ARM data in Table R, entry conditions in rows B and D in Table F AND in CG1.1, CG1.2, EU1.1, SU4.1 and SU4.2 EALs 5.3.4 IF triggers for radiological emergency classification or PAR changes PER EP-RM-004 OR Protective Action Recommendation Determination Flowchart in EP-PS-001 are indicated, THEN

a. IMMEDIATELY NOTIFY RPC.

b. WHEN evaluating radiological data, THEN DETERMINE rate of change (trending), if possible, to assist with determining when an EAL upgrade (OR downgrade) may occur.

5.3.5 IF Emergency Planning Boundary (EPB) projected doses are greater than 1,000 mrem Total Effective Dose Equivalent (TEDE) OR greater than 5,000 mrem Child Thyroid Committed Dose Equivalent (CDE), THEN in accordance with Protective Action Recommendation Determination in EP-PS-001, DISCUSS affected areas, initial PARs AND potential PAR changes with RPC.

a. INFORM RPC on the wind direction (10 OR 60 m met tower) used in dose assessment calculations.

a. WHEN evaluating radiological data, THEN DETERMINE rate of change (trending), if possible, to assist with determining when an EAL upgrade (OR downgrade) may occur.

Enclosure 2 to PLA-8077, Page 248 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 16 of 28 Unit: 0 NOTE x Based on data availability Step 5.3.6 may not be able to be completed within 15 minutes. x When such data is available, PARs beyond 10-mile EPZ should be based on vent sample OR verified field data calculations. x Integrated Dose data is provided in table form out to approximately 8550 miles when a 50 mile assessment is executed. 5.3.6 IF 1,000 mrem TEDE OR 5,000 mrem Child Thyroid CDE is exceeded at or beyond 10 miles in a 10-mile assessment, THEN RUN a 50 mile assessment AND PROVIDE distance and affected sectors these thresholds are exceeded to RPC from MIDASthe Dose Assessment Summary Report. NOTE x FMT data from beyond 10-mile cannot be used in the Field Team (back) calculation method. x A 50 mile assessment does not include a Field Team calculation method.

a. IF dose assessmentPAR is based on a Back Calculationvalid 10 mile dose assessment that used a Field Team method AND an Air Sample is NOT provided, THEN (1) DIRECT RP Radio Communicator to obtain an air sample (2) REDO dose assessment

b. DISCUSS PAR beyond 10-mile EPZ with RPC, Engineering, Operations, ED AND State representatives, considering at least the following:

x Model uncertainty x Wind shifts x Methodology uncertainty with distance x Release characteristics x Plant status x Placement of FMT x Field data x Reanalysis of questionable data

Enclosure 2 to PLA-8077, Page 249 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 17 of 28 Unit: 0 5.3.7 CONSIDER verification of dose assessment results by comparing field to calculated EDE projected exposure rate AND Child Thyroid CDE dose rate ratios using MIDAS Field to Projection Measurement Comparison in EP-PS-001 OR by performing calculations using Field Team (back) method (if necessary) OR study case calculations. 5.3.8 PREPARE Dose Assessment Package containing the following for each MIDAS calculation performed:

a. ATTACH the signed MIDAS Dose Assessment Summary SheetReport.

b. ATTACH Engineering Dose Assessment Support Information Worksheet provided by Engineering OR NUREG 1228 Event Tree Parameters for Dose Assessment forms, if applicable.

c.b. IF measured to projected dose rate evaluation was performed PER Field to Projection Measurement Comparison, THEN ATTACH results of measured to projected dose rate evaluation. (1) IF backField Team method was used as a valid calculation was performed, THEN ATTACH Field TeamFMT data sheets as provided by the TSC RP RadiocommunicatorRadio Communicator. NOTE x URI saves the dose assessment results files (URI7) on both C:\Dose Assessment Results Files (locally) as well as in Y:\URI\Dose Assessment Results Files (network) drive of the SDS computer. These files can be used in any facility in URI Summation mode. x URI saves the dose assessment reports files (pdf) only locally on C:\Dose Assessment Reports of the SDS computer.

a. IF network drive is available in both TSC and EOF, THEN (1) MAKE OR ASK TSC Administrative Coordinator to make, 1 copy of the Dose Assessment Package.

(2) COPY the dose assessment report (pdf file) on the network drive in the Y:\URI\Dose Assessment Reports folder of the SDS computer.

b. IF network drive is NOT available in EOF, THEN MAKE OR ASK TSC Administrative Coordinator to make, 2 copies of the Dose Assessment Package AND ASK TSC Administrative Coordinator to fax the Dose Assessment Package to the EOF.

Enclosure 2 to PLA-8077, Page 250 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 18 of 28 Unit: 0

c. INFORM EOF that a new calculation was performed and is available for review via the network OR fax, as applicable.

Enclosure 2 to PLA-8077, Page 251 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 19 of 28 Unit: 0 5.3.9 PROVIDE one copy of the Dose Assessment Package to RPC with verbal explanation on summary of results

a. RETAIN one copy of Dose Assessment Summary Package for own records.

5.3.10 MAINTAIN status board for completed dose calculations PER Status of Dose Calculations form and instructions in EP-PS-001. 5.3.11 CONSIDER updating the Dose Assessment Data Gathering Form whenever plant information changes. 5.3.115.3.12 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001. 5.3.125.3.13 IF under a 15-minute time clock, THEN RETURN to Step 0 for entire plume (early) phase. OTHERWISE CONTINUE monitoring per Step 5.2.

Enclosure 2 to PLA-8077, Page 252 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 20 of 28 Unit: 0 5.4 OSCAR and Field Monitoring Team (REFERENCE USE) 5.4.1 EVALUATE the following to determine if any changes to plume dose rates would result: x Wind changes x Plume width (sectors) AND centerline x Impact of stability class x Impact of precipitation, that is, impact of rainout / washout x Impact of future weather forecast (for example, stability, precipitation) x Impact on site evacuation x Changes in ventilation lineups (for example, realignment, operation) x Hold up for decay rather than direct venting to environment

a. REPORT assessment results to RPC.

5.4.2 USEUSE TSC RP Radio Communicator AND guidance in Field Team Monitoring Strategy Notes in EP-PS-001 AND TSC Radiocommunicator to dispatch AND direct OSCAR AND ALPHA Field Monitoring Team (FMT) per EP-PS-134 procedure.

a. IF time allows, THEN NOTE Field Monitoring teams ALPHA and BRAVO are not qualified to use respiratory protection.

(1) ENSURE exposure of FMT personnel is maintained ALARA. (a) ENSURE FMTs perform calculations OR sample analysis in background area (b) WHEN Emergency Monitoring teams are NOT being used, THEN ENSURE FMTs wait in a low dose rate OR background area

Enclosure 2 to PLA-8077, Page 253 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 22 of 28 Unit: 0 5.4.2.a (continued) (3) IF one the following conditions are met: x Adult Thyroid CDE rate is greater than 1,000 mrem/hr (7,5004,000 ccpm frisker) for a team OR x Valid Thyroid CDE dose rate projection is greater than 1,000 mrem/hr at a Field Monitoring Team location AND measured Thyroid CDE rate data is not available at that location x FMT ED exceeds 400 mrem THEN ENSURE TSC RP Radio Communicator is tracking FMT Thyroid CDE. (4) IF adult thyroid CDE is determined to be potentially greater than 10,000 mrem OR a General Emergency with release in progress is declared OR a General Emergency is declared and the release is imminent, THEN, with RPC, FACILITATE approval of Potassium Iodide (KI) Tracking form in EP-PS-001 initiated by the TSC RadiocommunicatorRP Radio Communicator (5) ASSIST TSC RadiocommunicatorRP Radio Communicator OR RPC with the FMT turnover. (6) ASSIST TSC RadiocommunicatorRadio Communicator OR RPC with the FMT decontamination. (7) IF necessary, THEN (a) ASSIST TSC RadiocommunicatorRP Radio Communicator OR RPC to reviewrevise RWP 8001 instructions regarding OSCAR activities. (b) ASSIST TSC RadiocommunicatorRP Radio Communicator OR RPC to reviewrevise RWP 8002 instructions regarding offsite A FMT activities. 5.4.3 MAINTAIN a chronological event log PER Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 254 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 23 of 28 Unit: 0 5.5 Facility Turnover (INFORMATION USE) NOTE An updated Dose Assessment Data Gathering Form can be used as an aid for the turnover. 5.5.1 WHEN contacted by EOF Dose Assessment Staffer (DAST), THEN PROVIDE the following: x Dose Assessment status x Dose Assessment Summary Packages x Vent stack monitor data 5.5.2 IF unable to transmit Dose Assessment Summary Packages, THEN PROVIDE information to EOF on Radiological Dose Assessment Phone Log in EP-PS-001. 5.5.35.5.2 NOTIFY RPC when EOF is ready for turnover. 5.5.45.5.3 WHEN EOF assumes control of emergency, THEN TRANSFER responsibility for dose calculations to EOF. 5.5.55.5.4 SUPPORT RPC with radiological assessment for onsite personnel OR PERFORM dose assessment as peer-check for EOF. 5.6 Shift Turnover (INFORMATION USE) 5.6.1 REMAIN at duty station with full responsibility until properly relieved. 5.6.2 PROVIDE a briefing to Using an updated Dose Assessment Data Gathering Form in EP-PS-001, BRIEF the on-coming TSC Dose Calculator including the following: x Current emergency situationstatus x Calculations completed x Equipment status x Dose calculations performed AND pathways and scaling method used in the calculation.

Enclosure 2 to PLA-8077, Page 255 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 24 of 28 Unit: 0 5.7 Event Termination (INFORMATION USE) 5.7.1 REQUEST Computer Engineering to provide URI input / output data to NEP Department. 5.7.15.7.2 RETURN work area to a ready condition. 5.7.25.7.3 PARTICIPATE in emergency event debriefing. 5.7.35.7.4 FORWARD forms, logs, data, AND other documentation to: x TSC Administrative Coordinator OR x A Drill controller END of Instructions

Enclosure 2 to PLA-8077, Page 256 of 560 TSC DOSE CALCULATOR EP-PS-105 Revision: 33 Page 25 of 28 Unit: 0 6.0 RECORDS x ALL MIDASURI runs x ALL MIDAS Dose Assessment Summary SheetsReports generated x All Engineering Dose Assessment Support Information Worksheets received from Engineering x All NUREG 1228 Event Tree Parameters for Dose Assessment forms x ALL Field Team Data Sheets received from Field Teams x ALL measuredField to Projection dose rate evaluationsMeasurement Comparison Forms x Status of Dose Calculation x Logs, data and documented communications generated.

Enclosure 2 to PLA-8077, Page 257 of 560 TSC DOSE CALCULATOR Attachment A EP-PS-105 Revision: 33 Page 26 of 28 Unit: 0 Attachment A, TSC Dose Calculator Hard Card MAINTAIN a chronological event log for activities in this procedure including: Plant Data Review (Section 5.2) EVALUATE PSS vent release rate AND meteorological data IF low confidence (white) PSS data exist, CONTACT Engineering to decide if plant vent monitors can be used AND FIND alternative means to obtain vent and meteorological data. MONITOR available plant data for changes that may be indicative of a radiological release AND CHARACTERIZE release IF release in progress is declared, CONTACT Engineering AND OBTAIN Engineering Dose Assessment Support Information Worksheet PERFORM at least one dose assessment IF site totals exceed TRM limits or GE is declared, PERFORM dose calculations every 15 minutes Dose Calculations (Section 5.3) DETERMINE type of MIDASPathway AND magnitude scaling method to use in calculation to perform for current plant conditions. PERFORM appropriate Dose Assessment calculation AND PRINT a copy of the Dose Assessment Report REVIEW input and calculation results AND RECORD signature AND time review was completed ASK RPC to review, sign AND record the time the calculation was reviewed IF radiological emergency classification AND PARs changestriggers are requiredmet, IMMEDIATELY NOTIFY RPC AND DETERMINE trends, if possible. IF 1000 mrem TEDE OR 5000 mrem child Thyroid CDE is exceeded at EPB, PROVIDE distance and affected sectors to RPC AND INFORM RPC on the wind direction used (10 OR 60 m met tower) in calculation. IF 1000 mrem TEDE OR 5000 mrem child Thyroid CDE is exceeded at 10 miles, RUN a 50 mile assessment AND PROVIDE distance and affected sectors to RPC. CONSIDER verification of dose assessment results by comparing field to calculated EDE AND CDE dose rate ratios or performing back (if necessary) or study case calculations. FORM EP-PS-105-1 Rev. 8, Page 1 of 3

Enclosure 2 to PLA-8077, Page 258 of 560 TSC DOSE CALCULATOR Attachment A EP-PS-105 Revision: 33 Page 27 of 28 Unit: 0 PREPARE Dose Assessment Package, DISCUSS it with RPC, INFORM EOF a new calculation is available for review or send the new calculation to EOF, as applicable, AND UPDATE Dose Assessment Status Board PERFORM another Dose Assessment calculation OR RETURN to Plant Data Review FORM EP-PS-105-1 Rev. 8, Page 2 of 3

Enclosure 2 to PLA-8077, Page 259 of 560 TSC DOSE CALCULATOR Attachment A EP-PS-105 Revision: 33 Page 28 of 28 Unit: 0 OSCAR and Field Monitoring Team (Section 5.4) PERFORM plume assessment AND REPORT assessment results to RPC ID ENSURE TSC RP RadiocommunicatorRadio Communicator dispatches AND directs OSCAR and ALPHA FMT IF time allows, ENSURE exposure of FMTs is maintained ALARA ENSURE teams are performing calculations OR sample analysis in background area ENSURE teams are waiting in a low dose area IF FMT reports exposure rates / air sample cartridge readings exceed limits in Field Measurement Guidelines Table, IMMEDIATELY INFORM RPC If necessary, ENSURE TSC RadiocommunicatorRP Radio Communicator is tracking FMT TEDE AND Thyroid CDE If necessary, FACILITATE approval of Potassium Iodide (KI) Tracking form ASSIST with the FMT turnover. ASSIST with the FMT decontamination. 1 If necessary, ASSIST in reviewingrevising RWP 8001 andOR 8002 instructions FORM EP-PS-105-1 Rev. 8, Page 3 of 3

Enclosure 2 to PLA-8077, Page 260 of 560 RP TECH I (OSCAR) EP-PS-108 Revision: 28 Page 8 of 22 Unit: 0 NOTE OSCAR van is usually located outside protected area. Sometimes, however, the van can also be located inside the protected area. 5.2.4 PROCEED to OSCAR Van AND PERFORM van and equipment checks per Attachment B, OSCAR Survey Techniques. 5.2.5 INITIATE a chronological event log of activities performed on the paper form in Logkeeping Instructions and Paper Log Form in EP-PS-001. 5.3 Field Monitoring (Reference Use) 5.3.1 WHEN directed by RP Radio Communicator or Field Team Director, THEN INITIATE radiological monitoring using Attachment B, OSCAR Survey Techniques.

a. IF exposure ratesED reading approach 800 mR/hr400 mrem, THEN:

(1) MOVE to a low dose area. (2) NOTIFY RP Radio Communicator or Field Team Director to start dose tracking activities. NOTE Air sampling pumps pre-staged within OSCAR are calibrated in cubic-feet (ft 3) per minute

b. IF Net count rate of a silver zeolite cartridge is equal to or greater than 7,5004,000 ccpm (based on an air sample volume of 20 ft3),

THEN NOTIFY RP Radio Communicator or Field Team Director to start dose tracking for thyroid CDE.

Enclosure 2 to PLA-8077, Page 261 of 560 RP TECH I (OSCAR) Attachment A EP-PS-108 Revision: 28 Page 13 of 22 Unit: 0 Attachment A, RP Tech I (OSCAR) Hard Card D MAINTAIN a chronological event log of activities performed in this procedure including Field Monitoring (Section 5.3) D WHEN directed by RP Radio Communicator or FTD, INITIATE radiological monitoring. ID IF exposure ratesED reading approach 800 mR/hr400 mrem, MOVE to a low dose area AND NOTIFY RP Radio Communicator or FTD to start dose tracking. ID IF Net count rate of a silver zeolite cartridge is equal to or greater than 7,5004,000 ccpm (based on an air sample volume of 20 ft 3), NOTIFY RP Radio Communicator or FTD to start dose tracking for thyroid CDE D IF directed to take KI, either D INFORM them of any medical restrictions for taking KI OR D TAKE KI AND ASK them to document your KI usage D -- REQUEST approval to move further from site AND/OR USE respiratory protection, prior to entering the plume D Immediately REPORT to RP Radio Communicator or FTD: D x Significant radiological changes D x Fires D x Lightning strikes D x Rain or snow D x Damage to buildings D x Steam or smoke plumes FORM EP-PS-108-1 Rev. 5, Page 1 of 1

Enclosure 2 to PLA-8077, Page 262 of 560 RP TECH I (OSCAR) Attachment B EP-PS-108 Revision: 28 Page 22 of 22 Unit: 0 Attachment B, OSCAR Survey Techniques, Continued

6. COUNT the activity on the silver zeolite cartridge and the particulate filter.

a. HOLD the frisker probe in contact with the bagged silver zeolite cartridge.

b. HOLD the frisker probe in contact with the bagged particulate filter.

7. AFTER counting, PLACE the bagged particulate filter paper (small bag #1) and the bagged silver zeolite cartridge (small bag #2) into separate larger plastic bags for possible future analysis.

a. ENSURE that Radioactive Material tape is used to properly identify the contents of all sample bags.

b. IF Net count rate of a silver zeolite cartridge is equal to or greater than 7,5004,000 ccpm (based on an air sample volume of 20 ft 3),

THEN NOTIFY RP Radio Communicator or Field Team Director to start dose tracking for thyroid CDE.

8. COMPLETE Survey Data Form in EP-PS-001 AND ATTACH Sample Tag to the back of Survey Data Form

a. COMMUNICATE Survey Data Form information to TSC / EOF

9. RELOAD air sampler with a new 47 mm particulate filter and new silver zeolite cartridge to support future sampling.

a. ATACH air sample head to Portable Air Sampler.

(1) PROTECT loaded air sample head (using a bag, tape, or glove) until needed. F. System Shut Down

1. TURN OFF vehicle.

2. SET parking brake.

3. ENSURE that all interior and emergency lights have been turned off.

4. PLUG vehicle into a dependable power source.

5. SECURE vehicle Page 9 of 9

Enclosure 2 to PLA-8077, Page 263 of 560 RP II DOSE CALCULATOR EP-PS-130 Revision: 38 Page 4 of 23 Unit: 0 1.0 PURPOSE AND SCOPE 1.1 Purpose 1.1.1 This procedure describes actions to be taken by the RP II Dose Calculator during an event at Susquehanna Steam Electric Station (SSES). 1.2 Scope 1.2.1 RP II Dose Calculator reports to Shift Manager until Technical Support Center (TSC) is activated then to the TSC Dose Calculator or RPC after TSC is activated. 1.2.2 Attachment A, RP II Dose Calculator Hard Card, may be used to perform placekeeping for reference-use sections in this procedure. It is laminated and therefore, it may be used to handle placekeeping of cyclic activities or placekeeping in the situation the RP II Dose Calculator is in different reference-use sections of procedure at the same time. 1.2.3 This procedure ensures that SSES commitments delineated in SSES Emergency Plan Sections 6 and 7 and regulatory requirements 10CFR50.47 and Appendix E are fulfilled. 1.2.4 Expectation is to complete procedure steps in a way that ensures continuous operation during time critical evolutions during emergencies or drills.

2.0 REFERENCES

AND COMMITMENTS 2.1 Performance References 2.1.1 EP-PS-001, Emergency Planning Forms and Supplementary Instructions 2.1.2 EP-PS-134, TSC RP Radio Communicator 2.1.3 EP-RM-004, EAL Classification Bases 2.1.4 EP-RM-005, SSES MIDAS-NU User Manual 2.2 Developmental References 2.2.1 Susquehanna Steam Electric Station (SSES) Emergency Plan 2.2.2 NUREG 0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2.2.3 NEP Technical Basis #02-004 - Total Noble Gas to Iodine-131 and Total Noble Gas to Total Particulate Ratios for Use in MIDAS Evaluations Supporting SSES Emergency Plan 2.2.42.2.3 NEP Technical Basis #02-005 - Noble Gas Release Rate Limits for EALs 2.2.52.2.4 NEP Technical Basis #03-001 - Measured to Projected Ratio

Enclosure 2 to PLA-8077, Page 264 of 560 RP II DOSE CALCULATOR EP-PS-130 Revision: 38 Page 5 of 23 Unit: 0 2.2.62.2.5 NEP Technical Basis #04-23-001 - Start of Radiological Release- Unified RASCAL Interface Technical Design Description Version 3.7 2.2.6 NEP Technical Basis 23-002 - Unified RASCAL Interface Requirements Specification, Susquehanna Site Annex Version 3.7 2.3 Commitments 2.3.1 None 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions 3.1.1 None 3.2 Limitations 3.2.1 None 4.0 PREREQUISITES AND INITIAL CONDITIONS 4.1 Prerequisites 4.1.1 IF relieving an on-shift RP II Dose Calculator, THEN OBTAIN a briefing from the current RP II Dose Calculator using shift turnover process described in Step 5.4. 4.2 Initial Conditions 4.2.1 WHEN any of the following occur, x PA announcement x Notified by phone x Directed by RP Supervision x Emergency Classification is declared THEN

a. OBTAIN the following equipment from RP Control Point:

x High Radiation Area AND Locked High Radiation Area master keys x Source checked survey meter and frisker.

b. PROCEED to Control Room AND NOTIFY Control Room personnel of arrival.

Enclosure 2 to PLA-8077, Page 265 of 560 RP II DOSE CALCULATOR EP-PS-130 Revision: 38 Page 6 of 23 Unit: 0 5.0 INSTRUCTIONS 5.1 Initial Actions (INFORMATION USE) 5.1.1 OBTAIN briefing from Shift Manager or Control Room personnel on the following: x Emergency Classification x Release in progress declaration x Cause or source of release, if applicable

a. FILL IN Dose Assessment Data Gathering Form in EP-PS-001.

5.1.2 PROCEED to TSC

a. ALIGN MIDASURI computer time with the R*Time time, if necessary

b. OBTAIN the following forms from EP-PS-001, Emergency Planning Forms and Supplementary Instructions:

x Dose Assessment Data Gathering Form (hard card in procedure) x Logkeeping Instructions and Paper Log Form x Meteorological Data Acquisition x MIDAS Field to Projection Measurement Comparison x Radiological Release Duration Guidance x Vent Monitor Data Acquisition

c. OBTAIN EP-RM-005, SSES MIDAS-NU User Manual.

(1) VERIFY that MIDAS Hard Cards are available in working area. (a) IF MIDAS Hard cards are NOT available, THEN USE MIDAS Hard Cards in SSES MIDAS User Manual. 5.1.3 INITIATE a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 266 of 560 RP II DOSE CALCULATOR EP-PS-130 Revision: 38 Page 7 of 23 Unit: 0 5.2 Dose Assessment Calculations (REFERENCE USE) NOTE x The 10 meter OR 60 m Met Tower Wind Speed, Wind Direction, Delta T (Stability Class) and precipitation rate are necessary for MIDASURI inputs and field monitoring team direction. x PSS displays provide information regarding various plant parameters. If PSS data turns to a white color, that information may be suspect OR invalid AND other sources of data should be sought. x White data may be normal and acceptable due to low OR no system flow in the vent stack monitor (Ex. If SBGT is operating, the affected RB vent release data becomes white due to no flow) OR may indicate a release exceeding the range of the instrument OR an indication of instrumentation OR computer interface problems. x Another source of data that may be available is SPDS data display via PSS SPDS Menu. It should be noted that not all PSS data points are available on SPDS. However, for those parameters that are available on both SPDS AND PSS, SPDS may provide alternate source of required information. x If all PSS data sources become unavailable, i.e. both PSS AND SPDS data displays turn to a white color, additional alternate data sources should be sought such as data availability via hard wired OR independent data sources in control room OR locally in the plant. x White vent data should be considered as a potential unmonitored release condition unless Operations OR Engineering indicates otherwise. 5.2.1 IF Plant System Server (PSS or R*time) meteorological OR vent release rate data is questionable (white), THEN

a. With Operations OR RPC OR Engineering, DETERMINE if condition is normal (i.e., per design).

b. REFER TO the following for further instructions on obtaining alternate data:

x Meteorological Data Acquisition in EP-PS-001 x Attachment B, RP II Dose Assessment Flowchart (whiteboard in TSC RP area and hard card in procedure) x Vent Monitor Data Acquisition in EP-PS-001.

Enclosure 2 to PLA-8077, Page 267 of 560 RP II DOSE CALCULATOR EP-PS-130 Revision: 38 Page 8 of 23 Unit: 0 5.2.1 (continued)

c. IF valid vent data isFor unmonitored release pathways, USE available in Control Room, as communicated by Operations data AND in accordance with Vent Monitor Data Acquisition in EP-PS-001, THEN TAKE this procedure, the necessary forms AND the laptop computer, LEAVE a note of your whereabouts on the MIDAS computer keyboard AND GO TO control room (CR)alternate scaling methods in URI to perform dose calculation using VERMS and meteorological panel displays.

(1) ASK permission from the Emergency Director (ED) - CR on where to plug in the MIDAS laptop, preferably as close to the VERMS and Meteorological panel displaysassessment calculations PER Attachment B, RP II Dose Assessment Flowchart. d.c. ENSURE OSCAR is dispatched AND is taking air samples. e.d. USE alternate data such as grab sample (vent, (CH-ON-003, CH-ON-007 and CH-TP-016) results in dose assessment calculation to check on results from step 5.2.1.b. 5.2.2 With ED-CR OR RPC and using Radiological Release Duration Guidance in EP-PS-001, DISCUSS x Projection time. x Duration AND type of release (monitored OR unmonitored) Release pathways AND magnitude scaling methodsNOTE 5.2.35.2.2 Default NG/I-131 ratio of 1000 and default NG/Particulates ratio of 10,000 should be used until Chemistry provides different iodine and particulate vent datato perform URI calculations PER Attachment B, RP II Dose Assessment Flowchart. x Filtration ratios 5.2.4 START MIDAS code by doble clicking on the MIDAS icon 5.2.55.2.3 FOLLOWING Release in Progress declaration OR WHEN directed by ED- CR OR RPC, THEN PERFORM dose assessment calculations PER Attachment B, RP II Dose Assessment Flowchart AND MIDAS Hard Card Information Sheets.

a. IF criteria for Airborne Release in progress Due to an Event below TRM values PER Note 1 in Attachment B, RP II Dose Assessment Flowchart are met, THEN COMPLETE at least one MIDASURI dose calculation.

Enclosure 2 to PLA-8077, Page 268 of 560 RP II DOSE CALCULATOR EP-PS-130 Revision: 38 Page 9 of 23 Unit: 0 5.2.4 (continued)

b. IF criteria for Airborne Release in Progress above TRM values PER Note 1 of Attachment B, RP II Dose Assessment Flowchart are met, OR IF General Emergency is declared, THEN COMPLETE MIDASURI dose calculations every 15 minutes.

NOTE x URI saves the dose assessment results files (URI7) on both C:\Dose Assessment Results Files (locally) as well as in Y:\URI\Dose Assessment Results Files (network) drive of the SDS computer. x URI saves the dose assessment reports files (pdf) only locally on C:\Dose Assessment Reports of the SDS computer. x S.B. line in URI report and screen is equivalent with SSES EPB. 5.2.4 PRINT a copy of dose assessment report AND VERIFY calculation inputs.

a. IF dose assessment is satisfactory, THEN RECORD your name AND time the verification was completed AND SIGN in the Review by field on the report.

b. IF data input errors are identified, THEN REDO dose assessment calculations per step 5.2.3.

Enclosure 2 to PLA-8077, Page 269 of 560 RP II DOSE CALCULATOR EP-PS-130 Revision: 38 Page 10 of 23 Unit: 0 5.2.65.2.5 REPORT release rates and Emergency Plan Boundary (EPB) projected doses to ED - CR OR RPC. NOTE Control Room needs radiological data to evaluate entry conditions and action levels for EOP Procedures. For example, EO-000-105 procedure may require reactor SCRAM AND RPV control when an Alert based on radiological conditions is met, OR rapid depressurization if a General Emergency based on radiological conditions is met.

a. IF conditions that may trigger a change in emergency classification per Table R EALs in EP-RM-004 (White board in RP area) are met, THEN IMMEDIATELY NOTIFY ED-CR OR RPC.

b. IF EPB projected doses are greater than 1 rem TEDE or 5 rem Thyroid CDE, THEN IMMEDIATELY NOTIFY ED-CR OR RPC.

5.2.7 USE MIDAS Field to Projection Measurement Comparison in EP-PS-001 to determine if Back Calculations are necessary and confirm release characteristics. NOTE x URI saves the dose assessment results files (URI7) on both C:\Dose Assessment Results Files (locally) as well as in Y:\URI\Dose Assessment Results Files (network) drive of the SDS computer. These files can be used in any facility in URI Summation mode. x URI saves the dose assessment reports files (pdf) only locally on C:\Dose Assessment Reports of the SDS computer. 5.2.6 For each calculation performed AND IF Y network drive is available, THEN COPY the dose assessment report (pdf file) from the local C drive to the network drive in the Y:\URI\Dose Assessment Reports folder of the SDS computer. 5.2.85.2.7 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 270 of 560 RP II DOSE CALCULATOR EP-PS-130 Revision: 38 Page 11 of 23 Unit: 0 5.3 Field Team Monitoring (REFERENCE USE) 5.3.1 IF TSC RP Radio Communicator has NOT arrived in TSC AND Field Monitoring Teams (OSCAR OR A FMT) are available, THEN ASSUME TSC RP Radio Communicator duties PER EP-PS-134, TSC RP Radio Communicator. 5.3.2 UPON directions from the RPC AND FOLLOWING the TSC Dose Calculator arrival in the TSC, ASSUME TSC RP Radio Communicator role under direction of RPC.

a. BRIEF TSC Dose Calculator on the following:

x Emergency status x Equipment status x Team assignments x Team deployment strategies 5.3.3 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 271 of 560 RP II DOSE CALCULATOR EP-PS-130 Revision: 38 Page 13 of 23 Unit: 0 6.0 RECORDS x ALL MIDASURI runs x ALL MIDASURI Dose Assessment Summary SheetsReports generated x All Field Team Data Sheets received from Field Teams x ALL measured to projection dose rate evaluations x ALL logs, data and documented communications generated.

Enclosure 2 to PLA-8077, Page 272 of 560 RP II DOSE CALCULATOR Attachment A EP-PS-130 Revision: 38 Page 14 of 23 Unit: 0 Attachment A, HP II Dose Calculator Hard Card MAINTAIN a chronological event log for activities in this procedure including: Dose Assessment Calculations (Section 5.2) IF PSS meteorological OR vent release rate data is questionable, With Operations OR RPC OR Engineering, DETERMINE if condition is normal (i.e., per design). OBTAIN alternate data AND USE them in dose calculationavailable data and alternate scaling methods to perform dose assessment calculations If necessary, GO TO control room (CR) to perform dose calculation using VERMS AND meteorological panel displays ENSURE OSCAR is dispatched AND is taking air samples USE alternate data such as grab sample vent results in dose assessment calculation to check on previous results With ED-CR OR RPC, DISCUSS x Projection time x Duration AND type of release (monitored OR unmonitored) Release pathways AND magnitude scaling methods used to perform URI calculations x Filtration ratios START MIDAS program Following Release in Progress declaration OR WHEN directed by ED - CR or RPC, PERFORM dose calculations. IF site totals are below TRM values, PERFORM one dose calculation. IF site totals exceed TRM limits OR GE is declared, PERFORM dose calculations every 15 minutes., following successful verification PRINT a copy of dose assessment report AND VERIFY calculation inputs, IF verification is satisfactory, RECORD your name, time the verification was completed AND signature on the dose assessment report IF verification is satisfactory, REPERFORM dose assessment calculations

FORM EP-PS-130-1 Rev. 6, Page 1 of 3

Enclosure 2 to PLA-8077, Page 273 of 560 RP II DOSE CALCULATOR Attachment A EP-PS-130 Revision: 38 Page 15 of 23 Unit: 0 REPORT release rates AND EPB projected doses to ED-Control Room OR RPC OR TSC Dose Calculator. IF conditions that may trigger a change in emergency classification are met per Table R in EP-RM-004, IMMEDIATELY NOTIFY ED-CR OR RPC. IF EPB projected doses are greater than 1 rem TEDE or 5 rem Thyroid CDE, IMMEDIATELY NOTIFY ED-CR OR RPC. COMPARE Field to Projected EDE AND Thyroid CDE dose rates to determine if Back Calculations are necessary AND confirm release characteristics. For each calculation performed, COPY the dose assessment report file (.pdf) from the local C drive to the Y network drive if available FORM EP-PS-130-1 Rev. 6, Page 2 of 3

Enclosure 2 to PLA-8077, Page 274 of 560 RP II DOSE CALCULATOR Attachment B EP-PS-130 Revision: 38 Page 18 of 23 Unit: 0 RP II DOSE ASSESSMENT FLOWCHART Release in Progress Triggers ACTIVATION REQUIREMENTS Below TRM values (only one dose projection is required): As determined by CED-CR or per EP-PS-001, Release in Progress Guidance. RP II Dose Calculator Above TRM values (dose projections every 15 minutes): 1 - MIDAS Available &

     - Vent Monitor Triggers:                                                                                            - PSS or TSC Communications Available Total NG Release Rate > 2.0 E6 Ci/min for 60 minutes
     - Field Team Triggers GREATER THAN 0.1 mrem/h EDE OR GREATER THAN 100 ccpm on iodine cartridge Vent Flow Rates (cc/minute)

U#1 RB = 3.5E+9 cc/min U#2 RB = 3.2E+9 cc/min U#1 TB = 4.4E+9 cc/min U#2 TB = 2.7E+9 cc/min SBGT (10,100 scfm) = 2.9E+8 cc/min w/outside air dilution EVENT STATUS SBGT In-service To Be Determined by Operations 2 Staff Briefing and Information Exchange with ED-CR Secondary Containment Flow to SBGT Max Flow Rate (4000 scfm max)= 1.1E+8 cc/min Turbine Building Releases Releases in turbine building are usually unfiltered. Confirm 3 with Shift Manager/ED. Filter Efficiencies TURNOVER SE Charcoal Acceptance Criteria = 99.825% SE Particulate Acceptance Criteria = 99.95% All Calculations to TSC DC or DAST Control of Field Teams to HP Radiocommunicator Containment High Radiation Monitor or FTD Background @ 100% power ~ 3 R/hr Dose and Dose Rates EAL Criteria Table R, entry conditions in rows B and D in Table F and CG1.1, CG1.2, EU1.1, SU4.1, SU4.2 EALs MONITOR EFFLUENT RELEASE AND PLANT STATUS x PSS Met Vent Data x OSCAR Data x In-Plant Conditions 1 No dose Release In-Progress? No calculation is necessary Yes Perform Forward Multi-unit dose assessment calculations, if applicable Ref.: EP-RM-005 1

                                                                                                                                               > Field Team No      Triggers?

Yes 2 MONITORED RELEASE No PSS NG Data Yes Is White? SBGT System Running ? No OPERATIONS INPUT Time to mechanically stop leak or Cooldown Time (CD) Yes x CD is time until RCS temperature is SMALLER than boiling temperature and RPV pressure SMALLER THAN 5 psig x Assume initial time of 5 hours if unknown AND Affected Unit adjust hourly per plant conditions as appropriate Yes SBGT & TB Vent Yellow? FORWARD CALCULATION MIDAS Menu A with No x Use Vent Totals Until Chemistry Data is x Filtered Default NG/I = 1,000 & NG/Part =10,000 3 Affected Unit x Unfiltered Default NG/I = 20 & NG/Part = 27 Available for vents which are white Yes RB and TB Data No x Inform ED-CR that vent data is required x Chemistry / Measured NG/I & NG/Part Ratios (preferable) Yellow? ACCIDENT TYPE x Potential Unmonitored Release x Power > 10% : Use ATWS x Power < 10%: Choose appropriate LOCA type x Inform ED-CR of potential unmonitored release x 818' Hi Rad: Use Fuel Handling Accident x Inform ED-CR that vent data is required xIf release is filtered use site totals and:

                                            - If SBGT is in service, use TB vent path below if TB vent pathway is dominant OR SBGT vent path below.                                                                                                                                                              MIDAS B - W
                                            - If SBGT is NOT in service, use RB/TB vent path below.                                                                                                                             Back Calculation xWhen there are two significant release pathways (i.e. filtered from SBGT vent AND unfiltered from one or both TB vents), use Multi-Source Accident Run to perform both paths below.

Release from STBG Vent Release from RB or TB VENT x Use Initial Release Duration = 11 Hours OR Field Monitor Data x Use Initial Release Duration = 6 Hours OR time from Operation Input box above plus 6 Use OSCAR Data (if available and rad conditions allow) or A Field time from Operations Input box above plus 1 hr hrs with a limit of 16 hrs OR Team with a limit of 16 hrs OR 6 hrs once the leak is stopped and adjust x Distance, 1 hour after the leak is stopped hourly per plant conditions x EDE Gamma Dose Rate x Projection Time = 16 hours x Use Projection Time = 16 hours x Iodine Cartridge ccpm OR same release filtration ratios defined in the Monitored Release path to the left (Filtered Default Mix OR Unfiltered Default Mix OR Mix from Chemistry Results (preferable) 1 For Field Dose Rates GREATER OR EQUAL THAN Threshold Values Calculate Field/Projected EDE Ratio AND Field/Projected CDE Ratio x Use Monitored Release path to the left to Ratio determine accident type and release duration Ratio GREATER x Use Projection Time = 16 hours Yes BETWEEN No THAN 1 Yes 0.1 and 1? No High Field Readings: Perform Back Calculation MIDAS B-W Low Field Readings (ratio SMALLER THAN 0.1): x If EDE ratio GREATER THAN 5 look for unmonitored release LOCATE PLUME x If THY CDE ratio GREATER THAN 5 obtain vent sample & look for unfiltered release x IF Release in Progress is declared, DIRECT Field teams to periodically collect air samples throughout duration of release. x Initiate dose tracking & consider Protection Measures for Field Teams

                                                                                                         - GREATER THAN 800 mR/h
                                                                                                         - GREATER THAN1rem/hr Adult Thy CDE
                                                                                                         - GREATER THAN 7,500 ccpm (cartridge) x Discuss Release Pathway and Source Term with ED-CR x Control Exposure and Dose                                                                                       Release x Use most conservative (i.e. highest dose) valid calculations if
                                                                                                         - GREATER THAN 4 rem WB (0.4 rem Pregnant Female)                                                            Terminated?

Yes Stand By for other assignments more than forward calculation is required

                                                                                                         - GREATER THAN 4 rem WB - w/Emerg. Extension
                                                                                                         - GREATER THAN 5 rem Adult Thy CDE/Shift                                                                         No
                                                                                                         - GREATER THAN 10 rem Adult Thy CDE Total x When a General Emergency is declared or when Thy CDE approaches 10 rem recommend to ED-CR issuance of KI to field teams x Consider WBC FORM EP-PS-130-2, Rev. 6, Page 1 of 1 FORM EP-PS-130-2 Rev. 7, Page 2 of 7

Enclosure 2 to PLA-8077, Page 275 of 560 RP II DOSE CALCULATOR Attachment B EP-PS-130 Revision: 38 Page 19 of 23 Unit: 0 RP II DOSE ASSESSMENT FLOWCHART ACTIVATION REQUIREMENTS Note 1: Above TRM Values RP II Dose Calculator - Vent Monitor Triggers: Total NG Release Rate > 9.5E5 Ci/min for 60 minutes

                      - URI Available &                                                         - Field Team Triggers:
                      - PSS or TSC Communications Available x    GREATER THAN 0.1 mR/hr ORI x    GREATER THAN 100 ccpm on frisker EVENT STATUS Note 2: Blowout Panel Release (unmonitored, unfiltered)

Staff Briefing and Information Exchange with ED-CR Pathway D: A BOP calculation is ONLY used for a puff release, either when the leak was immediately isolated after the blowout panel lift, OR I after the isolation occurs to approximately account for the leftover activity release after isolation. Therefore, this calculation is to be used ONLY I one time for the same BOP lift. MONITOR EFFLUENT RELEASE AND PLANT STATUS Note 3: Release Duration x PSS Met Vent Data x OSCAR and Field Monitoring Teams Condition - Scenario Dependent Release Duration, Hours x In-Plant Conditions Blowout panel with immediate isolation (Pathway D) 0.25

-~

Condition - Building Specific TB / RB Vent OR I SBGT Vent RB / TB damaged (Note 8) Rx. Depressurized (< 5 psig) OR release pathway isolated I 1 6* IF Rx. Can be depressurized AND RHR Shutdown cooling is available 6* 11* Has a Release in Otherwise 12* 111/ No Progress Been

Times listed are for Rx NOT being Shutdown (SD) OR for the initial release duration after Rx SD. Following Rx SD, ADJUST as information Declared? changes OR time passes but, except for blowout panel calculation (Pathway D), DO NOT ENTER a release duration smaller than 1 hr.

I For example, IF started with an initial release duration of 11 hours for a SBGT vent release AND one hour from a successful reactor SCRAM has Yes each additional hour passed from the reactor SD. II passed, DECREASE the release duration by one hour if no other information has changed AND REPEAT the release duration time decrease for Note 4: Is SBGT Running? I I COMPLETE the Pathway Selection Flowchart below, GO TO Chart 1 AND CIRCLE SBGT is usually running for a total vent stack flow of GREATER than 10,000 cfm. CONFIRM with Operations id SBGT is running. the applicable Pathway AND PERFORM one Valid Calculation. Note 5: Multiple Pathways Examples of Multiple Pathways include, but are not limited to: For releases above TRM values (Note 1) OR in a General Emergency, - Concurrent releases from pathways in both units (ex. U1 TB vent AND U2 TB Vent) PERFORM Valid Calculations using the Pathway Selection Flowchart and Chart 1 - Concurrent release from more than one point for the same unit (ex. U1 TB vent AND U1 RB Vent) every 15 minutes OTHERWISE

                                                                                                - When there are two or more significant release pathways (i.e. Significant filtered release from SGTS/RB vent AND unfiltered release from one USE the release in progress calculation above as the valid calculation AND             or both TB vents CONTINUE to monitor for conditions specified above Note 6: Steam Leak in TB / RB I - Steam leak into the TB includes Condenser NOT under vacuum OR feedwater leak by. CONFIRM with Operations.
                                                                                                - Steam leak in RB includes containment bypass (Ex. RCIC line break), (LOCA in DW with DBA leakage or with primary containment loss per EAL)

I OR SP steam leakage. Is Field Team No Data Available?

                                    /                                                         I Note 7: LOCA bypassing the DW with direct blowdown to the SP (steam safeties)

Example: SRV stuck open OR Automatic / Manual Emergency Depressurization WITHOUT LOCA in DW. CONFIRM with Operations. Yes Note 8: Reactor Building (RB) / Turbine Building (TB) Intact Examples include Blowout panel without immediate line isolation, throwing a turbine blade through the building, visible damage of building x DIRECT Field Team(s) per EP-PS-134 procedure x If Field team report exposure rates / air sample cartridge readings exceed (i.e., hole in a RB / TB building), loss of ventilation, etc limits in Field Measurement Guidelines Table (white board of EP-PS-001-35 form), IMMEDIATELY INFORM CR-ED Note 9: Source Term SELECT Fuel Clad Damage Yes checkbox ONLY if Operations states there is Fuel Damage. SELECT Fuel Clad Damage No checkbox for normal coolant source term

                                                                                                - SELECT Yes checkbox for Have Conditions for Coolant Spiking been met for an automatic / manual emergency depressurization TURNOVER x    All Calculations to TSC DC or DAST x    CONTINUE to act as RP Radiocomminicator per EP-PS-134 OR TURNOVER control of Field Teams to another RP Radiocommunicat as directed by RPC Pathway Selection Flowchart RUN separate calculations for IF NOT previously performed,                                                                                                                                                                             GO TO Chart 1 to determine the Are there                  each applicable pathway AND                               SELECT appropriate Fuel Clad COMPLETE EP-PS-001-65, DA                                                                                                                                                                                    pathway to run, CLICK on Multiple, significant             USE Calculation menu ->                             Damage checkbox (SEE Note 9) AND Data Gathering Form OR                                  release points or      Yes                                                                                                                       appropriate checkbox in the source terms?
                                                                    \                          Simultaneous Release                               ENTER the actual Reactor Shutdown, CONSIDER updating the form, if                                                                                                                                                                           Release Point Pathway pane AND (Note 5)                 Summation option to perform multi                      if applicable, in the Source Term pane time allows                                                                                                                                                                                       RUN calculation per Table 1 No                           source calculation FORM EP-PS-130-2, Rev. 7, Page 1 of 5 FORM EP-PS-130-2 Rev. 7, Page 3 of 7

Enclosure 2 to PLA-8077, Page 276 of560 RP II DOSE CALCULATOR Attachment B EP-PS-130 Revision: 38 Page 20 of 23 Unit: o Chart 1: Reactor Accidents Chart1 legend Steamleak(seeNote6} Release Turbine Building Riter Reactor Building SBGT / RB Filter Drywell

JE an unmonitored release is identified for Pathways A, B, E, H. L QR P, CLICK on the applicable pathway checkboxin Release Point Pathway pane, AND.RUN calculation using No Effluent Monitors available method In Table 1 Recommended Order for Data Entry in URI (Rapid Mode)

                                              !f.trlterla for running Calculations f3Jeryl5 minute5IS met!J:mlli2data has                                                  St!!p7:RUN lOMUecalc changed 'Mthfn this Interval, PRESS Force Reco/wlatlon Button                      AND. GO TO Step 7 j1~.~R:a1;1~-~~t-                                  a1Eyentl fl.l~*   ~!l~;ition:s *}Jclp*                               ..* ,:.-.*   *.     ..      *.
                                                     ;:~~*~l~.l!~-~Foc~~~k~r~~-!-~+1~~~~!~~~oM~-d~ '_
                                                        ~Term                 * .:_ _ ~-****                                                       **

Stepl:SourceTermSelection,lf N.Q!alreadyenteredQ.!tchanged (SEEP11thl.UllVSPIP-r.tlnnflowr.h.lrt\

                                                       ~~~~f]?-:r~o-<<~

J1;-v.L..;,r,:;':l,M<:',-:-i,~-.:::;..,,=*;,.,,;,.~"Jlc""'-r:w.;*

Step2:ReactorShutdownifappllc:able AN.D.H.Q!alreadyentered (SEE PathwaySelec:t:lonFtowchart} Sb!p6:MetData,ifN.Qlalreadyentere

            .QBchanged(SEETablel)

Sb!.pS:ReleaseDuration(SEETablel A,M2Note3) Step3:Pathwav(SEEPathway Selectlun Chart, Chart 1At:m Table 1,asappl!cable) 511!,p,4:AssessmentMethod(SEE Tablel) FORM EP-PS-130-2, Rev. 7, Page2 of5 FORM EP-PS-130-2 Rev. 7, Page 4 of?

Enclosure 2 to PLA-8077, Page 277 of 560 RP II DOSE CALCULATOR Attachment B EP-PS-130 Revision: 38 Page 21 of 23 Unit: 0 Table 1 - URI Pathway Description and Associated Assessment Methods Note: Code DOES NOT RUN if one or more required parameters (identified in the main window by ! ) are missing. ID URI Pathway Pathway Description and Examples Assessment Method and Parameters Needed Note: if the following method is selected AND Enable Auto Mode button is selected, the code will automatically update the vent readings per the user selection WHEN vent release rate is available AND valid, SELECT the Yes checkbox to answer the question Are the Effluent Monitors available in the Release Point Information pane, CHECK TB Vent checkbox AND EITHER Normal flow through the steam jet ENTER the TB vent release rate value in Readings OR, air ejectors through offgas to the

             <RCS> <Condenser>                                                  IF Enable Auto Mode button was selected, ENSURE the value was turbine building stack, with A      <Filters> <TB Vent>                                               transferred correctly condenser still under vacuum.
                     <Env>

Monitored release through TB vent. - - - WHEN vent release rate is NOT available OR valid, SELECT the No checkbox to answer the question Are the Effluent Monitors available in the Release Point Information pane, CHECK Estimated RCS Leak checkbox AND EITHER ENTER the leak rate from Operations OR CLICK I Dont know checkbox GO TO instructions at the end of the Table to complete calculation. Note: if the following method is selected AND Enable Auto Mode button is selected, the code will automatically update the vent readings per the user selection WHEN vent release rate is available AND valid, SELECT the Yes checkbox to answer the question Are the Effluent Monitors available in the Release Point Information pane, CHECK TB Vent checkbox AND EITHER Steam leak in TB, including ENTER the TB vent release rate value in Readings OR, Condenser NOT under vacuum OR IF Enable Auto Mode button was selected, ENSURE the value was

           <RCS> <Turb Bldg> <TB       feedwater leak by, released through B                                                                        transferred correctly Vent> <Env>                   normal TB ventilation Monitored / Unfiltered release.   -WHEN                          -             -

vent release rate is NOT available OR valid, SELECT the No checkbox to answer the question Are the Effluent Monitors available in the Release Point Information pane, CHECK Estimated RCS Leak checkbox AND EITHER ENTER the leak rate from Operations OR CLICK I Dont know checkbox GO TO instructions at the end of the Table to complete calculation. CLICK Estimated RCS Leak Rate checkbox AND ENTER estimated leak rate in gpm from Table below: Panel Calculated Leak Rate, gpm LOCA directly into RB or TB with RCIC Pump Room 8 blowout panel lift and line

           <RCS> <Blowout Panel>                                                               HPCI Pump Room                         100 D                                              isolation.
                     <Env>                                                                RWCU Penetration Room                       125 RCIC/HPCI Pipe Routing Area                   145 Unmonitored / Unfiltered Puff release.

I RB / TB Main Steam Tunnel I 940 I GO TO instructions at the end of the Table to complete calculation. Note: if the following method is selected AND Enable Auto Mode button is selected, the code will automatically update the vent readings per the user selection WHEN vent release rate is available AND valid, SELECT the Yes checkbox to answer the question Are the Effluent Monitors available in the Release Point Information pane, Leak directly to the RB SELECT EITHER RB Vent OR SBGT Vent checkbox, as appropriate per Note (containment bypass) released through normal RB / SBGT -- 4, AND EITHER

               <RCS> <Rx Bldg>                      ventilation.                                 -

ENTER the RB OR SBGT vent release rate value in Readings OR, E <Filters> <Env> Monitored release through RB / SBGT vent. WHEN vent release rate is NOT available or valid, SELECT the No checkbox Like pathway H but without LOCA in to answer the question Are the Effluent Monitors available in the Release Point DW. Information pane, CHECK Estimated RCS Leak checkbox AND EITHER ENTER the leak rate from Operations OR CLICK I Dont know checkbox GO TO instructions at the end of the Table to complete calculation. Leak directly into the RB - ENTER the leak rate from Operations in gpm OR CLICK I Dont know (containment bypass) NOT released through ventilation (SEE checkbox. F <RCS> <Rx Bldg> <Env> Note 8 for examples). GO TO instructions at the end of the Table to complete calculation. Unmonitored / Unfiltered release from RB. FORM EP-PS-130-2, Rev. 7, Page 3 of 5 FORM EP-PS-130-2 Rev. 7, Page 5 of 7

Enclosure 2 to PLA-8077, Page 278 of 560 RP II DOSE CALCULATOR Attachment B EP-PS-130 Revision: 38 Page 22 of 23 Unit: 0 Table 1 (cont) ID URI Pathway Pathway Description and Examples Assessment Method and Parameters Needed Note: if the following method is selected AND Enable Auto Mode button is selected, the code will automatically update the vent readings per the user selection WHEN vent release rate is available and valid, SELECT the Yes checkbox to answer the question Are the Effluent Monitors available in the Release Point Information pane, SELECT EITHER RB Vent OR SBGT Vent checkbox, as appropriate per Note 4, AND EITHER ENTER the RB OR SBGT vent release rate value in Readings OR, IF Enable Auto Mode button was selected, ENSURE the value was transferred correctly WHEN vent release rate is NOT available OR valid, SELECT the No checkbox LOCA in DW, with DW leaking into to answer the question Are the Effluent Monitors available in the Release Point the RB, including design basis DW Information pane, AND leakage, released through RB / EITHER:

         <RCS> <Drywell> <Rx SBGT ventilation.         x CHECK Estimated RCS Leak checkbox AND EITHER H   Bldg> <Filters>  <Env>

Monitored release through RB / SBGT OR vent. Note: if the following method is selected AND Enable Auto Mode button is Like pathway E but with LOCA in DW. selected, the code will automatically update the CHRM A or B readings per the user selection x CHECK Containment Leakage checkbox AND SELECT one of the applicable checkboxes: Cont High Rad A, Cont High Rad B OR No Monitor available or Applicable Note: The Containment Radiation Monitors method is applicable ONLY for a LOCA in DW AND can be used ONLY when CHRM values have stabilized. IF available AND valid, SELECT the highest CHRM value AND EITHER ENTER its value in Readings OR, IF Enable Auto Mode button was selected, ENSURE the value was transferred correctly GO TO instructions at the end of the Table to complete calculation. Note: if the following method is selected AND Enable Auto Mode button is selected, the code will automatically update the vent readings per the user selection WHEN vent release rate is available and valid, SELECT the Yes checkbox to answer the question Are the Effluent Monitors available in the Release Point Information pane, SELECT EITHER RB Vent OR SBGT Vent checkbox, as appropriate per Note 4, AND EITHER ENTER the RB or SBGT vent release rate value in Readings OR, IF Enable Auto Mode button was selected, ENSURE the value was transferred correctly WHEN vent release rate is NOT available or valid, SELECT the No checkbox LOCA in DW blowing down to the to answer the question Are the Effluent Monitors available in the Release Point SP with SP leaking into RB, Information pane, AND EITHER:

        <RCS> <Drywell> <Supp          released through RB / SBGT     x CHECK Estimated RCS Leak checkbox AND EITHER Pool> <Rx Bldg>                    ventilation.                 ENTER the leak rate from Operations OR L
          <Filters>  <Env>       Monitored release through RB / SBGT     OR vent                  Note: if the following method is selected AND Enable Auto Mode button is Like pathway P but with LOCA in DW      selected, the code will automatically update the CHRM A or B readings per the user selection x CHECK Containment Leakage checkbox AND SELECT one of the applicable checkboxes: Cont High Rad A, Cont High Rad B OR No Monitor available or Applicable Note: The Containment Radiation Monitors method is applicable ONLY for a LOCA in DW AND can be used ONLY when CHRM values have stabilized.

IF available and valid, SELECT the highest CHRM value AND EITHER ENTER its value in Readings OR, IF Enable Auto Mode button was selected, ENSURE the value was transferred correctly. GO TO instructions at the end of the Table to complete calculation. Note: if the following method is selected AND Enable Auto Mode button is selected, the code will automatically update the vent readings per the user selection WHEN vent release rate is available and valid, SELECT the Yes checkbox to answer the question Are the Effluent Monitors available in the Release Point Information pane, SELECT EITHER RB Vent OR SBGT Vent checkbox, as appropriate per Note LOCA bypassing the DW with 4, AND EITHER direct blowdown to the SP (e.g. ENTER the RB or SBGT vent release rate value in Readings OR, steam safeties) with SP leaking IF Enable Auto Mode button was selected, ENSURE the value was into the RB with RB ventilation in transferred correctly

       <RCS> <Supp Pool> <Rx service through EITHER normal RB P     Bldg> <Filters>  <Env>                                           WHEN vent release rate is NOT available or valid, SELECT the No checkbox to answer the question Are the Effluent Monitors available in the Release Point Monitored release.        Information pane, AND EITHER:

Like pathway L but without LOCA in x CHECK Estimated RCS Leak checkbox AND EITHER DW. ENTER the leak rate from Operations OR CLICK I Dont know checkbox OR x CHECK Containment Leakage checkbox AND SELECT No Monitor available or Applicable checkbox GO TO instructions at the end of the Table to complete calculation. FORM EP-PS-130-2, Rev. 7, Page 4 of 5 FORM EP-PS-130-2 Rev. 7, Page 6 of 7

Enclosure 2 to PLA-8077, Page 279 of 560 RP II DOSE CALCULATOR Attachment B EP-PS-130 Revision: 38 Page 23 of 23 Unit: 0 Table 1 (cont) To complete the calculation: Note: Code DOES NOT RUN if one or more required parameters (identified in the main window by ! ) are missing Note: If changing any of the parameters in the Source Term Pane, the code resets and the appropriate Pathway needs to be selected again.

1. VERIFY whether the parameters in the Source Term Pane need to change AND PERFORM the change if necessary.

2. IF NOT previously performed, ENTER the Reactor Shudown time, if appropriate.

3. CLICK Enable Auto Mode button to automatically enter meteorological data, DRAG AND DROP OR ENTER actual and valid Meteorological Data from:

Note: Based on the chosen Pathway, the met tower (10 OR 60 m) release height is automatically selected; 10 m data applies to Pathways D and F while 60 m data applies to all the other Pathways in Table 1 x Primary Tower (10 m OR 60 m data, as applicable for the release point) x IF primary met tower data is NOT valid, ENTER 10 m data from the Backup Tower x IF both primary and backup met tower data is NOT available, SEE EP-PS-001-41 for additional options

a. DETERMINE whether it is raining or snowing AND ENTER precipitation value in the dropdown selection using R*Time Precipitation Rate, if available, and table below:

RAININHR in IN/HR URI Value to ENTER for Precipitation Type 0 None Up to 0.089 Light Rain Between 0.089 and 0.24 Moderate Rain Greater than 0.24 Heavy Rain I Up to 0.089 Greater than 0.089 I Light Snow Moderate / Heavy Snow

4. ENTER OR CHECK if appropriate release duration is entered per Note 3.

5. CLICK 10 Miles button in Process Assessment To: window to run calculation.

FORM EP-PS-130-2, Rev. 7, Page 5 of 5 FORM EP-PS-130-2 Rev. 7, Page 7 of 7

Enclosure 2 to PLA-8077, Page 280 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 5 of 23 Unit: 0 1.0 PURPOSE AND SCOPE 1.1 Purpose 1.1.1 This procedure describes actions to be taken by the Technical Support Center (TSC) RP Radio Communicator during an event at Susquehanna Steam Electric Station (SSES). 1.2 Scope 1.2.1 This procedure is used by the TSC RP Radio Communicator upon arriving at TSC until the termination of the emergency event or until relieved by another TSC RP Radio Communicator. 1.2.2 The TSC RP Radio Communicator directs the emergency environmental field monitoring team(s) (FMT) to determine the significance of airborne releases. 1.2.3 In the context of this procedure, when not specifically indicated as Field Monitoring Team (FMT) A, the term FMTs by itself includes OSCAR. 1.2.31.2.4 Attachment A, RP Radio Communicator Hard Card, may be used to perform placekeeping for reference-use sections in this procedure. 1.2.5 Expectation is to complete procedure steps in a way that ensures continuous operation during time critical evolutions during emergencies or drills. 1.2.41.2.6 This procedure ensures that SSES commitments delineated in Emergency Plan Section 6 and 7, and regulatory requirements 10CFR50.47(b) and Appendix E are fulfilled. 1.2.51.1.1 Expectation is to complete procedure steps in a way that ensures continuous operation during time critical evolutions during emergencies or drills.

2.0 REFERENCES

AND COMMITMENTS 2.1 Performance References 2.1.1 EP-PS-001, Emergency Planning Forms and Supplementary Instructions 2.1.2 EP-RM-007, Emergency Telephone Instructions and Directory 2.1.3 EP-00-005, Remote Assembly Area Contamination Control 2.2 Developmental References 2.2.1 SSES Emergency Plan 2.2.1 EP-PS-105, TSC Dose Calculator 2.2.2 NUREG 0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants

Enclosure 2 to PLA-8077, Page 281 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 6 of 23 Unit: 0 2.2.3 NEP Technical Basis 16-001, Frisker Response in Support of EAL Implementation and Determination of Release In Progress 2.3 Commitments 2.3.1 None 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions 3.1.1 None 3.2 Limitations 3.2.1 None 4.0 PREREQUISITES AND INITIAL CONDITIONS 4.1 Prerequisites 4.1.1 L IF responding to a phone call or plant PA announcement of an emergency, THEN TAKE source checked dose rate meter AND frisker to TSC 4.1.2 IF relieving an on-shift TSC RP Radio Communicator, THEN OBTAIN a shift turnover from the current TSC RP Radio Communicator using shift turnover process described in Step 5.8. 4.2 Initial Conditions x An Emergency Plan entry has been declared x Facility has been precautionary staffed x An emergency tabletop, drill or exercise is being conducted

Enclosure 2 to PLA-8077, Page 282 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 7 of 23 Unit: 0 5.0 INSTRUCTIONS 5.1 Initial Actions (Information Use) 5.1.1 SIGN IN on TSC Access Log. 5.1.2 SIGN IN on TSC On Duty Personnel Board 5.1.3 NOTIFY TSC Dose Calculator of arrival.

a. IF TSC Dose Calculator is NOT present, THEN NOTIFY RP II Dose Calculator OR Radiation Protection Coordinator (RPC) of arrival.

5.1.4 OBTAIN the following forms from EP-PS-001, Emergency Planning Forms and Supplementary Instructions: x Calculation and Tracking Sheet for Estimated IodineThyroid CDE and TEDE Doses x County Emergency Worker Decontamination Facility Locations x Emergency Exposure Extension Request x Emergency Personnel Dose Assessment and Protective Action Guide x Field Team Monitoring Strategy Notes x Logkeeping Instructions and Paper Log Form x Potassium Iodide (KI) Tracking Form x Survey Data Form 5.1.5 INITIATE a chronological log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 283 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 8 of 23 Unit: 0 5.1.6 OBTAIN a briefing from TSC Dose Calculator OR RP II Dose Calculator OR RPC including the following: x Release occurred or is in progress or is imminent x Nature of the release x Wind direction x Wind speed x Atmospheric stability x Affected sector x Emergency classification 5.1.7 TURN ON VHF radio to channel 1.

a. ROTATE volume clockwise to acceptable volume.

5.1.8 IF notified that OSCAR OR West Building RadiologicalField Monitoring Team (FMT) A Van at West Building will not start OR is otherwise NOT functional, THEN DIRECT OSCAR RP I Technician OR Emergency Monitoring TeamFMT A, respectively, to perform alternate starting instructions per their procedure. NOTE Telephone numbers are in the EP-RM-007, Emergency Telephone Instructions and Directory.

a. IF van still does not start, THEN OBTAIN repairs or a replacement vehicle by performing the following:

(1) REQUEST a spare vehicle from TSC Security Coordinator. (2) IF a Security vehicle is NOT available, THEN CONTACT SSES garage AND REQUEST to (a) Jumpstart van; (b) Replace battery. (c) IF van still does not start, THEN REQUEST a loaner vehicle with an AC inverter

Enclosure 2 to PLA-8077, Page 284 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 9 of 23 Unit: 0 5.1.8.c (continued) (3) IF SSES garage is NOT available during off hours, THEN REQUEST EOF Duty Planner from the ERO on call list to arrange for a replacement van, preferably with an AC outlet, from a local vehicle rental agency.

b. WHEN a replacement van is obtained, THEN ENSURE manual air sampler AND hand held instruments are loaded in vehicle.

5.2 Field Team Monitoring Strategy Determination (Information Use) 5.2.1 DETERMINE an effective Field Team Monitoring Strategy, referencing PER Field Team Monitoring Strategy Notes in EP-PS-001, which consider: x Availability AND status of Field Teams. x Wind direction AND wind speed. x Atmospheric stability. x Potentially affected sector(s). x Terrain factors. x Impact of cooling tower entrainment. x Field Team exposure control. x Field Team members with iodine allergy. x Availability of traverse routes in affected sector(s). 5.2.2 NOTIFY TSC Dose Calculator OR RPC regarding monitoring strategy. 5.2.3 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 285 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 10 of 23 Unit: 0 5.3 Taking Control of OSCAR and Field Monitoring Team A (Information Use) 5.3.1 OBTAIN the following information from TSC RP II Dose Calculator OR other individual that dispatched Team(s):FMTs x OSCAR AND ALPHA TeamFMT A member names x OSCAR AND ALPHA TeamA FMT members initial dose (YTD) x OSCAR AND ALPHA TeamFMT A current dose extensions x OSCAR AND ALPHA TeamFMT A cell phone number(s) x Sectors monitored by OSCAR AND ALPHA TeamFMT A x Locations monitored by OSCAR AND ALPHA TeamFMT A x Results for previously monitored locations

a. IF information is NOT available from RP II Dose Calculator, THEN OBTAIN information from OSCAR AND ALPHA Field Monitoring TeamFMT A.

5.3.2 CONDUCT a radio checkPERFORM communications checks with OSCAR AND ALPHA Field Monitoring TeamFMT A. NOTE The TX light and the F1 light will illuminate when the handset button is depressed.

a. DEPRESS button on handset to transmit.

b. RELEASE button to receive.

c. IF channel 1 is inoperable, THEN USE channel 2.

5.3.3 IF ALPHA Field Monitoring TeamFMT A OR OSCAR were previously dispatched, THEN:

a. OBTAIN a target time from TSC Dose Calculator OR RPC for taking control of Field TeamsFMTs

b. COORDINATE turnover with RP II Dose Calculator OR other individual that dispatched Field Teams.

c. PERFORM communications checks with Field TeamsFMTs.

Enclosure 2 to PLA-8077, Page 286 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 11 of 23 Unit: 0 5.3.3 (continued)

d. WHEN directed by TSC Dose Calculator OR RPC, THEN INFORM Field TeamsFMTs AND RP II Dose Calculator OR individual who dispatched Field Teamsthem that Field TeamsFMTs are now being directed by RP Radio Communicator.

e. REQUEST Field TeamsFMTs report present locations.

f. DIRECT Field TeamsFMTs to continue monitoring PER briefing and assignments received.

g. RECORD turnover in TSC RP Radio Communicator Log.

5.3.4 IF OSCAR OR Field Team wereFMT A was NOT previously dispatched, THEN:

a. IF RP II Dose Calculator OR other personnelindividual has started team deployment process, THEN OBTAIN a target time from TSC Dose Calculator for taking control of Field TeamsFMTs.

b. COORDINATE turnover time with RP II Dose Calculator OR individual preparing Teams for dispatch.

c. PERFORM communications checks with Field TeamsFMTs.

d. WHEN directed by TSC Dose Calculator OR RPC, THEN INFORM the Field TeamsFMTs AND RP II Dose Calculator OR other individual dispatching Field Teamsthem that Field TeamsFMTs are now being directed by TSC RP Radio Communicator.

e. RECORD turnover in TSC RP Radio Communicator Log.

5.4 Field Team Dispatch (Information Use) 5.4.1 OBTAIN AND RECORD the following information: x FMT A AND OSCAR member name(s) x FMT A AND OSCAR member(s) initial dose (YTD) x FMT A AND OSCAR current dose extensions x FMT A AND OSCAR cell phone numbers

Enclosure 2 to PLA-8077, Page 287 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 12 of 23 Unit: 0 NOTE Field TeamsFMTs that have already being dispatched may be briefed via radio or cell phone. 5.4.2 PERFORM TeamFMTs briefings including the following: x Event status. x Projected radiological conditions in field. x Field monitoring strategy, as determined in step 5.2, including sectors to be monitored and likely travel and traverse routes. x Radiological controls requirements listed on RWP and in Field Team Monitoring Strategy Notes in EP-PS-001. x Potential communications issues listed in Field Team Monitoring Strategy Notes in EP-PS-001. x Potassium Iodide (KI) Protective Action guidance described in Emergency Personnel Dose Assessment and Protective Action GuidePotassium Iodide (KI) Tracking Form in EP-PS-001. x Safety considerations x Obeying traffic laws x Impact of forecast weather on road conditions x Hazards of driving at low speeds x Respecting private property boundaries 5.4.3 DIRECT Field TeamFMTs members to sign on: x RWP 8001 - OSCAR x RWP 8002 - ALPHA and BRAVO x RWP 8888 - ALL for drills and exercises

a. Discuss radiological controls requirements listed on RWP AND in Field Team Monitoring Strategy Notes in EP-PS-001.

5.4.4 DISPATCH TeamFMTs. 5.4.5 RECORD a summary of completed Field TeamFMTs briefing in RP Radio Communicator Log.

Enclosure 2 to PLA-8077, Page 288 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 13 of 23 Unit: 0 5.4.6 PERFORM VHF Radio or Cell Phone operabilitycommunication check with Field Teamseach dispatched FMT.

Enclosure 2 to PLA-8077, Page 289 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 14 of 23 Unit: 0 NOTE Monitoring for radioactive airborne releases is a cyclical process that is repeated numerous times during the course of an event to initially locate the airborne plume(s), and then monitor the movement of the located plume(s). Consequently, the Flow Chart in Field Team Monitoring Strategy Notes in EP-PS-001 is the most efficient procedural tool for the TSC RP Radio Communicator to use when carrying out this cyclical monitoring process. Therefore, the flow chart steps are NOT reproduced in this section. 5.5 Directions for Field Monitoring Teams for Monitoring of Airborne Releases (Reference Use) 5.5.1 OBTAIN a visual display of plume path from TSC Dose Calculator OR RPC. 5.5.2 EMPLOYIMPLEMENT monitoring strategy established in Step 5.2 AND IMPLEMENT Field Team monitoring strategy, PER Field Team Monitoring Strategy Flowchart in Field Team Monitoring Strategy Notes in EP-PS-001 5.5.3 IF Release in Progress is declared, THEN

a. DIRECT Field teamsFMTs (preferably OSCAR) to periodically obtain an air sample, COUNT the cartridge in a low background area AND IMMEDIATELY COMMUNICATE the results

b. RECORD field monitoring results on Survey Data Forms in EP-PS-001, MAKE a copy of the form for own record AND COMMUNICATE results of plume traverse and boundaries to TSC Dose Calculator OR RPC throughout the release duration, OR as directed by TSC Dose Calculator OR RPC.

5.5.4 TRACK AND MANAGE FMTs exposure PER Calculation and Tracking Sheet for Estimated IodineThyroid CDE and TEDE Doses form in EP-PS-001 AND following instructions.

a. Every 15 to 30 minutes, LOG each FMT ED readings.

b. IF FMTs report exposure rates / air sample cartridge readings exceed limits in Field Measurement Guidelines Table (white board from Field Team Monitoring Strategy Notes in EP-PS-001),

THEN IMMEDIATELY INFORM TSC Dose Calculator or RPC

Enclosure 2 to PLA-8077, Page 290 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 15 of 23 Unit: 0 5.5.4 (continued)

c. IF FMTs report any of the following conditions, x Exposure RatesED readings equal to or greater than 800 mR/hr400 mrem x Cartridge Readings greater than 7,5004,000 ccpm THEN (1) IMMEDIATELY NOTIFY TSC Dose Calculator OR RPC.

(2) START tracking FMT Whole Body (EDE)TEDE AND Thyroid CDE per Calculation and Tracking Sheet for Estimated IodineThyroid CDE and TEDE Doses in EP-PS-001. (3) DIRECT teams to use effective exposure control measures

d. IF YTD exposure plus current ED readings areis approaching 3,800 mrem TEDE OR 8,000 mrem Thyroid CDE, THEN (1) POSITION affected FMT in a low background area until further direction is received from TSC Dose Calculator or RPC.

(2) IMMEDIATELY NOTIFY TSC Dose Calculator OR RPC that a dose extension ismay be required (3) DO NOT SEND FMTaffected FMTs back through the plume without RPC approval (4) IF other FMTs are available, THEN CALL OUT OR ROTATE FMTs to maintain thyroid CDE less than 10,000 mrem OR TEDE less than 4,000 mrem. (5) IF other FMTs are NOT available, THEN, in consultation with TSC Dose Calculator or RPC, x PLACE affected FMT further away to minimize dose OR x PROCESS a dose extension using Emergency Exposure Extension Request and Emergency Personnel Dose Assessment and Protective Action GuideForm in EP-PS-001.

Enclosure 2 to PLA-8077, Page 291 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 16 of 23 Unit: 0 5.5.4 (continued)

e. IF CDE thyroid doses are determined to be potentially greater than 10,000 mrem OR a General Emergency with a release in progress is declared OR a General Emergency is declared and the release is imminent, as communicated by RPC, THEN (1) PROVIDE names of personnel requiring KI issue to RPC using Potassium Iodide (KI) Tracking Form in EP-PS-001.

(2) WHEN approved Potassium Iodide (KI) Tracking Form in EP-PS-001 is received from RPC, THEN NOTIFY FMT personnel of recommendation to use KI including precautions regarding interactions with other drugs using Emergency Personnel Dose Assessment and Protective Action GuidePotassium Iodide (KI) Tracking Form in EP-PS-001. (3) TRACK issuance of KI using Potassium Iodide (KI) Tracking Form in EP-PS-001. (4) DIRECT teamsFMTs to track use of KI in their Potassium Iodide (KI) Tracking Form in EP-PS-001.

f. REVIEW exposure control statements of RWP 8002 and RWP 8001.

(1) IF current radiological conditions require RWP revision, THEN NOTIFY RPC. 5.5.5 IF requested by RPC, THEN DIRECT Field TeamsFMTs to perform notification of evacuation PER EP-PS-222, Emergency Monitoring Team. 5.5.6 PARTICIPATE in TSC Dose assessment staff briefings. 5.5.7 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001. 5.5.8 REPEAT steps in this section until release is terminated or field team direction is transferred to EOF FTD PER Step 5.7.

Enclosure 2 to PLA-8077, Page 292 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 17 of 23 Unit: 0 5.6 Field Monitoring Team Turnover and Termination (Information Use) NOTE

1. A turnover location should be established in a non-contaminated buffer zone in accordance with standard RP contamination control practices.

2. If personnel and resources are available, a non-contaminated company vehicle with a separate driver should transport the incoming FMT to the turnover location and transport the off-going FMT to a County Decontamination Facility.

5.6.1 IF Field TeamFMTs turnover is required, THEN with TSC Dose Calculator OR RPC, DETERMINE turnover location in an unaffected sector.

a. DIRECT off-going Field Team to proceed to turnover location AND NOTIFY TSC RP Radio Communicator when turnover is complete.

b. For incoming Field Teams, REFER TO Step 5.4

c. With TSC Dose Calculator OR RPC, DETERMINE Countythe designated Decontamination Facility to be used by off-going Field TeamFMTs in accordance with EP-00-005 procedure OR PER County Emergency Worker Decontamination Facility Locations in EP-PS-001.

d. WHEN notified Field TeamFMTs turnover is complete, THEN DIRECT off-going Field TeamFMTs to:

(1) IMMEDIATELY PROCEED to the designated County Decontamination Facility for monitoring and decontamination. (2) WHEN monitoring and decontamination is complete, THEN DEBRIEF with TSC.

Enclosure 2 to PLA-8077, Page 293 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 18 of 23 Unit: 0 5.6.2 At termination of release, PERFORM the following:

a. With TSC Dose Calculator OR RPC, DETERMINE Countythe designated Decontamination Facility to be used by Field Team(s)FMTs in accordance with EP-00-005 procedure OR PER County Emergency Worker Decontamination Facility Locations Instructions in EP-PS-001.

b. DIRECT field teamFMTs vehicles to designated decontamination facility.

c. Upon vacating team vehicle, DIRECT teamsFMTs to lock up inside the vehicle any known or suspected radioactive waste generated during field monitoring activities (1) POST field teamFMTs vehicles as containing radioactive materials AND REPORT their location to TSC RP Radio Communicator or RPC (2) NOTIFY station personnel to take custody of vehicle

Enclosure 2 to PLA-8077, Page 294 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 19 of 23 Unit: 0 5.6.2 (continued)

d. With RPC, DETERMINE OSCAR vehicle disposition

e. In accordance with Emergency Exposure Extension Request form in EP-PS-001 AND with RPC, DETERMINE the need to perform bioassay for the FMT members.

(1) IF applicable, THEN ARRANGE for AND DIRECT teamFMT members to perform bioassay per Emergency Personnel Dose Assessment and Protective Action Guide in EP-PS-001at the designated location. e.f. Upon being decontaminated, DIRECT team to debrief with TSC 5.6.3 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 295 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 20 of 23 Unit: 0 5.7 Function Turnover (Information Use) 5.7.1 WHEN notified by TSC Dose Calculator OR RPC, THEN TRANSMIT copies of TSC RP Radio Communicator Log and other Field Team Data forms including the following information to EOF Field Team Director (FTD): x OSCAR Team member name AND initial dose (YTD) x Team member Names, initial doses (YTD), AND team designator(s) for other Field Team(s) dispatched from the TSC x Current approved dose extensions for ALL team(s) x Sectors and locations monitored x Results for previously monitored sectors AND locations x Current instructions and locations for Field Team(s)FMTs dispatched from TSC 5.7.2 OBTAIN a target time from RPC for turning over control of Field Monitoring Team(s)FMTs to FTD.

a. COORDINATE turnover time with the FTD.

5.7.3 WHEN directed by RPC, THEN TURN OVER control of the Field Monitoring Team(s)FMTs to FTD. 5.7.4 NOTIFY Field Team(s)FMTs AND RPC that field teams are now being directed by FTD. 5.7.5 SECURE TSC RP Radio Communicator duty station. 5.7.6 SUPPORT site response as directed by RPC.

Enclosure 2 to PLA-8077, Page 296 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 21 of 23 Unit: 0 5.8 Shift Turnover (Information Use) 5.8.1 REMAIN at duty station with full responsibility until properly relieved. 5.8.2 PERFORM a briefing forBRIEF the on-coming TSC RP Radio Communicator on the following: x Emergency status x Communication AND FMT equipment status x TeamFMTs assignments x TeamFMTs deployment strategies x Individual bioassay requirements for field team members x Exposure control measures in effect (KI) x Impediments x Current step in procedure 5.8.3 With RPC, BRIEF off-going TSC RP Radio Communicator on Protective actions that should be taken when leaving facility 5.8.4 NOTIFY TSC Dose Calculator or RPC when turnover is complete 5.8.5 Off -going TSC RP Radio Communicator SIGN OFF TSC Access Log. 5.8.6 In-coming TSC RP Radio Communicator SIGN IN TSC Access Log. 5.9 Event Termination (Information Use) 5.9.1 RETURN work area to a ready condition. 5.9.2 PARTICIPATE in emergency event debriefing. 5.9.3 FORWARD forms, logs, data, and other documentation to: x TSC Dose Calculator OR x A Drill controller 5.9.4 DIRECT Teams to fuel vehicle if less than 3/4 tank. END of Instructions

Enclosure 2 to PLA-8077, Page 297 of 560 TSC RP RADIO COMMUNICATOR EP-PS-134 Revision: 15 Page 22 of 23 Unit: 0 6.0 RECORDS x Calculation and Tracking Sheet for Estimated IodineThyroid CDE and TEDE Doses x Emergency Exposure Extension Request x Potassium Iodide (KI) Tracking Form x Survey Data Forms x All paper-based logs, data, calculation sheets and documented communications generated.

Enclosure 2 to PLA-8077, Page 298 of 560 TSC RP RADIO COMMUNICATOR Attachment A EP-PS-134 Revision: 15 Page 23 of 23 Unit: 0 Attachment A, TSC RP Radio Communicator Hard Card MAINTAIN a chronological event log for activities in this procedure including Directions for Field Team and OSCAR Monitoring of Airborne Releases (Section 5.5) 1 OBTAIN a visual display of plume path from TSC Dose Calculator EMPLOY Monitoring Strategy based on met conditions and field teams availability IF Release in Progress is declared, DIRECT OSCAR to periodically obtain an air sample, COUNT the cartridge in a low background area AND RECORD and COMMUNICATE air sample and FMT gamma survey result(s) from plume traverses to TSC Dose Calculator / RPC TRACK AND MANAGE FMTs exposure Every 15 to 30 minutes, RECORD team members ED readings IF FMT readings exceed limits in Field Measurement Guidelines Table, IMMEDIATELY INFORM TSC Dose Calculator / RPC IF conditions are met, IMMEDIATELY NOTIFY TSC Dose Calculator / RPC, TRACK FMTs Whole Body (EDE) and Thyroid CDE AND DIRECT teams to use effective exposure control measures CALL OUT and ROTATE teams, as appropriate, OR NOTIFY TSC Dose Calculator or RPC of need for dose extensions, if appropriate IF conditions are met, COMMUNICATE FMT members to take KI NOTIFY RPC AND REVIEW RWPs for FMTs, if necessary PARTICIPATE in Dose assessment staff briefings IF requested by RPC, DIRECT Field Teams to perform notification of evacuation REPEAT steps in this section until release is terminated or field team direction is transferred to EOF FTD FORM EP-PS-134-1 Rev. 6, Page 1 of 1

Enclosure 2 to PLA-8077, Page 299 of 560 NEP DUTY PLANNER EP-PS-210 Revision: 29 Page 8 of 20 Unit: 0 5.2.15 (continued)

b. IF EOF Support Office is NOT ready THEN COMPLETE the following:

(1) ENSURE VHF Radio is on. (2) ENSURE EOF Public Address is working, including a test of the microphone. (3) ENSURE Plant Process Computer operability, (4) IF equipment is NOT operable THEN CONTACT EOF Facility Manager or ISD. 5.2.16 ENSURE Dose Assessment Area is ready as follows:

a. CHECK status of Dose Assessment Area with x Dose Assessment Supervisor OR x Dose Assessment Staffer

b. IF Dose Assessment Area is NOT ready THEN COMPLETE the following:

(1) ENSURE VHF Radio is on. (2) ENSURE two MIDASURI terminals (SDS computer and monitors) are operating AND associated printers areprinter is on-line with sufficient paper. (3) ENSURE Network PC is operating. (4) ENSURE Plant Process Computer operability, (5) IF equipment is NOT operable THEN CONTACT EOF Facility Manager OR ISD.

Enclosure 2 to PLA-8077, Page 300 of 560 NEP DUTY PLANNER EP-PS-210 Revision: 29 Page 9 of 20 Unit: 0 5.2.17 ENSURE Engineering Area is ready as follows:

a. CHECK status of Engineering Area with x Engineering Supervisor OR x Engineering Personnel

b. IF Engineering Area is NOT ready THEN COMPLETE the following:

x ENSURE Network PCs are operating. x ENSURE at least one Plant Process Computer terminal is monitoring the affected unit. x ENSURE associated printer is on-line with sufficient paper. x ENSURE Fuel Damage computer and associated printer on line with sufficient printer paper available. x IF equipment is NOT operable THEN CONTACT EOF Facility Manager OR ISD. 5.2.18 OBTAIN following forms from EP-PS-001, Emergency Planning Forms and Supplementary Instructions x Emergency Response Data System (ERDS) Operating Instructions (EP-PS-001-33 form) x Logkeeping Instructions and Paper Log Forms (EP-PS-001-40 form) 5.2.19 ENSURE Emergency Response Data System (ERDS) has been activated utilizing Emergency Response Data System (ERDS) Operating Instructions. 5.2.20 CONSIDER obtaining an individual from ISD to be stationed in the EOF during the duration of the emergency to troubleshoot equipment issues. 5.2.21 INITIATE a chronological event log using Logkeeping Instructions and Paper Log Forms in EP-PS-001 5.2.22 GO to Step 5.6

Enclosure 2 to PLA-8077, Page 301 of 560 NEP DUTY PLANNER EP-PS-210 Revision: 29 Page 10 of 20 Unit: 0 5.3 OSC Facility Setup 5.3.1 ASSEMBLE all non-essential personnel currently in the OSC. x Non-Emergency Response Organization (ERO) Personnel x Non company Personnel x Contract Personnel 5.3.2 INFORM them that an emergency has been declared at Susquehanna. 5.3.3 REQUEST the non-essential personnel leave the facility due to it being activated in support of emergency event. 5.3.4 SIGN IN on OSC Ingress/Egress log. 5.3.5 OBTAIN position specific badge. 5.3.6 NOTIFY OSC Coordinator of arrival. 5.3.7 ENSURE OSC is ready as follows: x ENSURE Network PCs are operating. x ENSURE at least one Plant Process Computer terminal is monitoring the affected unit. x ENSURE adequate supplies (including headsets) are available. x ENSURE associated printer is on-line with sufficient paper. x ENSURE OSC Radio is turned on AND Operable x IF OSC Radio is NOT operable THEN ENSURE portable radios are operable. 5.3.8 OBTAIN Logkeeping Instructions and Paper Log Forms (EP-PS-001-40 form) from EP-PS-001, Emergency Planning Forms and Supplementary Instructions 5.3.9 ASSIST OSC Coordinator with ensuring responders sign-in on OSC Access Log. 5.3.10 INITIATE a chronological event log using Logkeeping Instructions and Paper Log Forms in EP-PS-001.

Enclosure 2 to PLA-8077, Page 302 of 560 NEP DUTY PLANNER EP-PS-210 Revision: 29 Page 11 of 20 Unit: 0 5.4 TSC Facility Setup 5.4.1 ASSEMBLE all non-essential personnel currently in the TSC. x Non-Emergency Response Organization (ERO) Personnel x Non company Personnel x Contract Personnel

a. INFORM them that an emergency has been declared at Susquehanna.

b. REQUEST the non-essential personnel leave the facility due to it being activated in support of emergency event.

5.4.2 SIGN IN on TSC Ingress/Egress log. 5.4.3 OBTAIN position specific badge. 5.4.4 SIGN IN on TSC Organization Board. 5.4.5 NOTIFY TSC Emergency Director of arrival. 5.4.6 ENSURE TSC is ready as follows:

a. ENSURE VHF Radio is on.

b. ENSURE MIDASURI terminals (SDS computer and monitors) are operating AND associated printers areprinter is on-line with sufficient paper.

c. ENSURE Network PCS are operating.

d. ENSURE x Plant Process Computer is operational, x Terminals are monitoring affected unit x Associated printers are on-line with sufficient paper.

e. ENSURE TSC display monitors are operating

f. IF equipment is NOT operable THEN CONTACT Facility Manager or ISD 5.4.7 OBTAIN Logkeeping Instructions and Paper Log Forms (EP-PS-001-40 form) from EP-PS-001, Emergency Planning Forms and Supplementary Instructions 5.4.8 INITIATE a chronological event log using Logkeeping Instructions and Paper Log Forms in EP-PS-001.

Enclosure 2 to PLA-8077, Page 303 of 560 NEP DUTY PLANNER EP-PS-210 Revision: 29 Page 12 of 20 Unit: 0 5.5 OSC/TSC Responsibilities After Facility Activation 5.5.1 MAINTAIN a chronological event log using Logkeeping instructions and Paper Log Forms in EP-PS-001. 5.5.2 ESTABLISH communications with EP Staff members in other facilities by calling into the EP Conference bridge. 5.5.3 ASSIST ERO responders with using WebEOC Instance at SSES (WIS) 5.5.4 ASSIST ERO responders with facility/equipment/procedure issues 5.5.5 ENSURE information on current event status is displayed throughout OSC (using WIS and Smartboards, or maintained with whiteboards if WIS is unavailable) 5.5.6 ASSIST OSC Coordinator/Emergency Director with emergency as required

Enclosure 2 to PLA-8077, Page 304 of 560 NEP DUTY PLANNER EP-PS-210 Revision: 29 Page 14 of 20 Unit: 0 5.6.5 ASSIST ERO responders with facility/equipment/procedure issues 5.6.6 ASSIST EOF Recovery Manager with emergency as required 5.6.7 IF an individual is not Fit-For Duty OR Recovery Manger requests an individual be tested for Fit-For-Duty THEN CONTACT APF to schedule individual for Fit-For-Duty Testing

a. COORDINATE transportation for individual to the APF for testing.

5.6.8 MAINTAIN a chronological event log using Logkeeping instructions and Paper Log Forms in EP-Ps-001. 5.7 EOF Security NOTE NEP Duty Planner may delegate EOF security point of contact duties to Support Services Manager. 5.7.1 ACT as a point of contact for contract security personnel that will be posted throughout EOF. 5.7.2 REVIEW Attachment A, EOF Floor Plan. NOTE Proper Identification for entry in the EOF is: x Company issued identification x NRC issued identification x PEMA issued identification x FEMA issued identification x Other Federal Government issued identification 5.7.3 For events that are NOT expected to generate much public interest, such as most Unusual Events and Alerts, CONSIDER posting three around-the-clock security personnel with the following assigned duties:

a. Post #2: Main Lobby adjacent to Reception Desk.

(1) With the receptionist VERIFY individuals have proper identification. (2) ISSUE Visitor Badge to non-company authorized personnel (3) IF other individuals request access THEN CONTACT EOF Facilities Manager for authorization.

Enclosure 2 to PLA-8077, Page 305 of 560 RADIOLOGICAL MONITORING TEAM EP-PS-222 Revision: 32 Page 11 of 37 Unit: 0 5.2.4 PERFORM source check as follows:

a. IF at West Building, THEN OPEN source safe by performing the following:

(1) TURN safe dial to 0. (2) TURN safe dial counterclockwise three times past 0 to 71. (3) TURN safe dial clockwise one full turn past 71 to 24. (4) TURN safe dial counterclockwise to 46. (5) ALIGN red dot on lockthe key vertical with roundthe bump on key and INSERTthe key facing upwards. (6) TURN key to right to open safe. (7) GO TO Step 5.2.4c.

b. IF at EOF, THEN OPEN source safe by performing the following:

(1) PLACE safe dial to 0. (2) TURN safe dial clockwise three times past 0 to 37. (3) TURN safe dial counterclockwise one full turn past 37 to 4. (4) TURN safe dial clockwise to 70. (5) INSERT key into lock. (6) TURN key to right to open safe. CAUTION Handle the source block with extreme care. DO NOT TOUCH the radioactive source buttons that are embedded in the Plexiglass.

c. Handling source block by the plexiglass, MOVE source block from safe to work table.

(1) WHEN source block is out of safe, THEN (a) MAINTAIN line-of-sight control,

Enclosure 2 to PLA-8077, Page 306 of 560 RADIOLOGICAL MONITORING TEAM EP-PS-222 Revision: 32 Page 14 of 37 Unit: 0 5.3 Frisker Instrument Checkout (Information Use) NOTE A second frisker survey meter is available should the first instrument be out of calibration, fail its source check, or become inoperable. 5.3.1 CHECK instrument for Calibration Due Date.

a. IF calibration is past due, THEN CONTACT the TSC Radio Communicator or Field Team Director.

     . .__I----------~___.I WARNING I

AN ELECTRIC SHOCK MAY RESULT from touching damagedamaged cables. 5.3.2 INSPECT frisker cable for damage. CAUTION If directed by TSC Radio Communicator or Field Team Director to replace the cable, turn OFF the Radeye Survey MeterFrisker before removing the cable.

a. If cable is damaged, ENSURE UNIT IS OFF AND CONTACT TSC Radio Communicator or Field Team Director.

5.3.3 PERFORM battery check as follows:

a. ISOLATE 120 VAC power to frisker

b. UNPLUG power cord from frisker.

c. ENSURE frisker probe is connected to front of frisker unit.

d. PLACE ON/OFF switch to ON position.

e. PRESS red BAT TEST button.

f. OBSERVE meter deflects to BATT TEST region of scale.

g. IF meter does NOT deflect to BATT TEST region of scale, THEN CONTACT the TSC Radio Communicator or Field Team Director.

5.3.4 PERFORM response check as follows:

a. IF source block is locked in safe, THEN REFER to Steps 5.2.4a or 5.2.4b.

Enclosure 2 to PLA-8077, Page 307 of 560 RADIOLOGICAL MONITORING TEAM EP-PS-222 Revision: 32 Page 22 of 37 Unit: 0 5.6.5 (continued)

c. HOLD probe outside window, SLOW DOWN AND OBSERVE response of survey meter to detect edge of the plume.

d. IDENTIFY edge of plume boundary by using any of the following if available:

x GPS Coordinates x Nearest street address x Other landmarks

e. IF exposure ratehighest ED readings approach 800 mR/hr400 mrem, THEN (1) MOVE to a low dose rate area.

(2) NOTIFY TSC Radio Communicator or Field Team Director to start dose tracking activities.

f. TRAVERSE plume observing meter reading.

g. WHEN survey meters readout is highest, THEN STOP AND PARK vehicle in a safe configuration, off road as close to plume centerline as possible.

h. TURN flashers ON.

5.6.6 OBTAIN air sample.

a. ENSURE particulate filter and cartridge have been loaded onto sample head.

b. ENSURE sampler toggle switch is in OFF position.

c. REMOVE glove covering sample head.

(1) RETAIN glove to cover sample head after sample is completed.

d. ENSURE vehicle engine is running.

e. TURN ON inverter.

f. PLUG in air sampler.

Enclosure 2 to PLA-8077, Page 308 of 560 RADIOLOGICAL MONITORING TEAM EP-PS-222 Revision: 32 Page 26 of 37 Unit: 0 Step 5.6.30 (continued)

c. RECORD sample count rate in Cartridge column on Survey Data Form in EP-PS-001.

d. SUBTRACT background count rate from sample count rate to determine net count rate (corrected cpm, or ccpm).

(1) RECORD on Survey Data Form in EP-PS-001.

e. IF net count rate of a silver zeolite cartridge is equal to or greater than 7,5004,000 ccpm (based on an air sample volume of 20 ft 3),

THEN NOTIFY TSC Radio Communicator or Field Team Director to start dose tracking for thyroid CDE. 5.6.31 DETERMINE particulate filter count rate.

a. HOLD frisker probe in contact with bagged filter.

(1) COUNT particulate filter on the side with the marking.

b. OBSERVE meter for approximately 30 seconds AND DETERMINE average count rate.

c. RECORD sample count rate in Particulate column on Survey Data Form in EP-PS-001.

d. SUBTRACT background count rate from sample count rate to determine net count rate.

(1) RECORD on Survey Data Form in EP-PS-001. 5.6.32 RECORD team member dose data from ED on the Survey Data Form in EP-PS-001. 5.6.33 TRANSMIT sample and exposure information recorded on Survey Data Form to TSC Radio Communicator or Field Team Director. 5.6.34 PLACE small plastic bags containing cartridge, particulate samples, and completed Survey Data Form in EP-PS-001 into large bag with RADIOACTIVE MATERIAL sticker. 5.6.35 RETAIN samples for future analysis. 5.6.36 PLACE potentially contaminated items (e.g., gloves) in large RADIOACTIVE MATERIAL trash bag.

Enclosure 2 to PLA-8077, Page 309 of 560 RADIOLOGICAL MONITORING TEAM EP-PS-222 Revision: 32 Page 30 of 37 Unit: 0 5.8.10 PERFORM instrument checkout.

a. IF instrument checkout was not performed OR IF it is unknown if instrument checkout was performed, THEN (1) REFER TO Step 5.2 to perform RadEye Survey Meter Instrument checkout.

(2) REFER TO Step 5.3 to perform Frisker instrument checkout. (3) REFER TO Step 5.4 to perform Air Sampler Instrument checkout.

b. REFER TO Step 5.5 to prepare for deployment.

5.8.11 MAINTAIN a chronological event log of activities performed on the paper form in Logkeeping Instructions and Paper Log Form in EP-PS-001. 5.9 Field Monitoring of Environmental Sample Location (Information Use) 5.9.1 DISCUSS travel route with Environmental Sample Director/Field Team Director. 5.9.2 Upon arrival near the monitoring location, PERFORM general area dose rate survey to determine the best travel path to the monitoring location.

a. DON protective clothing.

b. PERFORM frisker survey with probe held at waist level.

c. IF frisker readings are greater than 300 ccpmcpm, THEN NOTIFY Environmental Sample Director/Field Team Director.

5.9.3 NOTIFY Environmental Sample Director/Field Team Director when samples have been collected. 5.9.4 Before entering vehicle, REMOVE AND BAG protective clothing and potentially contaminated sampling equipment. 5.9.5 WHEN directed by Environmental Sample Director/Field Team Director, THEN PROCEED to designated County or company Facility to drop off samples. 5.9.6 MAINTAIN a chronological event log of activities performed on the paper form in Logkeeping Instructions and Paper Log Form in EP-PS-001. 5.10 Sample Transport Courier (Information Use) 5.10.1 REFER TO Sample Transport Courier Instructions in EP-PS-001.

Enclosure 2 to PLA-8077, Page 310 of 560 RADIOLOGICAL MONITORING TEAM Attachment A EP-PS-222 Revision: 32 Page 34 of 37 Unit: 0 Attachment A, Emergency Monitoring Team Hard Card D MAINTAIN a chronological event log for activities in this procedure including Field Team Monitoring (Section 5.6) D OBTAIN briefing from the TSC Radio Communicator or Field Team Director. D ESTABLISH monitoring location(s), tasks to be performed, expected dose rates, etc D DETERMINE travel route to assigned monitoring location staying out of plume as much as possible to minimize radiation exposure. D ESTABLISH team member responsibilities for radiation and air sample surveys. D REPORT to first monitoring location. D WHEN approaching suspected location of plume, DON protective clothing if necessary AND NOTIFY TSC Radio Communicator or FTD D CHARACTERIZE plume boundaries and centerline. D OBSERVE meter response for rising and maximum exposure rates during plume transverse. ID IF exposure ratehighest ED reading approach 800 mR/hr400 mrem, MOVE to a low dose rate area AND NOTIFY TSC Radio Communicator or FTD to start dose tracking activities. D STOP at plume centerline AND safely PULL OFF the road to collect air sample(s). D PERFORM radiation survey AND COLLECT air sample D COUNT air sample(s). D PROCEED to low background area to analyze samples. ID IF net count rate of a silver zeolite cartridge is equal to or greater than 7,5004,000 ccpm NOTIFY TSC Radio Communicator or FTD to start dose tracking for thyroid CDE D PREPARE sample bags AND UTILIZE sample labels to maintain proper sample identification. D DOCUMENT AND COMMUNICATE radiation survey results and air sample results. D DISPOSE of rad trash in bag with radioactive material label D PREPARE air sample head with new particulate filter and iodine cartridge. D NOTIFY TSC Radio Communicator or FTD team is ready for next assignment. FORM EP-PS-222-1 Rev. 6, Page 1 of 2

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Enclosure 2 to PLA-8077, Page 329 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 6 of 54 Unit: 0 1.0 PURPOSE AND SCOPE 1.1 Purpose 1.1.1 This procedure describes actions to be taken by the Emergency Operations Facility (EOF) Dose Assessment Supervisor (DASU) during an event at Susquehanna Steam Electric Station (SSES). 1.2 Scope 1.2.1 This procedure is used by DASU responder upon arriving at EOF until the termination of emergency event or until released by another DASU responder. 1.2.2 Sections 5.3 through 5.9 are cyclic and may be performed out of sequence. 1.2.3 Attachment A, Dose Assessment Supervisor Hard Card, may be used to perform placekeeping for reference-use sections in this procedure. It is laminated and therefore, it may be used to handle placekeeping of cyclic activities or placekeeping when DASU is in different reference-use sections of procedure at the same time. 1.2.4 Expectation is to complete procedure steps in a way that ensures continuous operation during time critical evolutions during emergencies or drills. 1.2.5 This procedure ensures that SSES commitments delineated in SSES Emergency Plan Section 6 and 7 and regulatory requirements in 10CFR50.47 and Attachment E are fulfilled.

2.0 REFERENCES

AND COMMITMENTS 2.1 Performance References 2.1.1 EP-00-003, Termination and Restoration 2.1.2 EP-PS-001, Emergency Planning Forms and Supplementary Instructions 2.1.3 EP-PS-221, Environmental Monitoring Team 2.1.4 EP-PS-248, Environmental Sampling Director 2.1.32.1.5 EP-RM-004, EAL Classification Bases 2.1.42.1.6 EP-RM-007, Emergency Telephone Instructions and Directory 2.1.7 EP-RM-009, SSES URI User Manual 2.2 Developmental References 2.2.1 Susquehanna Steam Electric Station (SSES) Emergency Plan 2.2.2 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants

Enclosure 2 to PLA-8077, Page 330 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 7 of 54 Unit: 0 2.2.3 EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA 400-R-92-001 May 1992) 2.2.4 FDA Guidance: "Accidental Radioactive Contamination of Human Food and Animal Feed and Recommendations for State and Local Governments." Federal Register, pages 47073-47083, October 22, 1982 2.2.5 ICRP Publication 28, The Principles and General Procedures for Handling Emergency and Accidental Exposures of Workers. International Commission on Radiation Protection. (1978) 2.2.6 IE Notice 83 28 2.2.7 NCRP Report 55, Protection of the Thyroid Gland in the Event of Releases of Radioiodine, National Council Radiation Protection and Measurements. (1977) 2.2.8 NUMARC Graded Response Study 2.2.9 Spray Pond Blowdown Water Outlet Flow Rate PLI 50258 (May 8, 1987) 2.2.10 10 CFR 20 Appendix B 2.2.11 Study of Travel Time and Mixing Characteristics for the Susquehanna River below the Susquehanna SES - SUTRON CORPORATION November 1985 2.2.12 NDAP-QA-0620, Conduct of Radiation Protection 2.2.13 NDAP-QA-1191, ALARA Program and Policy 2.2.14 CH-RM-001, Conduct of Radiological Environmental Monitoring Program 2.2.15 National Interim Primary Drinking Water Regulations, EPA 570/9 76 003 (U.S.) Environmental Protection Agency, Washington, D.C. 1976 2.2.16 BRP Technical Assessment of Protective Actions, Appendix 6, Annex E 2.2.17 EC-ENVR-1047, Protective Action Guides, (PAGs), for the Evaluation of Abnormal, Unusual, or Unplanned Liquid Releases to the Susquehanna River 2.2.18 Potassium Iodide as a Thyroid Blocking Agent in Radiation Emergencies, HHS/FDA Guidance, December 2001. 2.2.19 NEP Technical Basis #02-004 - Total Noble Gas to Iodine 131 and Total Noble Gas to Total Particulate Ratios for Use in MIDAS Evaluations Supporting SSES Emergency Plan 2.2.202.2.19 NEP Technical Basis #02-005 - Noble Gas Release Rate Limits for EALs 2.2.212.2.20 NEP Technical Basis #03-001 - Measured to Projected Ratio 2.2.22 NEP Technical Basis #04-001 - Start of Radiological Release

Enclosure 2 to PLA-8077, Page 331 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 8 of 54 Unit: 0 2.2.232.2.21 NEP Technical Basis #04-003 - Classification of Dose During Declared Emergency 2.2.242.2.22 NEP Technical Basis #04-004 - Rationale for Selection of Release Duration for Dose Assessments for Selected, Common Plant Conditions 2.2.25 EC-RADN-1002, MIDAS Source Term Calculation 2.2.23 NEP Technical Basis 16-001 - Frisker Response in Support of EAL Implementation and Determination of Release In Progress 2.2.24 NEP Technical Basis 23-001 - Unified RASCAL Interface Technical Design Description Version 3.7. 2.2.25 NEP Technical Basis 23-002 - Unified RASCAL Interface Requirements Specification, Susquehanna Site Annex Version 3.7 2.3 Commitments 2.3.1 None 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions 3.1.1 None 3.2 Limitations 3.2.1 None 4.0 PREREQUISITES AND INITIAL CONDITIONS 4.1 Prerequisites 4.1.1 L IF relieving an on-shift EOF Dose Assessment Supervisor, THEN OBTAIN a shift turnover from the current Dose Assessment Supervisor using shift turnover process described in Step 5.11. 4.2 Initial Conditions x An Emergency Plan entry has been declared x Facility has been precautionary staffed x An emergency tabletop, drill or exercise is being conducted

Enclosure 2 to PLA-8077, Page 332 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 9 of 54 Unit: 0 5.0 INSTRUCTIONS 5.1 Initial Actions (INFORMATION USE) 5.1.1 SIGN IN on EOF Ingress / Egress Log AND Organization Board. 5.1.2 NOTIFY Recovery Manager (RM) of arrival. NOTE

1. Steps 5.1.3 AND 5.1.4 are necessary to complete PRIOR TO EOF activation

2. Positions required for EOF activation are:

x DASU x Dose Assessment Staffer (DAST) x Field Team Director (FTD) x One Field Team on location and ready to be dispatched OR in the process of completing equipment setup in preparation for dispatch

3. If all other forms of phone communications are not available for a beyond design accident, a Satellite phone is available to use. Refer to EP-RM-007 for instructions on using the Satellite phone.

5.1.3 CONFIRM staff is ready to assume control of Dose Assessment including the following:

a. Prepared to perform AND evaluate dose calculations x MIDASDose assessment software operational x Plant System Server (PSS or R*Time) OR communications with TSC available

b. Prepared to assume control of field teams x Communications link established

c. Prepared to assume communications with DEP/BRP x Communications link available

d. IF staffing problems occur, THEN NOTIFY Administrative Assistant to call out additional offsite monitoring teams or Dose Assessment Staff.

5.1.4 WHEN staff is ready to assume control of Dose Assessment, THEN NOTIFY RM.

Enclosure 2 to PLA-8077, Page 333 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 10 of 54 Unit: 0 5.1.5 OBTAIN briefing from RM including the following: x Technical picture of plant conditions x Plant prognosis x Target Turnover time 5.1.6 OBTAIN following forms from EP-PS-001, Emergency Planning Forms and Supplementary Instructions: x Dose Assessment Data Gathering Form x Emergency Exposure Extension Request x Emergency Personnel Dose Assessment and Protective Action Guide x EOF Command And Control Briefing (Hard Card in EOF Command and Control area) x EOF Dose Assessment Shift Turnover Checklist x Event Status (white board in EOF Command and Control Area) x Field Team Monitoring Strategy Notes x Field to Projection Measurement Comparison Form x Logkeeping Instructions and Paper Log Form x Meteorological Data Acquisition Options x MIDAS Field to Projection Measurement Comparison Form x Potassium Iodide (KI) Tracking Form x Protective Action Recommendation (PAR) Determination (White Board in DA and EOF Command and Control areas) x Radiological Release Duration Guidance x Radiological Release in Progress Guidance (White Board in DA area) x Response Levels For Protective Action Guides (PAG) x Return of NERO Personnel x TSC/EOF Dose Assessment Flowchart (White board in DA area) x Vent MonitoringMonitor Data Acquisition

Enclosure 2 to PLA-8077, Page 334 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 12 of 54 Unit: 0 5.1.8 OBTAIN briefing from Technical Support Center (TSC) Radiation Protection Coordinator (RPC) including the following: x Open items. x Type(s) AND magnitude(s) of release(s). x Status of the emergency. x All Dose Assessments performed, if not already available. 5.1.9 PROVIDE briefing to Dose Assessment staff including accident status and current PARs.

a. REFER TO Attachment B, Dose Assessment Briefing Guidance.

b. ENSURE the following is obtained AND recorded on EOF Dose Assessment Shift Turnover Checklist in EP-PS-001:

x DASU information x MIDASDose assessment information from DAST x Field Team data from FTD

c. ENSURE DAST fills in the Dose Assessment Data Gathering Form.

Enclosure 2 to PLA-8077, Page 335 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 14 of 54 Unit: 0 NOTE Steps 5.3 to 5.11 AND their substeps may be performed in any order that ensures an I optimum and continuous

                       -       operation.

5.3 Data Collection [INFORMATION USE] NOTE For a General Emergency OR if release exceed limits in TSC/EOF Dose Assessment Flowchart in EP-PS-001, periodically means every 15 minutes. Otherwise approximately every 60 minutes is appropriate. 5.3.1 Periodically OBTAIN status of the following from Dose Assessment Staffer (DAST) AND Field Team Director (FTD): x MIDAS Dose Assessment Packages x Field Team results x Field team placement strategy x Radiation protection for field teams x Meteorological observations AND forecasts x Communications obstacles AND opportunities

a. WHEN information collected has potential for a classification OR PAR change, THEN REFER TO Steps 5.8 AND 5.9 respectively.

5.3.2 MAINTAIN awareness of plant status AND prognosis through discussions with one or more of the following: x Engineering Support Supervisor x Recovery Manager x Radiation Protection Coordinator 5.3.3 OBTAIN current weather AND weather forecast from FTD.

Enclosure 2 to PLA-8077, Page 336 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 16 of 54 Unit: 0 5.4 Support for Determination of Release in Progress due to Event [REFERENCE USE] NOTE Recovery Manager (RM) has the responsibility to declare a release in progress due to event. 5.4.1 ASSESS if there is a radiological release in progress due to event PER Radiological Release in Progress Guidance in EP-PS-001,

a. IF it is believed that an airborne radiological release is in progress THEN:

(1) OBTAIN CONSULT with Engineering concurrence AND ASK Engineering to characterize release on Engineering Dose Assessment Support Information Worksheet (2) With DAST AND Engineering, ESTABLISH at least the following: x Monitoredor EOF Technical Advisor OR Unmonitored x Filtered OR Unfiltered x If unfiltered, appropriate filtration ratios x Estimated Release duration PER Radiological Release Duration Guidance in EP-PS-001, and basis for this estimation IMMEDIATELY COMMUNICATE information AND RECOMMEND RM to declare an airborne radiological release in progress due to event

b. IF FTD reports, OR it is believed that a liquid radiological release is in progress due to event PER Radiological Release in Progress Guidance or Protective Action Recommendation (PAR) Determination (Liquid PAR chart) in EP-PS-001, THEN IMMEDIATELY COMMUNICATE information AND RECOMMEND RM to declare a liquid radiological release in progress due to event.

5.4.2 IF RM declares an airborne radiological release in progress due to event, THEN,

a. IF Engineering Dose Assessment Support Information Worksheet is not available, THEN ASK Engineering to characterize the release in accordance with Step 5.4.1a(1).

Enclosure 2 to PLA-8077, Page 337 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 17 of 54 Unit: 0 b.a. DIRECT DAST to initiate dose calculations in accordance with their procedures AND TSC/EOF Dose Assessment Flowchart in EP-PS-001. c.b. ENSURE EOF E-plan Communicator indicates airborne radiological release in progress AND the wind speed and direction from the appropriate meteorological tower (10 OR 60 m) on Emergency Notification Report (ENR) OR Follow-up Notification Report (FNR) form . d.c. PROVIDE information to DEP/BRP AND RPC. e.d. ENSURE OSCAR OR other Field Monitoring Teams (FMT), as appropriate, periodically perform radiation surveys AND collect air samples throughout release duration in support of EAL changes AND release characterization. f.e. DETERMINE appropriate radiological Emergency Classification using EP-RM-004, EAL Classification Bases, in accordance with step 5.8.

Enclosure 2 to PLA-8077, Page 338 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 18 of 54 Unit: 0 5.4.3 IF event is still in progress AND a airborne release in progress was previously declared, THEN ADVISE RM that release is terminated when:

a. Radiological Release in Progress Guidance in EP-PS-001 shows that No (Airborne) Release is in Progress AND

b. Emergency event is downgraded or terminated per EP-00-003.

AND

c. Any releases have been reduced to levels allowed by plant Technical Specifications AND are below TRM values.

5.4.4 IF RM declares a liquid radiological release in progress due to event, THEN

a. ENSURE EOF E-Plan Communicator indicates liquid radiological release in progress AND the 10 m met tower wind speed and direction on ENR OR FNR form.

(1) IF both airborne AND liquid releases are in progress, THEN USE the met tower applicable to the airborne release in progress. a.b. Using telephone numbers in EP-RM-007, Emergency Telephone Instructions and Directory, to NOTIFY Danville Water Authority of liquid release AND activation of SSES Emergency Plan. b.c. Using telephone numbers in EP-RM-007, NOTIFY DEP/BRP representative OR USE telephone numbers in EP-RM-007 to notifyin EOF OR DEP/BRP of liquid release. c.d. NOTIFY NRC (through EOF representative OR through HPN line in the TSC) that a liquid release has occurred. d.e. ENSURE FTD performs calculations to determine potential liquid PAR. (1) IF NO PAR is required from step 5.9.6a, THEN NOTIFY DEP/BRP AND NRC that NO liquid PAR is required.

e. ENSURE EOF E-Plan Communicator indicates liquid radiological release in progress on Emergency Notification Report (ENR) form.

Enclosure 2 to PLA-8077, Page 339 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 21 of 54 Unit: 0 5.5.3 EVALUATE data reliability NOTE x PSS displays provide information regarding various plant parameters. If PSS data turns to a white color, that information may be suspect or invalid and other sources of data should be sought. x White data may be normal and acceptable due to low OR no system flow in the vent stack monitor (Ex. If SBGT is operating, the affected RB vent release rate data becomes white due to no flow) OR may indicate a release exceeding the range of the instrument OR an indication of instrumentation OR computer interface problems. x Another source of data that may be available is SPDS data display via PSS SPDS Menu. It should be noted that not all PSS data points are available on SPDS. However, for those parameters that are available on both SPDS and PSS, SPDS may provide alternate source of required information. x If all PSS data sources become unavailable, i.e. both PSS and SPDS data displays turn to a white color, additional alternate data sources should be sought such as data availability via hard wired or independent data sources in control room or locally in the plant. x White vent data should be considered as a potential unmonitored release condition unless Engineering or Operations indicates otherwise.

a. IF low confidence (white) Plant System Sever (PSS or R*Time) data exists, THEN CONSULT with Engineering to determine if condition is normal (i.e.,

per design) AND if vent release rate data are valid from Engineering OR Dose Assessment perspective.

b. IF vent release rate and meteorological data is suspect, THEN (1) REQUEST Engineering to promptly pursue corrective actions (2) REQUEST TSC to communicate vent release rate data from Control Room OR local VERMS terminals, if available, PER Vent Monitor Data Acquisition in EP-PS-001.

(3) REQUEST RPC to obtain Chemistry vent sample data as often as possible AND DISCUSS alternate methods to obtain release data (e.g., HP air samples). (4) DIRECT DAST to use appropriate alternate data such as grab sample (vent, HP air samples) results, default noble gas to iodine/particulate ratios, OR noble gas to iodine ratios judged by Engineering to be consistent with current release rate conditions in affected unit(s) in Forward Calculation.

Enclosure 2 to PLA-8077, Page 340 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 22 of 54 Unit: 0 (a) USE vent sample data to verify previous URI dose assessment calculation PER TSC/EOF Dose Assessment Flowchart in EP-PS-001

Enclosure 2 to PLA-8077, Page 341 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 23 of 54 Unit: 0 5.5.3.b (continued) (4) IF vent data for the respective pathway is still not available, THEN DISCUSS with DAST to use alternate URI methods (other than monitored and field team) to complete required calculations PER the TSC/EOF Dose Assessment Flowchart in EP-PS-001. (5) ENSURE field monitoring teams (OSCAR) are taking air samples.

Enclosure 2 to PLA-8077, Page 342 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 24 of 54 Unit: 0 5.5.3.b (continued) (6) REPORT conditions as a potential unmonitored OR unfiltered release, until Chemistry sample or field team data are confirmed. (7) IF meteorological data is not reliable, THEN DIRECT FTD AND DAST to use alternate meteorological data PER Meteorological Data Acquisition Options in EP-PS-001, if necessary. NOTE Data is suspect if the NG/I-131 release rate ratio is less than 1,000 for a filtered release through a given vent. 5.5.4 CHECK if reported Iodine-131 release rates from Chemistry OR other analyses seem reasonable when compared with NG, for current plant conditions AND TAKE appropriate actions for additional dose assessment OR directing FMTs. NOTE Data is suspect if the NG/Particulates release rate ratio is less than 10,000 for a filtered release through a given vent. 5.5.5 CHECK if reported particulate release rates from Chemistry OR other analyses seem reasonable when compared with NG, for current plant conditions, AND TAKE appropriate actions for additional dose assessment OR directing FMTs. 5.5.6 ASSIST DAST in obtaining release characteristics AND pathways on Engineering Dose Assessment Support Information Worksheet from Engineering. 5.5.7 SUPPORT DAST to determine type of valid MIDAS dose calculation to be performed by consulting TSC/EOF Dose Assessment Flowchart in EP-PS-001. 5.5.85.5.4 IF aan airborne release in progress is declared, THEN

a. ENSURE OSCAR OR field monitoring teams (FMT), as appropriate, are taking air samples as often as possible.

(1) IF Oscar is NOT available, THEN ENSURE FMT A OR B is dispatched on OSCAR route PER Field Monitoring Team Strategy Notes in EP-PS-001.

Enclosure 2 to PLA-8077, Page 343 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 25 of 54 Unit: 0 5.5.8 (continued) NOTE A Forward calculation is the preferred choice for valid calculations unless the release is unmonitored, there are multiple sources (use Multiple Menu), OR a back calculation provides more conservative results.

b. ENSURE DAST performs at least one valid dose calculation.

(1) IF TRM limits shown in Note 41 of TSC/EOF Dose Assessment Flowchart in EP-PS-001 are exceeded, OR IF General Emergency is declared, THEN DIRECT AND SUPPORT DAST to perform MIDAS dose calculations every 15 minutes

Enclosure 2 to PLA-8077, Page 344 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 26 of 54 Unit: 0 5.5.5 ASSIST DAST in obtaining release characteristics AND pathways to be used in URI dose assessment calculation PER TSC/EOF Dose Assessment Flowchart in EP-PS-001. NOTE S.B. line in URI report and screen is equivalent with SSES EPB.

a. REVIEW input AND calculation results AND RECORD name, signature, date AND time the review was complete in the Review By field on the URI Dose Assessment report.

NOTE A valid calculation is to be used for EAL Classification, Initial PAR determination OR a PAR upgrade. 5.5.95.5.6 IMMEDIATELY INFORM RM on potential EAL AND PAR changes based on Dose Assessment results. 5.5.105.5.7 IF containment venting is needed as determined by Engineering or Control Room, THEN

a. ENSURE DAST performs a dose assessment for venting the containment PER TSC/EOF Dose Assessment Flowchart in EP-PS-001.

b. ENSURE dose assessment results are immediately communicated to:

(1) EOF Technical Advisor OR Shift Manager of affected unit for potential entries into EOP procedures; (2) RM

c. IF necessary THEN RECOMMEND to RM a PAR based on dose assessment results PER Step 5.9.

5.5.115.5.8 REVIEW measured/projected EDE OR CDE dose rate ratios AND TAKE appropriate actions for additional dose assessment OR directing field monitoring teamsFMTs PER instructions in MIDAS Field to Projection Measurement Comparison Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 345 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 27 of 54 Unit: 0 NOTE NG / Iodines and NG / Particulates release rate ratios are identical in URI and their ratios are shown in the URI dose assessment report. 5.5.9 CHECK if reported Iodine and Particulates release rates from Chemistry OR other analyses seem reasonable when compared with NG, for current plant conditions, AND TAKE appropriate actions for additional dose assessment or FMT repositioning. 5.5.125.5.10 ENSURE Dose Assessment resultsPackages are communicated to TSC AND to Offsite organizations (NRC, DEP/BRP) per their request. 5.5.135.5.11 MAINTAIN a chronological log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 346 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 28 of 54 Unit: 0 5.6 Field Monitoring Strategy [REFERENCE USE] 5.6.1 IF airborne release, THEN

a. DIRECT Field Team Director (FTD) to periodically collect air samples as needed throughout the release duration in support of EAL classification AND release characterization

b. REVIEW with FTD AND DAST changes that could impact Field Team placement strategy using Field Team Monitoring Strategy Notes in EP-PS-001.

NOTE Field Team Director is backup for OSC Chemistry Coordinator for liquid release calculations. 5.6.2 IF abnormal liquid release is indicated by FTD, THEN ENSURE liquid release sample results AND calculations are obtained from and reviewed by OSC Chemistry Coordinator OR are performed by FTD.

a. IF liquid release sample calculations indicate a liquid release, THEN PERFORM Step 5.4.1b AND, if necessary step 5.4.4.

5.6.3 With EOF Administrative Support staff AND Effluents Management, ASSIST FTD with radioactive materials transport at the following locations: x Onsite x County decontamination facility x Other mutually agreed upon site 5.6.4 IF known that other organizations are performing dose assessment or field monitoring, THEN REQUEST applicable data AND, if obtained, COMPARE it with own radiological data and analyses.

a. IF sample data is supplied by DEP/BRP or other organizations, THEN USE data ONLY to aid in assessing existing field team results or change field monitoring strategy.

Enclosure 2 to PLA-8077, Page 347 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 29 of 54 Unit: 0 5.6.5 For security related events, INSTRUCT FTD to:

a. TAKE control of OSCAR and Field Teams

b. CONTACT TSC Security Coordinator to establish the following:

(1) Team safety (2) Team security (3) Routes to take (4) Reporting suspicious activity (5) Contact information (6) Back out criteria

c. BRIEF field teams on information gathered in Step b.

5.6.6 MAINTAIN a chronological log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 348 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 30 of 54 Unit: 0 5.7 Emergency Personnel Protective Actions [REFERENCE USE] 5.7.1 ENSURE Field Monitoring Teams (FMT) are maintaining their exposure ALARA.

a. IF affected FMT ED exceeds 400 mrem OR NOTE An Adult Thyroid CDE rate of 1,000 mrem/hr (4,000 ccpm) would imply a CDE greater than 5 rem/shift assuming 50% affected area occupancy factor.

IF Cartridge Readings are greater than 4,000 ccpm, THEN ENSURE Field Team Director (FMT) initiated dose tracking AND is using effective exposure control measures for the appropriate Field Monitoring Team (FMT) a.b. IF feasible, THEN ENSURE teams are rotated, OR new teams are called out to minimize exposure AND MAINTAIN adult thyroid exposure under 10 rem CDE AND TEDE under 4 rem. b.c. Using Field Team Monitoring Strategy Notes in EP-PS-001 AND FTD input, EVALUATE risk of moving field team further away from plant vs. need for a reading in high radiation fields in determining whether an emergency dose extension is warranted for a field team, particularly for OSCAR.

c. ENSURE protective actions are established PER Emergency Personnel Dose Assessment and Protective Action Guide in EP-PS-001.

d. IF measured exposure rate exceeds 800 mR/h OR NOTE An Adult Thyroid CDE rate of 1,000 mrem/hr (7,500 ccpm) would imply a CDE greater than 5 rem/shift assuming 50 % affected area occupancy factor.

IF Cartridge Readings are greater than 7,500 ccpm, THEN ENSURE Field Team Director (FMT) initiated dose tracking AND is using effective exposure control measures for the appropriate Field Monitoring Team (FMT) 5.7.2 IF adult thyroid CDE is determined to be potentially greater than 10 rem, as reported by FTD,

Enclosure 2 to PLA-8077, Page 349 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 31 of 54 Unit: 0 OR a General Emergency with a release in progress is declared OR a General Emergency is declared and the release is imminent, THEN,

a. DIRECT FTD to fill in the names of affected FMT personnel on a Potassium Iodide (KI) Tracking Form in EP-PS-001 a.b. OBTAIN approval from RM for teams to use KI tablets on Potassium Iodide (KI) Tracking Form in EP-PS-001.

b.c. Once approval from RM is received, REQUEST FTD to recommend issuance of KI to field teams AND ENSURE teams are notified of precautions regarding interactions with other drugs using Emergency Personnel Dose Assessment and Protective Action GuidePER Potassium Iodide (KI) Tracking Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 350 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 32 of 54 Unit: 0 5.7.2 (continued) NOTE Consulting Radiological Physician contact information is in EP-RM-007. 5.7.3 IF assistance with KI issuance is required, THEN CONTACT Consulting Radiological Physician for input regarding the following: x Administration of subsequent doses of KI x Potential drug interaction x Cessation of KI intake NOTE RWP 8001 applies to OSCAR activities, RWP 8002 to Field Monitoring Teams activities and RWP 8888 is for drills and exercises. 5.7.4 Based on changing radiological conditions and with RPC, EVALUATE RWP revisions AND RECORD changes in log 5.7.5 Upon recommendation by FTD, IF estimated doses are greater than 4 rem TEDE OR 50 rem Adult Thyroid CDE, THEN

a. DIRECT FTD to fill in the names of affected FMT personnel on Emergency Exposure Extension Request form in EP-PS-001.

a.b. PROCESS AND OBTAIN RM approval on Emergency Exposure Extension Request form in EP-PS-001 for exposure extensions for field team personnel. b.c. Once approval from RM is received, REQUEST FTD to communicate new dose allowance AND applicable ALARA information on Emergency Exposure Extension Request form AND Emergency Personnel Dose Assessment and Protective Action Guide in EP-PS-001 to FMT personnel. 5.7.6 DIRECT FTD to ensure that bioassay for exposed field team members to determine actual internal exposure is performed PER section C in Emergency Personnel Dose Assessment and Protective Action GuideExposure Extension Request form in EP-PS-001. 5.7.7 MAINTAIN a chronological log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 351 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 33 of 54 Unit: 0 5.8 Support for Emergency Classification [REFERENCE USE] 5.8.1 EVALUATE available radiological airborne OR liquid release information. NOTE x Trending may involve evaluating the rate of change of measured data. For example, what is the rise or fall in CHRM exposure rates for a given unit of time (15 min, 30 min, etc.) x Radiological Emergency Classification triggers include ARM data in Table R, entry conditions in rows B and D in Table F and in CG1.1, CG1.2, EU1.1, SU4.1 and SU4.2 EALs 5.8.2 IF triggers for radiological emergency classification PER EP-RM-004 are met, THEN IMMEDIATELY RECOMMEND changes in classification to Recovery Manager (RM)

a. WHEN evaluating radiological data, THEN DETERMINE rate of change (trending), if possible, to assist with determining when an EAL upgrade (OR downgrade) may occur.

NOTE Control Room needs radiological data to evaluate entry conditions and action levels for EOP Procedures. For example, EO-000-105 procedureEOP procedures may require reactor SCRAM AND RPV control when an Alert based on radiological conditions is met, OR rapidemergency depressurization if a General Emergency based on radiological conditions is met. 5.8.3 IF following are met,

a. Conditions are trending towards an Alert declaration, an Alert is declared OR a concurrent EAL at Alert level is identified, all based on Table R in EP-RM-004, EAL Classification Bases.

OR

b. Conditions are trending towards a General Emergency declaration, a GE is declared OR a concurrent EAL at GE level is identified, all based on Table R in EP-RM-004, EAL Classification Bases.

THEN PROVIDE release and dose assessment information to EOF Technical Advisor to request Shift Manager to evaluate a potential entry into EO-000-105 procedure.

Enclosure 2 to PLA-8077, Page 352 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 34 of 54 Unit: 0 5.8.4 IF RM declares a change in Emergency Classification level, THEN

a. INFORM EOF E-Plan Communicator OR RM of the met tower (10 OR 60 m) used OR potentially used in a dose assessment calculation AND ENSURE the ENR form contains appropriate data on wind direction and speed.

a.b. COMMUNICATE informationclassification change to DEP/BRP. 5.8.5 MAINTAIN a chronological log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 353 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 35 of 54 Unit: 0 5.9 Support for Protective Action Recommendations [REFERENCE USE] 5.9.1 OBTAIN following data needed to assess magnitude and anticipated duration of offsite releases from DAST AND FTD: x Release rates AND trends x Prognosis for release AND continued release x In plant source terms AND leakage pathway(s) x Meteorological OR river flow data x Dose calculations x Field data x Plume direction AND affected sectors 5.9.2 Following a General Emergency declaration, RECOMMEND Initial Protective Action Recommendations (PAR) to RM PER Protective Action Recommendation Determination in EP-PS-001. NOTE PARs are evaluated by the Recovery Manager, Technical Advisor, Engineering Support Supervisor AND DASU in the EOF as well as by TSC AND CR key decision makers.

a. PROVIDE radiological input required to determine the appropriate protective actions using the following:

(1) Dose at Emergency Plan Boundary (EPB), 2 and 5 miles (2) Type of calculationRelease Pathway AND method OR field monitoring results used to estimate dose including key assumptions OR limitations. (3) Release height (10 OR 60 m) used in dose assessment calculations. 5.9.3 AFTER RM declares a PAR due to an airborne release or a PAR change, COMMUNICATE information to DEP/BRP and RPC

Enclosure 2 to PLA-8077, Page 354 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 36 of 54 Unit: 0 NOTE x Based on data availability completion of Step 1.1.1 may require more than 15 minutes. x When such data is available, PARs beyond 10-mile EPZ should be based on vent sample calculations OR verified field data. 5.9.4 EVALUATE if an airborne release PAR beyond 10 miles is appropriate. 5.9.55.9.4 IF 10001,000 mrem TEDE or 50005,000 mrem child Thyroid CDE is exceeded at 10 miles, THEN THEN EVALUATE if an airborne release PAR beyond 10 miles is appropriate.

a. DIRECT DAST to identify affected sectors AND associated distance downwind for which PAGs are exceeded.

NOTE URI does not provide for analysis beyond 50 miles for the filed team (back calculation) method.

b. IF PAR is based on a Back Calculation AND an Air Sample is NOT provided, THEN, DIRECT FTD to request applicable Field Team to obtain andata at the plume edge, including air samplesamples x ENSURE dose assessment is re-performed to include this information AND CHANGE OR VALIDATE previous PAR (1) IMMEDIATELY COMMUNICATE need to consider PARs beyond 10-mile EPZ to RM.

c. CONSULT with Engineering Support Supervisor, Operations to communicate the need to consider PARs beyond 10-mile AND Recovery Manager to verify dose projections are consistent with plant conditions.

Enclosure 2 to PLA-8077, Page 355 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 37 of 54 Unit: 0 5.9.4.a (continued)

d. ENSURE dose assessment is re-performed to include new information AND CHANGE OR VALIDATE previous PAR d.e. DISCUSS PAR beyond 10-mile EPZ with DAST, FTD, Engineering, Operations, RM AND State representatives, considering at least the following x Model uncertainty x Wind shifts x Methodology uncertainty with distance x Release characteristics x Plant status x Placement of FMT x Field data x Reanalysis of questionable data

Enclosure 2 to PLA-8077, Page 356 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 38 of 54 Unit: 0 5.9.4 (continued) e.f. IF an airborne release PAR beyond EPZ is confirmed, THEN IMMEDIATELY RECOMMEND to RM to issue a PAR beyond 10 miles in accordance with the PAR Determination flowchart in EP-PS-001. 5.9.65.9.5 Following initial PAR, CONTINUE to evaluate for PAR changes AND RECOMMEND revising airborne release PARs based on increasing dose levels OR wind shifts, in accordance with PAR Determination Flowchart in EP-PS-001.

a. INFORM RM if release height (10 OR 60 m) changes in dose calculation.

5.9.75.9.6 IF FTD identifies need for liquid release protective action recommendations, THEN:

a. With FTD, DETERMINE Liquid PAR PER Protective Action Recommendation Determination guidance (Liquid PAR chart) in EP-PS-001

b. IMMEDIATELY NOTIFY RM of potential Liquid PARs.

5.9.85.9.7 IF RM declares a Liquid PAR, THEN:

a. ENSURE EOF E-Plan Communicator indicates liquid PAR AND the 10 m met tower wind speed and direction on ENR.

(1) IF both airborne AND liquid releases are in progress, THEN USE the met tower applicable to the airborne release in progress on the ENR. a.b. Using phone numbers in EP-RM-007, NOTIFY DEP/BRP representative OR USE telephone numbers in EP-RM-007 to notify DEP/BRP by of liquid release PAR to divert drinking water at Danville. (1) DO NOT COMMUNICATE liquid PAR to Danville Water Authority b.c. NOTIFY NRC (through EOF representative OR through HPN line in TSC) that a liquid release PAR to divert drinking water at Danville was recommended to the State of Pa. c.d. COMMUNICATE liquid PAR to RPC. 5.9.95.9.8 MAINTAIN a chronological log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 357 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 39 of 54 Unit: 0 NOTE This section is applicable to the restoration efforts, when airborne radiological releases are under control AND SSES entered EP-00-003, Termination and Restoration, procedure. 5.10 Re-entry and Recovery [INFORMATION USE] NOTE Steps 5.10.1 through 5.10.4 may take several days to complete. 5.10.1 With DAST, DEVELOP a sequence of events AND ALL associated calculations performed by Control Room, TSC AND EOF during the entire event.

a. CHECK calculations for accuracy AND ENSURE calculations deemed to be incorrect are reperformed, if necessary.

NOTE URI saves the results and input files on both the C:/URI (local) and Y:/URI (network) drives on the SDS computers. 5.10.2 With DAST AND Computer Engineering, ENSURE ALL URI runs performed during the event by the Control Room, TSC AND EOF are saved on the Y drive as well as on a regular network folder. NOTE EP Dose Assessment and REMP Subject Matter Experts (SME) are more experienced and knowledgeable in performing URI Integrate Mode calculation 5.10.3 CONTACT additional support personnel AND ARRANGE for a meeting to discuss the sequence of events AND calculations performed. 5.10.4 ENSURE Integrated mode analysis in URI is performed to obtain expected environmental data PER Integrate Mode section in EP-RM-009, SSES URI User Manual.

a. EVALUATE results AND COLLABORATE with support personnel to update the post plume analysis, if necessary OR additional pertinent information is obtained.

Enclosure 2 to PLA-8077, Page 358 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 40 of 54 Unit: 0 5.10.15.10.5 With State and Federal radiological organizations, Environmental Sampling Director Environmental Sampling Teams AND DAST, DEVELOP environmental sampling plan.

a. CONSIDER including the following in environmental sampling plan:

x Environmental sampling - all media x Projected dose from ground contamination x TEDE AND Thyroid CDE plume plots from VALID dose assessments 5.10.6 ASSIST Environmental Sampling Director AND Environmental Sampling Teams in executing environmental monitoring PER EP-PS-221 and EP-PS-248 procedures. 5.10.25.10.7 COMPARE expected AND analyzed environmental data with Protective Action Guides (PAG) using Response Levels For Protective Action Guide, FDA AND EPA guidance in EP-PS-001. 5.10.35.10.8 COMPARE analyzed SSES data with data collected from other organizations (State AND Federal). 5.10.45.10.9 PROVIDE protective actions recommendations PER Response Levels For Protective Action Guides in EP-PS-001 to RM. NOTE The following step cannot be completed without performing an URI Integrate Mode analysis per Steps 5.10.1 through 5.10.4. 5.10.10 IF any off-site agency requests the population dose, THEN

a. OPEN SSES Population Dose Estimator.xls file from T:\SSES\Nuclear Emergency Planning folder AND SAVE it with a different name in an accessible network folder.

NOTE DO NOT MODIFY OR ENTER any values into any cells except in columns D, E, F, and H. (1) RESET the TEDE AND CDE Thyroid dose values to 0 in columns D AND E. (2) RESET the Zone Evacuation Status to all be Not Evacuated (1) in column F if not already set. (3) RESET the KI PAR parameter Status to all be More than 6 Hours AFTER exposure in column F.

Enclosure 2 to PLA-8077, Page 359 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 41 of 54 Unit: 0 5.10.10.a (continued) (4) From Integration dose assessment, DISPLAY the plume plot for TEDE AND ENSURE sure the plume plot is for the FINAL accumulation period. (5) CHOOSE the map radius that is most convenient for the distance being worked on (e.g. start with the 2 mile radius AND work your way up to the 5 mile map when attending to the 2 and 5 mile segments, etc). (6) SELECT the Show Balloon option from the Options Menu in the map. (7) Using the RASCAL result cell listed in column C for each zone, POINT the mouse pointer at the specified RASCAL result cell AND ENTER the TEDE value in the cell in column D for that zone. (a) REPEAT for all zones that show plume overlaying the zone. (8) REPEAT #7 using the CDE Thyroid plume plot, entering the CDE Thyroid values in column E. (9) For each zone with non-zero doses, SELECT the Zone Evacuation Status in column F based on the timing of evacuation (if any) for the dose accumulation for that zone. (a) In selecting the dropdown options, CONSIDER the START of Release, the plume TRAVEL TIME to the location of interest, AND the time of evacuation order. (b) USE only the drop down available options. (10) For each zone with non-zero doses, SELECT the KI PAR parameter Status in column H based on the timing of evacuation (if any) and the KI PAR issued for the dose accumulation for that zone. (a) In selecting the dropdown options, CONSIDER the START of Release, the plume TRAVEL TIME to the location of interest, the time of evacuation order AND the time of the KI PAR. (b) USE only the drop down available options.

b. DELIVER results to the requesting agency.

5.10.55.10.11 Using results AND actions from environmental efforts, ENSURE RM OR Restoration Manager is informed of results AND actions. 5.10.12 At all times, PARTICIPATE in ALL State or Federal radiological meetings AND INFORM participants on the SSES progress.

Enclosure 2 to PLA-8077, Page 360 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 42 of 54 Unit: 0 5.10.13 At all times, PARTICIPATE in ALL SSES Restoration meetings AND INFORM participants on the radiological group progress. 5.10.65.10.14 MAINTAIN a chronological log using Logkeeping Instructions and Paper Log Form in EP-PS-001. 5.11 Shift Turnover [INFORMATION USE] 5.11.1 REMAIN at duty station with full responsibility until properly relieved. 5.11.2 IF State has issued a Protective Action, THEN

a. REFER TO Return of NERO Personnel guidance in EP-PS-001 for returning personnel to EOF.

b. COORDINATE return of personnel to EOF with the Administrative Assistant.

5.11.3 ENSURE Dose Assessment staff provides briefings to replacement personnel AND RELAY pertinent information to their counterparts. 5.11.4 COMPLETE DASU section of EOF Dose Assessment Shift Takeover Checklist. 5.11.5 Using EOF Dose Assessment Shift Takeover Checklist AND an updated Dose Assessment Data Gathering Form in EP-PS-001, PERFORM a briefing for on-coming DASU(s) on the following using EOF Dose Assessment Shift Takeover Checklist: x Emergency status x PARs x Equipment status x Field Team deployment strategies x Urgent actions to perform AND place in procedure NOTE SSES badge and Dosimeters of Legal Records (DLR) are needed to return to site after State has issued a Protective Action recommendation. 5.11.6 ADVISE personnel to take SSES badge AND DLR when leaving facility.

a. IF FMT personnel doses were estimated to exceed 100 mrem for shift, THEN ENSURE DLR are processed.

Enclosure 2 to PLA-8077, Page 361 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 43 of 54 Unit: 0 5.11.7 NOTIFY off going staff of the following: x Protective actions that should be taken when leaving facility x Bioassay requirements for each individual. x Leaving their contact information with EOF Administrative Assistant 5.12 Event Termination [INFORMATION USE] 5.12.1 WHEN emergency is downgraded or terminated AND offsite teams are no longer needed, THEN ENSURE teams are recalled. 5.12.2 IF FMT personnel doses were estimated to exceed 100 mrem for shift, THEN ENSURE DLR are processed. 5.12.25.12.3 PARTICIPATE AND ENSURE Dose Assessment staff receives debriefing. 5.12.4 ENSURE Computer Engineering provides URI input / output data to NEP Department. 5.12.35.12.5 ENSURE the following dose assessment data is retained: x Signed, sequentially numbered, originals (OR copies, as necessary) of all Dose Summary Packages x Hard copy of picture of Status of Dose Calculations x Offsite survey AND sampling records x Personnel dosimetry records

a. FORWARD documentation to:

x EOF Administrative Assistant OR x A Drill controller 5.12.4 PROVIDE for backup of data on MIDAS.

a. ENSURE computer is NOT turned OFF until backup is verified.

5.12.55.12.6 RETURN work area to a ready condition. 5.12.61.1.1 IF FMT personnel doses were estimated to exceed 100 mrem for shift, THEN ENSURE DLR are processed.

Enclosure 2 to PLA-8077, Page 362 of 560 EOF DOSE ASSESSMENT SUPERVISOR EP-PS-245 Revision: 27 Page 45 of 54 Unit: 0 6.0 RECORDS NOTE All information entered in WebEOC Instance at SSES (WIS) is already saved for event reconstruction or critique. x EOF Dose Assessment Shift Turnover Checklist x Dose Assessment Summary Sheets x Engineering Dose Assessment Support Information Worksheet x MIDAS Field to Projection Measurement Comparison Form x NUREG 1228 Event Tree Parameters for Dose Assessment Reports x Potassium Iodide (KI) Tracking Form x Emergency Exposure Extension Request x All logs, data and documented communications generated

Enclosure 2 to PLA-8077, Page 363 of 560 EOF DOSE ASSESSMENT SUPERVISOR Attachment A EP-PS-245 Revision: 27 Page 46 of 54 Unit: 0 Attachment A, Dose Assessment Supervisor Hard Card MAINTAIN a chronological event log for activities in this procedure including: Support for Determination of Release in Progress due to Event (Section 5.4) ASSESS if there is a radiological release in progress IF believed anthat a airborne radiological release is in progress due to event OBTAIN concurrence AND ASK, CONSULT with EOF Tech Advisor or Engineering to characterize release OR IMMEDIATELY COMMUNICATE information AND RECOMMEND RMED to declare an airborne release in progress due to event IF FTD reports, OR it is believed that a liquid radiological release is in progress due to event, IMMEDIATELY COMMUNICATE information AND RECOMMEND RM to declare a liquid radiological release in progress due to event IF RM declares an airborne radiological release in progress due to event, IF not already performed, CHARACTERIZE release with Engineering support DIRECT Dose Assessment personnel to initiate dose calculations AND field monitoring ENSURE EOF E-Plan Communicator indicates an airborne release in progress AND appropriate wind speed and direction (10 OR 60 m met tower) on ENR OR FNR form PROVIDE information to DEP/BRP AND RPC. DIRECT FMTs (OSCAR) to periodically collect air samples throughout release duration IF applicable, DETERMINE appropriate radiological Emergency Classification AND OBTAIN concurrence from Engineering, ADVISE RM when airborne radiological release is terminated IF RM declares a liquid radiological release in progress due to event, ENSURE EOF E-Plan Communicator indicates liquid release in progress AND the 10 m met tower wind speed and direction on ENR or FNR form IF both liquid and airborne releases are in progress, USE the met tower applicable to the airborne release in progress NOTIFY Danville, DEP/BRP AND NRC of liquid release ENSURE FTD performs calculations to determine potential liquid PAR FORM EP-PS-245-1 Rev. 10, Page 1 of 7

Enclosure 2 to PLA-8077, Page 364 of 560 EOF DOSE ASSESSMENT SUPERVISOR Attachment A EP-PS-245 Revision: 27 Page 47 of 54 Unit: 0 ENSURE EOF E-Plan Communicator indicates liquid release in progress on ENR form DIRECT activation of Environmental teams to monitor for liquid releases FORM EP-PS-245-1 Rev. 10, Page 2 of 7

Enclosure 2 to PLA-8077, Page 365 of 560 EOF DOSE ASSESSMENT SUPERVISOR Attachment A EP-PS-245 Revision: 27 Page 48 of 54 Unit: 0 Dose Calculation Support (Section 5.5) 1 EVALUATE AND REVIEW available offsite AND onsite dataradiological conditions EVALUATE data reliability AND IMPLEMENT countermeasures if questionable data exists IF white data exists, with Engineering support, VALIDATE if condition is normal IF vent release rate OR meteorological data is suspect, REQUEST Engineering to promptly pursue corrective actions REQUEST TSC to communicate vent release rate data from Control Room OR local VERMS terminals, if available. REQUEST RPC to obtain or confirm Chemistry vent sample data AND DISCUSS alternate methods to obtain release data DIRECT DAST to use appropriate alternate data resultsmethods in Forwarddose assessment Calculation. ENSURE OSCAR is taking air samples Until confirmed otherwise, REPORT conditions as a potential unmonitored OR unfiltered release. DIRECT FTD and DAST to use alternate meteorological data, if necessary CHECK if NG/I-131 and NG/Particulates ratios reported by chemistry seem reasonable for plant conditions AND TAKE appropriate actions for additional dose assessment OR directing FMTs ASSIST DAST in obtaining release characteristics AND pathways from Engineering SUPPORT DAST to determine type of valid MIDAS dose calculation IF an airborne radioactive release has occurredis declared, ENSURE DAST performs one valid dose calculation IF site total release rates exceed TRM limits or GE is declared, DIRECT DAST to perform dose calculations every 15 minutes ASSIST DAST in determining the appropriate dose calculation to be run, REVIEW AND SIGN ON the calculation performed. IMMEDIATELY INFORM RM on potential EAL AND PAR changes based on Dose Assessment calculations FORM EP-PS-245-1 Rev. 10, Page 3 of 7

Enclosure 2 to PLA-8077, Page 366 of 560 EOF DOSE ASSESSMENT SUPERVISOR Attachment A EP-PS-245 Revision: 27 Page 49 of 54 Unit: 0 IF conditions are met, ENSURE DAST performs a dose assessment for containment venting, COMMUNICATE results to EOF Technical Advisor OR Shift Manager AND RM AND RECOMMEND RM a PAR, if necessary. CHECK if measured / projected exposure rate OR Thyroid CDE ratios OR reported NG/I or NG/Particulates release ratios seem reasonable for plant conditions AND, if necessary, TAKE actions for additional dose assessment OR directing FMTs ENSURE Dose assessment results are communicated to RPC AND if requested, to NRC, AND DEP/BRP. Field Monitoring Strategy (Section 5.6) For airborne releases, DIRECT FTD to periodically collect air samples throughout the release AND REVIEW with FTD AND DAST impact on Field Team placement strategy For liquid release, ENSURE liquid release samples and calculations are obtained and reviewed AND EVALUATE liquid PARs ASSIST FTD with radioactive materials transport REQUEST radiological data and analysis from other organizations for comparison AND, if sample data is supplied by DEP/BRP or other organizations, USE data ONLY to validate existing field team results OR change field monitoring strategy For security related events, DIRECT FTD to TAKE CONTROL of OSCAR AND Field Teams CONTACT TSC Security Coordinator to establish measures for Field Team security AND BRIEF teams accordingly Emergency Personnel Protective Actions (Section 5.7) ENSURE FMTs are maintaining their exposure ALARA, EVALUATE OSCAR risk AND, if exposure rateFMT ED exceeds 800 mR/h or400 mrem OR Iodine Cartridge Readings are greater than 7,5004,000 ccpm, ENSURE FTD initiated FMT exposure control. IF feasible, ENSURE teams are rotated, OR new teams are called out to minimize exposure AND MAINTAIN adult thyroid CDE under 10 rem / shiftAND TEDE under 4 rem IF adult thyroid CDE is determined to be potentially greater than 10 rem OR a GE with release in progress is declared or a GE is declared and the release is imminent, OBTAIN approval from RM for field monitoring team personnel to take KI tablets AND ENSURE personnel is notified of recommendation to take KI and other required precautions IF assistance with KI issuance is required, CONTACT Consulting Radiological Physician IF necessary, DISCUSS with RPC AND ENSURE changes to FMTs RWPs are implemented FORM EP-PS-245-1 Rev. 10, Page 4 of 7

Enclosure 2 to PLA-8077, Page 367 of 560 EOF DOSE ASSESSMENT SUPERVISOR Attachment A EP-PS-245 Revision: 27 Page 51 of 54 Unit: 0 Support for Emergency Classification (Section 5.8) EVALUATE available radiological airborne OR liquid release information MONITOR for radiological EAL changes AND, if necessary, IMMEDIATELY RECOMMEND potential classification changes to RM IF radiological conditions for an Alert or GE are approaching or declared OR a concurrent EAL at Alert OR GE level is identified, all based on radiological conditions, PROVIDE release AND dose assessment information to EOF Technical Advisor for SM evaluation of potential entry into EO-000-105. IF RM declares a change in classification level, change, INFORM EOF E-Plan Communicator OR RM of the met tower to use on the ENR, ENSURE ENR contains appropriate data on wind direction and speed, AND COMMUNICATE informationclassification change to DEP/BRP. Support for Protective Action Recommendations (Section 5.9) OBTAIN data needed to assess magnitude AND anticipated duration of offsite releases WHEN a GE is declared, RECOMMEND initial PAR to RM AND PROVIDE radiological input required to determine appropriate PAR, if necessaryincluding release height (10 OR 60 m met tower) WHEN RM declares a PAR due to an airborne release OR a PAR change, COMMUNICATE PAR to DEP/BRP AND RPC EVALUATE if a PAR beyond 10 miles is appropriate DIRECT Dose assessment staff to identify affected sectors IF PAR is based on a Back Calculation AND an Air Sample is not provided, ENSURE calculation is redone AND an air sample results is included, DIRECT FTD to obtain data at the plume edge, including air samples CONSULT with DAST, FMT, Engineering, Operations, RM AND State representatives for PAR issuance AND verification of dose projections IF required, RECOMMEND appropriate PAR to RM CONTINUE to evaluate for PAR changes AND RECOMMEND revising airborne release PARs based on increasing dose levels or wind shifts AND INFORM RM if release height (10 OR 60 m met tower) changes in dose calculation. IF liquid releases are identified, DETERMINE Liquid PAR AND NOTIFY RM of potential Liquid PAR if necessary IF RM declares a liquid PAR, COMMUNICATE PAR to DEP/BRP, NRC AND RPCENSURE the liquid PAR is checked AND appropriate met tower wind speed and direction are entered on the ENR form FORM EP-PS-245-1 Rev. 10, Page 6 of 7

Enclosure 2 to PLA-8077, Page 368 of 560 EOF DOSE ASSESSMENT SUPERVISOR Attachment A EP-PS-245 Revision: 27 Page 52 of 54 Unit: 0 COMMUNICATE liquid PAR to DEP/BRP, NRC AND RPC FORM EP-PS-245-1 Rev. 10, Page 7 of 7

Enclosure 2 to PLA-8077, Page 369 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 5 of 29 Unit: 0 1.0 PURPOSE AND SCOPE 1.1 Purpose 1.1.1 This procedure describes actions to be taken by the Field Team Director (FTD) in the Emergency Operations Facility (EOF) during an event at Susquehanna Steam Electric Station (SSES). 1.2 Scope 1.2.1 This procedure is used by the FTD upon arriving at EOF until the termination of the emergency event or until relieved by another FTD. 1.2.2 The FTD directs the emergency environmental field monitoring teams to determine the significance of airborne and liquid releases. 1.2.3 In the context of this procedure, when not specifically indicated as Field Monitoring Team (FMT) A or B, the term FMTs by itself includes OSCAR. 1.2.31.2.4 Attachment A, Field Team Director Hard Card, may be used to perform placekeeping for reference-use sections in this procedure. It is laminated and therefore, it may be used to handle placekeeping of cyclic activities or placekeeping in the situation the Field Team Director is in different reference-use sections of procedure at the same time. 1.2.5 Expectation is to complete procedure steps in a way that ensures continuous operation during time critical evolutions during emergencies or drills. 1.2.41.2.6 This procedure ensures that SSES commitments delineated in Emergency Plan Section 6 and 7, and regulatory requirements 10CFR50.47(b) and Appendix E are fulfilled. 1.2.51.1.1 Expectation is to complete procedure steps in a way that ensures continuous operation during time critical evolutions during emergencies or drills.

2.0 REFERENCES

AND COMMITMENTS 2.1 Performance References 2.1.1 EP-PS-001, Emergency Planning Forms and Supplementary Instructions 2.1.2 EP-PS-248, Environmental Sampling Director 2.1.3 EP-RM-007, Emergency Telephone Instructions and Directory 2.1.4 EP-00-005, Remote Assembly Area Contamination Control 2.2 Developmental References 2.2.1 SSES Emergency Plan 2.2.2 CH-RM-001, Conduct of Radiological Environmental Monitoring Program

Enclosure 2 to PLA-8077, Page 370 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 6 of 29 Unit: 0 2.2.3 EP-RM-004, EAL Classification Bases 2.2.4 EP-PS-108, RP Tech I OSCAR 2.2.5 EP-PS-222, Emergency Monitoring Teams 2.2.6 BRP Technical Assessment of Protective Actions, Appendix 6, Annex E 2.2.7 National Interim Primary Drinking Water Regulations, EPA 570/9 76 003 2.2.8 NUREG 0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2.2.9 NUREG 0696, Functional Criteria for Emergency Response Facilities 2.2.10 EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-400-R-92-001 May 1992) 2.2.11 10 CFR 20 Appendix B 2.2.12 Spray Pond Blowdown Water Outlet Flow Rate PLI 50258 (May 8, 1987) 2.2.13 Study of Travel Time and Mixing Characteristics for the Susquehanna River below the Susquehanna SES - SUTRON CORPORATION November 1985 2.2.14 Guidance Potassium Iodide as a Thyroid Blocking Agent in Radiation Emergencies, HHS/FDA, December 2001. 2.2.15 ICRP Publication 28, The Principles and General Procedures for Handling Emergency and Accidental Exposures of Workers. International Commission on Radiation Protection. (1978) 2.2.16 NCRP Report 55, Protection of the Thyroid Gland in the Event of Releases of Radioiodine, National Council Radiation Protection and Measurements. (1977) 2.2.17 NCRP Report 91, Recommendations on Limits for Exposure to Ionizing Radiation, National Council on Radiation Protection and Measurements. (1987) 2.2.18 NCRP Report 116, "Limitation of Exposure to Ionizing Radiation, National Council on Radiation Protection and Measurements." (1993) 2.2.19 NDAP-QA-1191, ALARA Program and Policy 2.2.20 NEP Technical Basis 16-001, Frisker Response in Support of EAL Implementation and Determination of Release In Progress 2.3 Commitments 2.3.1 None

Enclosure 2 to PLA-8077, Page 371 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 8 of 29 Unit: 0 5.0 INSTRUCTIONS 5.1 Initial Actions (Information Use) 5.1.1 SIGN IN on EOF Access Log and Organization board. 5.1.2 NOTIFY Dose Assessment Supervisor (DASU) of arrival. 5.1.3 PERFORM the following to meet Field Monitoring Team (FMT) activation criteria: NOTE x During a security event, TSC RP Radio Communicator and OSCAR may not be available. x FMT Radios may not work inside EMBC.

a. ESTABLISH communications with TSC RP Radio Communicator OR OSCAR OR a FMT via radio or phone.

b. CHECK if one FMT is available AND preparing for dispatch

c. NOTIFY DASU the FTD activation criteria has been met OR COMMUNICATE DASU or EOF Support Supervisor problems in meeting activation criteria.

NOTE Upon activation, it will take 30 minutes for OSCAR field team to complete equipment checks and clear the South Gatehouse. 5.1.4 IF OSCAR field team is not yet activated, THEN IMMEDIATELY CONTACT TSC RP Radio Communicator OR RPC AND REQUEST activation of OSCAR field team.

Enclosure 2 to PLA-8077, Page 372 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 9 of 29 Unit: 0 5.1.5 OBTAIN the following forms from EP-PS-001, Emergency Planning Forms and Supplementary Instructions: x Calculation and Tracking Sheet for Estimated IodineThyroid CDE and TEDE Doses x County Emergency Worker Decontamination Facility Locations x EOF Dose Assessment Shift Turnover Checklist x Emergency Exposure Extension Request x Emergency Personnel Dose Assessment and Protective Action Guide x Field Team Monitoring Strategy Notes x Logkeeping Instructions and Paper Log Form x Met/VentMeteorological Data Acquisition Instructions x Potassium Iodide (KI) Tracking Form x Protective Action Recommendation (PAR) Determination (laminated Liquid PAR on white board at FTD location) x Sample Transport Courier Instructions x SSES Environmental Sampling Strategy x Survey Data Form 5.1.6 INITIATE a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001. 5.1.7 OBTAIN the following information on history and current state of emergency from TSC RP Radio Communicator x Emergency classification x Whether a release has occurred or is occurring x Nature of release 5.1.8 DETERMINE sampling actions required using SSES Environmental Sampling Strategy Instructions in EP-PS-001.

a. IF a liquid release has occurred, THEN REFER TO Step 5.6.

Enclosure 2 to PLA-8077, Page 373 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 10 of 29 Unit: 0 5.1.9 OBTAIN wind direction, speed and atmospheric stability using R*Time computer OR Met/VentMeteorological Data Acquisition Instructions in EP-PS-001 5.1.10 OBTAIN current 3-day weather forecast using Met/VentMeteorological Data Acquisition Instructions in EP-PS-001. 5.1.11 COMPLETE FTD section of EOF Dose Assessment Shift Turnover Checklist in EP-PS-001 AND FORWARD to DASU. 5.1.12 PARTICIPATE in Dose assessment staff briefings. 5.1.13 IF notified that OSCAR van or FMT A Van at West Building FMT Van will NOT start OR is otherwise NOT functional, THEN DIRECT OSCAR RP Technician OR FMT, respectively, to perform alternate starting instructions per their procedure. NOTE Telephone numbers are in the EP-RM-007, Emergency Telephone Instructions and Directory.

a. IF van still does not start, THEN OBTAIN repairs or a replacement vehicle by performing the following:

(1) REQUEST a spare vehicle from TSC Security Coordinator. (2) IF a Security vehicle is NOT available, THEN CONTACT SSES garage AND REQUEST to (a) JUMPSTART van OR REPLACE battery. (b) IF van still does not start, THEN REQUEST a loaner vehicle, preferably with an AC inverter (c) IF SSES garage is NOT available during off hours, THEN REQUEST repairs or a spare vehicle from Field Services Emergency Dispatch.

b. WHEN a replacement van is obtained, THEN ENSURE manual air sampler and hand held instruments are loaded in vehicle

Enclosure 2 to PLA-8077, Page 374 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 12 of 29 Unit: 0 5.3 Taking Control of Field Monitoring Teams (Information Use) 5.3.1 OBTAIN a target time from DASU for taking control of Field Monitoring Teams (FMTs) NOTE During a security event the RP Radio Communicator and OSCAR may not be available. 5.3.2 During a Security event, immediately TAKE control of ALL FMTs, if available.

a. CONTACT TSC Security Coordinator to establish the following:

(1) Team safety (2) Team security (3) Routes to take (4) Reporting suspicion activity (5) Contact information (6) Back out criteria

b. OBTAIN approval from TSC Security Coordinator prior to dispatching FMTs.

5.3.3 OBTAIN AND RECORD the following information from TSC RP Radio Communicator OR individual FMTs: x FMTFMTs member name(s) x FMTFMTs member(s) initial dose (YTD) x FMTFMTs current dose extensions x FMTFMTs cell phone numbers x Sectors or locations monitored thus far by FMTs x Results for previously monitored locations by FMTs

Enclosure 2 to PLA-8077, Page 375 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 13 of 29 Unit: 0 5.3.4 ENSURE FMT members have signed in on correct RWP: x RWP 8001 - OSCAR FMT x RWP 8002 - ALPHA AND BRAVO FMTs x RWP 8888 - ALL for drills and exercises 5.3.5 COORDINATE turnover with TSC RP Radio Communicator. 5.3.6 PERFORM communications checks with ALL FMTs. 5.3.7 WHEN directed by DASU, THEN INFORM FMTs AND TSC RP Radio Communicator that all FMTs are now being directed by FTD. 5.3.8 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 376 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 14 of 29 Unit: 0 5.4 Field Monitoring Team Dispatch (Information Use)

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NOTE FMTs that have already beingbeen dispatched may be briefed via radio or cell I phone. 5.4.1 PERFORM FMT briefings including the following: x Event status. x Projected radiological conditions in field. x Field monitoring strategy, as determined in step 5.2, including sectors to be monitored and likely travel and traverse routes. x Radiological controls requirements listed on RWP AND in Field Team Monitoring Strategy Notes in EP-PS-001. x Potential communications issues listed in Field Team Monitoring Strategy Notes in EP-PS-001. x Potassium Iodide (KI) Protective Action guidance described in Emergency Personnel Dose Assessment and Protective Action GuidePotassium Iodide (KI) Tracking Form in EP-PS-001. x Safety considerations x Obeying traffic laws x Impact of forecast weather on road conditions x Hazards of driving at low speeds x Respecting private property boundaries x Security considerations obtained in Step 5.3.2, if applicable. 5.4.2 DISPATCH FMTs. 5.4.3 RECORD a summary of completed FMT briefing(s) in FTD Log. 5.4.4 PERFORM VHF Radio or Cell Phone operabilitycommunication check with each dispatched FMT.

Enclosure 2 to PLA-8077, Page 377 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 15 of 29 Unit: 0 NOTE Monitoring for radioactive airborne releases is a cyclical process that is repeated numerous times during the course of an event to initially locate the airborne plume(s), and then track the movement of the located plume(s). Consequently, the Flow Chart in the Field Team Monitoring Strategy Notes in EP-PS-001 is the most efficient procedural tool for the FTD to use when carrying out this cyclical monitoring process. Therefore, the flow chart steps are NOT reproduced in this section. 5.5 Directions for Field Monitoring Teams For Monitoring of Airborne Releases (Reference Use) 5.5.1 OBTAIN a visual display of plume path from DAST. 5.5.2 IMPLEMENT monitoring strategy established in Step 5.2 PER Field Team Monitoring Strategy Flowchart in Field Team Monitoring Strategy Notes in EP-PS-001 5.5.3 IF Release in Progress is declared, THEN

a. DIRECT FMTs (preferably OSCAR) to periodically obtain air sample, COUNT the air sample cartridge(s) in a low background area AND IMMEDIATELY COMMUNICATE the results.

b. RECORD field monitoring results on Survey Data Forms in EP-PS-001, MAKE a copy of the form for own record AND COMMUNICATE results of plume traverse and boundaries to DAST or DASU throughout the release duration or as directed by DAST or DASU.

5.5.4 TRACK AND MANAGE FMTs exposure PER Calculation and Tracking Sheet for Estimated IodineThyroid CDE and TEDE Doses form in EP-PS-001 AND following instructions.

a. Every 15 to 30 minutes, LOG each FMT ED readings.

b. IF FMTs report exposure rates / air sample cartridge readings exceed limits in Field Measurement Guidelines Table (white board from Field Team Monitoring Strategy Notes in EP-PS-001),

THEN IMMEDIATELY INFORM EOF Dose Calculator or DASU

Enclosure 2 to PLA-8077, Page 378 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 16 of 29 Unit: 0 5.5.4 (continued)

c. IF FMTs report any of the following conditions, x Exposure RatesED readings equal to or greater than 800 mR/hr400 mrem x Cartridge Readings greater than 7,5004,000 ccpm THEN (1) IMMEDIATELY NOTIFY DASU.

(2) START tracking FMT Whole Body (EDE) and Thyroid CDE per Calculation and Tracking Sheet for Estimated IodineThyroid CDE and TEDE Doses in EP-PS-001. (3) DIRECT FMT to use effective exposure control measures.

d. IF YTD exposure plus current ED readings are approaching 3800 mrem TEDE or 8,000 mrem Thyroid CDE, THEN (1) POSITION FMT in a low background area until further direction is received from DASU.

(2) IMMEDIATELY NOTIFY DASU that a dose extension ismay be required. (3) DO NOT SEND FMTaffected FMTs back through the plume without DASU approval. (4) IF other FMTs are available, THEN CALL OUT OR ROTATE FMTs to maintain TEDE less than 4,000 mrem or thyroid CDE less than 10,000 mrem or TEDE less than 4,000 mrem. (5) IF other FMTs are NOT available, THEN, in consultation with DASU, x PLACE FMT further away to minimize dose OR x PROCESS a dose extension using Emergency Exposure Extension Request and Emergency Personnel Dose Assessment and Protective Action Guide in EP-PS-001.

Enclosure 2 to PLA-8077, Page 379 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 17 of 29 Unit: 0 5.5.4 (continued)

e. IF thyroid CDE are determined to be potentially greater than 10,000 mrem OR a General Emergency with a release in progress is declared OR a General Emergency is declared and the release is imminent, as communicated by DASU, THEN (1) PROVIDE names of personnel requiring KI issue to DASU using Potassium Iodide (KI) Tracking Form in EP-PS-001.

(2) WHEN approved Potassium Iodide (KI) Tracking Form is received from DASU, THEN NOTIFY FMT personnel of recommendation to use KI including precautions regarding interactions with other drugs using Emergency Personnel Dose Assessment and Protective Action GuidePotassium Iodide (KI) Tracking Form in EP-PS-001. (3) TRACK issuance of KI using Potassium Iodide (KI) Tracking Form in EP-PS-001. (4) DIRECT FMTs to track use of KI in their Potassium Iodide (KI) Tracking Form in EP-PS-001.

f. REVIEW exposure control statements of RWP 8001 and RWP 8002.

(1) IF current radiological conditions require RWP revision, THEN NOTIFY DASU. 5.5.5 WHEN necessary, THEN ARRANGE for transport of air sample cartridges and filters to SSES site for additional analysis (e.g., cartridge and filter for gamma spectroscopy).

a. REQUEST courier(s), equipped with cell phone, from the EOF Support Supervisor.

b. BRIEF courier(s) PER Sample Transport Courier Instructions in EP-PS-001.

c. OBTAIN couriers cell phone number AND ESTABLISH a location for courier to meet at a predetermined location in an unaffected sector.

d. DIRECT FMTs to proceed to designated drop off location AND PROVIDE samples to couriers.

Enclosure 2 to PLA-8077, Page 380 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 19 of 29 Unit: 0 5.5.5 (continued)

f. COMMUNICATE to TSC RP Radio Communicator OR TSC Dose Calculator (1) Estimated time of arrival of courier at site (2) Need for sample analysis to be arranged (3) When available, results need to be communicated back to FTD

g. TRACK couriers dose AND ENSURE control of potentially contaminated material PER Sample Transport Courier Instructions in EP-PS-001.

5.5.6 IF requested by RPC, THEN DIRECT FMTs to perform notification of evacuation PER EP-PS-222, Emergency Monitoring Team. 5.5.7 PARTICIPATE in Dose assessment staff briefings 5.5.8 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001. 5.5.9 REPEAT steps in this section until release is terminated.

Enclosure 2 to PLA-8077, Page 381 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 23 of 29 Unit: 0 5.7 Field Monitoring Team Turnover and Termination (Information Use) NOTE

1. A turnover location should be established in a non-contaminated buffer zone in accordance with standard RP contamination control practices.

2. If personnel and resources are available, a non-contaminated company vehicle with a separate driver should transport the incoming FMT to the turnover location and transport the off-going FMT to a County Decontamination Facility.

5.7.1 IF FMT turnover is required, THEN with DASU DETERMINE turnover location in an unaffected sector.

a. DIRECT off-going FMT to proceed to turnover location AND NOTIFY FTD when turnover is complete.

b. For incoming FMT, REFER TO Step 5.4.

c. With DASU AND RPC, DETERMINE Countythe designated Decontamination Facility to be used by off-going FMTFMTs in accordance with EP-00-005 procedure OR PER County Emergency Worker Decontamination Facility Locations Instructionsin EP-PS-001.

d. WHEN notified FMT turnover is complete, THEN DIRECT off-going FMT to:

NOTE OSCAR FMT may return to the site Protected Area with the concurrence of the TSC Radiation Protection staff. (1) IMMEDIATELY PROCEED to one ofthe designated facilities in County Emergency Worker Decontamination Facility Locations Instructions in EP-PS-001for monitoring and decontamination. (2) WHEN monitoring and decontamination is complete, THEN DEBRIEF with EOF. 5.7.2 At termination of release, PERFORM the following:

a. With DASU AND RPC, DETERMINE one ofthe designated facilities Decontamination Facility to be used by FMTs in accordance with EP-00-005 procedure OR PER County Emergency Worker Decontamination Facility Locations Instructions in EP-PS-001.

Enclosure 2 to PLA-8077, Page 382 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 24 of 29 Unit: 0 5.7.2 (continued)

b. DIRECT FMTFMTs vehicles to the designated Decontamination Facility.

c. Upon vacating vehicle, DIRECT FMTs to lock up inside the vehicle any known or suspected radioactive waste generated during field monitoring activities (1) POST FMT vehicles as containing radioactive materials AND REPORT their location to FTD.

(2) NOTIFY station personnel to take custody of vehicle.

d. With TSC Radiation Protection staffRPC, DETERMINE OSCAR van disposition.

e. With RPC, In accordance with Emergency Exposure Extension Request form in EP-PS-001 AND with DASU and RPC, DETERMINE the need to perform bioassay for the FMT members.

(1) IF applicable, THEN ARRANGE for AND DIRECT FMT members to perform bioassay per Emergency Personnel Dose Assessment and Protective Action Guide in EP-PS-001at the designated location. e.f. Upon being decontaminated, DIRECT FMT to proceed to EOF for debriefing and to meet with environmental sampling personal to form unified monitoring teams. 5.7.3 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001. 5.7.35.7.4 NOTIFY DASU to have second FTD and Environmental Sampling Team (EST) personnel called out in preparation for transitioning to post release phase.

a. OBTAIN additional environmental sampling support through Environmental Lab personnel or other environmental sampling vendor.

NOTE Environmental Sampling Director may need to utilize EP-PS-247 and EP-PS-248 in the event of a simultaneous liquid and airborne release. 5.7.45.7.5 TRANSITION to EP-PS-248, Environmental Sampling Director. 5.7.51.1.1 MAINTAIN a chronological event log using Logkeeping Instructions and Paper Log Form in EP-PS-001.

Enclosure 2 to PLA-8077, Page 383 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 25 of 29 Unit: 0 5.8 Shift Turnover (Information Use) 5.8.1 With EOF Administrative Assistant, DEVELOP AND MAINTAIN schedules. 5.8.2 REMAIN at duty station with full responsibility until properly relieved. 5.8.3 COMPLETE FTD section of EOF Dose Assessment Shift Turnover Checklist in EP-PS-001. 5.8.4 PERFORM a briefing for on-coming FTD on the following Using EOF Dose Assessment Shift Turnover Checklist in EP-PS-001, BRIEF the on-coming FTD, including: x Emergency status x Communication AND FMT equipment status x FMT assignments x FMT deployment strategies x Individual bioassay requirements for field team members x Exposure control measures in effect (KI) x Impediments x Current step in procedure 5.8.5 With DASU, BRIEF off-going staff on Protective actions that should be taken when leaving facility. 5.8.6 NOTIFY DASU when turnover is complete. 5.8.7 Off -going FTD SIGN OFF EOF Access Log. 5.8.8 In-coming FTD SIGN IN EOF Access Log and Organization board. 5.9 Event Termination (Information Use) 5.9.1 RETURN work area to a ready condition. 5.9.2 PARTICIPATE in emergency event debriefing. 5.9.3 FORWARD forms, logs, data, and other documentation to: x DASU OR x A Drill controller

Enclosure 2 to PLA-8077, Page 384 of 560 FIELD TEAM DIRECTOR EP-PS-247 Revision: 22 Page 27 of 29 Unit: 0 6.0 RECORDS x Calculation and Tracking Sheet for Estimated IodineThyroid CDE and TEDE Doses x Emergency Exposure Extension Request x Liquid Discharge Data Sheets x Potassium Iodide (KI) Tracking Form x Survey Data Forms x All logs, data, and documented communications generated.

Enclosure 2 to PLA-8077, Page 385 of 560 (2)(19,5210(17$/6$03/,1*',5(&725 (336

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=-..::r"'dpooll,v<l1a~Ul.*-1h,10pdll,o U.a,myofl,,*<111<dlldln11toftB'UEUNGl'ATliWA.Y UNPLANNECl,...lorlo..Jdr~lnU..Rl:l'UalNGPATIM/,W IU.U j 1 j l f J I :1 j i I Q j,pg.~81 11lldco1<4byANYalll,ofdl/,n,ga, EllllEII. ~*II: ,FudPoolW.1orl.oJ,t""'1olrtm lll1n10<,lal.-.6atodfll<lre,i,t)jngln1rdo._.oal
~~Simllel"SUro<,Tonkl.ollt,,...iot.ttn~~
~~,adm.cnty , 1,1-i,:,bscrwt1onol1WUdl...idroi,bdCN1 ildpod ANO *lm!mcrfll'll*llnlrlnld~~
~~:::::=~~~~=:::J~ ;;::;:~~
~~MY*fU.of,u....... , ......... ~t.tln,lcdons:~~
~~Ob<<MU""or~otdr,lnlngdo,Jnl~*"'1>fcle ....lol AN~rmt,Y<<**l-"1~~
~~, Ch1mdH~lfudJ>adho10ll1c>lByl.la\l'°' IJNPlANNBlN<lnotQ!>dlda,l*Y<bUln-*db)'~~
~~c~1ootnRAI~ ANYa!!holdbo,lngradl,llanmordllri:~~
Cll1Md151!<1u=inuR""'h**1~'"lnlfhl

Chanod1Sl,cntFudP<idJ<utnU"Tfyl.lonltor

OlomdZR<lU<lhgR_.h .. l~**mRtt)

ChmndlSR<fll~Flo>a'>n,1

Chomd7U.ll114'11Uiit:l!Sp<rUFudPactNU

Ch*nndlR*fll~Fkxrh ..
~~ClllcdlJUanloti>100rnR.hrt~~
C!uimdSRofiloliogRoor}lghRonu*Ua1llir r......1o1 RuJit I 1 I* i

i" In j,pa,101
~~~ol-"11.. tN,lpoolbOd1:>~tOll.1bc>hthtq,0(1II, lfanlllld1><ko R.U1j1 j , i l j~~
j " iBl 1 *11-7 1 c.:"]:£.;:~~~=,~*~*****r.

B<thU..C*Jtlral.ObrmSl>i<<1[C"'5iMdS<<ood ,Y
.<lorm.!Ul..,!SASI MJ,1 ,~* j "*Li } f 4 j S j --,,j,~g.7S) h,UN?\.ANNED......,l"""'ll*li1-l....i.lh11 prd>b~<tlMPEDE cc=toAIIVTobl~R-::!.""""'<6 .,..,.1Na10S,Ncg6J Nol* 1: Tho ED/RM shoul:l dcdlro the nwntp1ampll)' upon do~rmlnlng 1,attlmo r1mlthas bol!JI **ccl>dcd, ar willikelybcc*cccded Nato2:lron0ngaJngu,leaoolsd*i."""dandlll0releaH,t11tUmelsunbiav,n,a*umolhatlhcrclc:i,.,
duratianhasaceededlhosp,,cifiedt.,,..limit N<1le 3: II th<! efflucnlllowpuhn offluentmonllarb k""""' lnhava olDppod, lndl<aldng lhattt.. releuo l"'lh b lo.alat=d,lhccffllJ"'111'11Cnl1<>rtQdlngJoNOlangcrVAUOforclau!flcadonpLlflla..,_,; Nale~: Th* F"'"'-'lculall!ld offlucntmonUarvalues pr=n!ed In EAL,; RA1.1, RS1.t and RG1.1 ,hould bo u.ed to1cmotgl!Jli,yc:t.usifio:i.tlcnuo*u;ll'&IIU.Unttllhoresuhs1n>mad0**a.., ... monlUAingai:llr:II
~~! lf1)RHRSWM! ~R-tl12-1(11Roll5 mdcDrokiwaroaawilab!,,.~~
~~Nol* S: lrlhc cqulpmontln th listed ream ara,o.awas aln,ady Inoperable or wt-okcivloc before the l!l!SW RR-D1~1(J.1Ri0l~~
~~!::~i::'~L":~:t~*n CV<tntoc,:urn,d,lhennacmorgonoycla.ss!flcatlcnlswarranted Nola s: Ith* initiating ov*n~ wt,fd1 Ii cau,lng el~atad radla~on 1.,,.1,;,~~
Chart 1 - Pi ant Area Key Plan Susquehanna o::J o::J IT] CO IT] FannEP-RM-GIJ.4..R IT] Rev.5.Pagc1oft Modes: Nuclear, LLC p......,rOpot.11lo<,1 Storhlp Hotstuitdown ColdShutd"""' Refu.Ung Octu.lod ALL CONDITIONS FORM EP-RM-004-R, Rev. 5, Page 1 of 1
Enclosure 2 to PLA-8077, Page 444 of560 Attachment4 EP-RM-004 Revision 21 Page 289 of 301 0o1.0~Ua'IQB<:llolm&an:ia9YlnliQJesclo£U,
>1Dn,"""TEUEcr5Dm"""ddldl1¥11h!CCE1lor eo.. a55...rnont udflll <Ulll nu,turdogy ~ul<:alts b..,-a,~U,eElileROOICVPLAN BOUNDARY dcses>100mn,,nTEOE,r500mo:md,14""'°1dCOE (Halo!) .tl<Jrb<'JOl>dlhoEI.IERGENCVPL\IJBOUmlMiY l!A1.~ j l j 1 j ;\ j i j S j Q j,Pg.!:I) ~,~,~,~,~,~,~,~,~,~,~1 (Not.~\
~~Rsu~,~, !pg.~l Fiold~ro<111Glndh::atoBTHERalflefolO'lllnga1or bey<ndlhoEIAERGENCVPUNBOUND.lRY:~~
* ~=ttr,~~!,."!:'=n I.CWmRklro,poaod * ~::O"'r;"':::~> 1oomR11ro>1>...tedto * ""3tJHSOl1okl!Ul\""f<ll!'pleslncJ<aUlchlld u.,tt,ldCCE>5.llDOffllllln!tr60mln.ollmUlbll. .Ar,.otvsc,,olOcld~umple,lndl:alochid (Nalos1,2j lhyro/dCOE>l:OOmtemforl;Om!n.ofhhol,.Oon, (Notoal,l\
~~Rn1j l j 1 f;, j~~
j S j Q jfpg.1-1) R,U.1j 1 j 7 I a j

j 5 j p jrag.H) RUJ..1 j l j 2 j ii j 1 j 5 i Q j{p!f,72J Si,ri~olpcooll..dcANNOT~~KE"1'<>ftEDto,1l..so.5i. i...-!ogal<ponlll<!pocll ..... l*~D.H.,!..,.Jh,t.,,afll,o l.11-.iyo!lrrodlok:ofll<llilh<REFUEUNGPATttNAV UNPLW'lEDwo1orlo\lllldn,plnU.oRERJEUNGPATHNAV
...............1.... 'l'<Nu,j1,d"b::.60nolr,.{N,,U,1} .. ,,,u.1 ..m RAl.2 j j j 7 f ? j 4 j /i j Q j,nJl.6&) .. 1ndkwdlr)'AHYOff101alaoingoosntE11un.lt
FldPodl'.llluL<ntLe,,,,ia!,nn C.rn:a11=111lmib.w!Udl:Sllllklglna1ol~Of

61rmmusu 111 oTllrirl<ntl.6tclPrm ridl~dMI\' , \,\111;dobWV111lanolawat!l'i.....idnlpbelD'.Ufudpod AND sldtnniot""lll*lalllclnlot
~~~of!ho. bbl.!ngndo!lonrr.onllorlndla,llons: , Ob""""~"'"'""'lddraHngd...,,,11,oot:rl<ldowollof~~
~~Relldfl>orlil,iE:dloustt>UmRh) A~Ml""/<<inlalMIOI\I~~
*RelldFl><lrVJal~(>l1mR4v)
~~O,,mi!IHlipOIIIRldPoal.-\rucmJmlllyMOl'lll<r llNPIANNEDrt...fnorcaradlollonlovol*""lnclcal!:ol-lr)'~~
~~r~1oomRAlrl IJNol'1:follcJw,grodloll<r1monll!u<:~~
Olamtf1SRtfll,llr111Fb,Or..a(>romR"1r) , O,,m,I 1,l Spetrt Fllel Fntf NU C,jtlc,iljfy J.lan~cr

a,..,tf~2ReluellngA,.1rJ;u1>WmRtv1 *Olomol15Reludligl'lom-NU

OlsY1olHUnl\1/H/l.kl~llSpl!IIIFU<IP<dA"'"-

a,...,o1~2Rolutllii;JRoor/otu Ollr:dl,'Llmlkrl>100mR<W'!

0,11Mol~9RefutflngRo..-Hghl!a"11*t.lonlor
("11Cl!,,j R,U..:1j3 11 I ? ' " i& I Pi(FJJ,7ll) i.-.d1111ortp-,lWp..ll....J10~1oft..-u..rop*!th*
- - - - - - - - - - + - - - - - - - - - .,,..1llol13tki Oo~~~~~~:v*fl\ololk,,i,!ngorm: ,Raot-,,.rl:!.COl\lrnlllocrn
l!olh!h.!IC.l\hlAl1rm5llltlon(CAS)M<lS.""'1da,y Al>m,$1>.Uot1/SA.s) 11A12i 0 +--l ~ i Is I 4 ifp9,1SJ MUtlPLANNetl""""l....,.._lnroclollonl..,<ls!hot p~llorlMf'ECE...:c:ulDANVTobleR-2ruo.,.or
~~"'"""CNolo5.Ncle5}~~
Notes Not& 1: The ED/RM shauld d~d~ra trn, *vent prampllyupc,n tfo!am,infoe !bl tim1 lim~ ha1< hasn aYcaatfod, ar wmm,*lvb<!*Yce<!<ltd N<>t* 2: Iran on11<>ln11 n,m11 Is d11tecwf and 1h11 ro!oa*11 start lime is unknawn. as.sum* lhatlh11 n,l11ase dur,r,banhasBYcHdodlhaspacifi*o'Hmoronit N<>I<! 3: II the 1111lu11nt now past an efflu11nt mon!or Is known Ill h.aVI!. stopp*tf, lntflcatlng that th~ r11lean i:alh Is lsalalld, Iha .muntmonUarindln11 I* NO lc,ngnVALID fcrclassi'lcatlun purp>HS Ncte ~= Th* pnt-ellculal!tf effluent manit<>rvak11v.r11av.illable NalaS: !rth1111qulp"'"ntlrilhe.llst.o.dn,,unara-wasalr=dylnape.tahloaraul..,r.,.,.r,1... bofor,,!he 1/llSW RR.01~1(l)R61J~ 11v*ntaccum,d,thonna11m11rg*ncycl1!i.5ir.catlonl&warranli!d Na1<!6:ThisEALls1ppUcable11=lf!h,.lnltblln1111wnl,whfclilsc:iw.ln11111!11i1111!tfr.adlatlunt,,v,,r,., occwredll ~cdes1 ar2. Chart 1 - Plant Area Key Plan
.. s.._Chon1!orl,w:atiano1PIO!\l/otoo* -~~~F
(,}l.""!'.::..L::..,_::.,_:=:.,-7,=.UCII*
~~....;~~ s~~+~~
Susquehanna FannEP-RM-1104-R Modes: CO [TI IT] [TI [ I I Pcw,,rOp,,r.itlans Startup lsalShutdw.an CcldShutdawn Rarvertng CQ=i D11fu1111!d Nuclear, LLC Reu.6,Page1ar1 ALL CONDITIONS FORM EP-RM-004-R, Rev. 5, Page 1 of 1
Enclosure 2 to PLA-8077, Page 445 of 560 Attachment 5 EP-RM-004 Revision 21 Page 292 of 298 CA1.2 j **--)*.--:~*]*-.s-<;\j A j S j."""-jlog.,7) C~l.2 j* j '**+~>> j A j i j **- j t~II-S\J RPVkvelCANNOTbo.detonnlned1or~15mln,(Not,.1\ CGU ,.,;c-jc-~-j-,_c,,,_ j ' j s I --~-t (pg.El) CON'Tf.jt,IUENfCLJ:lSUREutablo/1ed
!ti.Cl UNPLANNEO~o.. ln61il.T*bl*C-1sll!'l'lpottal\lc 11,vel,;duol!:la,.,.,.arRPVlnv,.r,lofY RPVltvelCANNOTDedotonnlned UNl'LANNEtl!lll:rea.. ln.611.:t.T*bl*C-1 ~importink RPVlolrolCANNOTbedol.,mlnodfor>,JQmin.(Not.1) RPV~l<-j 5 iln,(TAF) levelsdl!o!Dalo.. olAPVhmntarv
~~{J./<>lu1,II} UN~NEtl!ncrusolnAl£(,TobloC-11ump<rlaokl<'<d4uokl Un..,*lbbityofC,,r,,Spr>y~~
~~.:,,..,:,,*~RPVln~l~olSUfflcl:nlrna11"1Jdotala-coto CSi,3 j .,,,j-~ccj --d A j 5 j -*c-,j rpa.n)~~
~~RPVS.uoli=ANNOTboruili!nnlnedf*r~:ia m!n,(1,/ot..1) UNl'UNNEDlnef<1.. 1nAltl,Tlblee-1S11rr,p ... lankl:vditu,~~
~olRPVlrn,**ll"'l'clMlld<'llrnagslbid<lolllllcalo<<>"o l..anofAJ.L.all'<llcAliQAIJ.,.on*ltoAC)l<IWc/,:;ip:iblllyUI ACp,worcapob11Wy0>ALl.~.ISWESSbuso!""lilil:l9 Ail~.16 WESS b\ls=s on EITHER untlor:o IS min. llnil(T*bl! C-7}1od~ lo* slng!o P""crsoun:dor~ 15 (1/ot!:,1) mln.ttlo!al)
,IJ!ll &a.:<idltlon,l,lrglep,,,vor&ourcof.lnu,.wiar...ullnlo.,
~~olAU,Acpcw,,rto&AFETYSVSiEJS~~
~1D5VOCbusvc,bg lndlc.,tnn1onTochnl.al Sp,,clllc.l!lon REQUIRED 125 VtlC bu,u on Ille offeclod un~fDr:o1~mln.(Note 1) l!NPLANNEDlrcrc ..11lnR~lemporabJrolO>WO'Ffor >Tollloc..:idur:1I1Dn(Nollo$1,1D) l!NPUNNEDRP',1 P""'*uro Ina<~**> 1D p11lg<1Jo lo lo05ofd..:a,yhe.ol1cll'l:M.l<>p bllly UNPLANIJEOlnau.. lnRCSlom114r:,bJ,..lo>llMl'F due.lo km o1docoyho>l=n<M1l .. p bll!y Lo,.o!Al..LRCSt.mperolureondRPVL,vellndlallon 10n,1~ mln.(Noto I)
LonorALJ. Tobie C4 NRC commtml:atlan n,clhods CAl.1 fi-,j~~,a,jhi,i-:4.j ~ I 6 (,-,-jrpg.1:zJ) Thooccurr,,oco11fAl£l.Toh10C.Sh:Jzafllo"'~t Ellonldamogeh.t5caU**dlndla!kJ,-or<1e;r,1dod POSSIBLE UNUSUAL E\lcN.T
~~/-k'~. ~E,l,~~11 ~ "~:11:.:~7~,;~_Y p,,1f,:,in,oocoJnalont<1notr.1!nolaS~l'ETl'SVS1'ELI n,,eded/Drlhocurn,otoper:i~ngnoade, ~~~
~~Nota 1: Thn ED/RM should d=clare. lhe.1Nnlll promptly upcn de.luirin!nglhal time limit hasbec.ncxcceded,orwi1Illkelybeexceeded Nole 6: If CONTAINMENT CLOSURE ts rc-establ!shedprlor la cxce~/!lg tho.~~
Drywe/1 equipment drain tank

CONTAINMENT CLOSURE NQI established 30-mlnu!c tlme llmlt. declara!on of a General E/111!,gency I s ~ required.

Drywell sumps {Note 6)
~~Not" 9: If the coro:!illons spctlfll!d In th!s EAL lastlcnger than 15 mlnl.tes, CA1.2~~
Reactor Building sump

PC hydrogen concentration:> 6%
~~applie.s.~~
LRW collection tanks

UNPLANNED rise in PC pressure Nolo 10; lnlh=abi;eoi;e.ofreiableRCSta11"9el"3IUreltldtcaaoncau&edby1he[oss or

Main condenser hotwell . Exceeding one or more Secondary docay heat removal c:apabllltv, classlllcaUcn shoufd be ba.:ed on lh= RPV Containment Control Max Safe Radiation p1cssure Increase c~rla. when the RCS Is INTACT In Mod!, ,t or based on . Suppression pool tlme to boH data wMn In Mod!, 5 or th" RCS I s ~ INTACT In Mode -4. Levels (EO-000-107C (Mode 4) or EO-000-
. Visual observation 107R (Mode 5), Table SC-2) that can be read CONTAINUENT CLOSURE - The procedurally denne,;J condtlons or acllo111< ta!M.n to ncur,, PrllTlllry or SecondmyContalnrrentend ;is es,oc:J21cd structures. systems, in the Control Room (Table C-6) a~~"!tr,erts as a filncilonal barrier to ~lan product.release und=rshutdown . Seismic event (earthquake)
~~CONTAINMENT Hul-41p CLOSURE Status Duraaon System Onsite ORO NRC~~
Internal or external FLOODING event

High winds or tornado strike INTACT 60m1n.*

UHF Radio X

FIRE

Plant PA System X
~~. EXPLOSION~~
Dedicated Conference Lines X NOT INTACT

Other events with similar hazard

Commercial Telephone Systems X X X characteristics as determined by the Shift

Cellular Telephone X X Manager

lfan RCS h!IOt remaval system Is In operation within lh!s Ume

FTS-2001 (ENS) X X lta!TI!! and RCS temperatuia!s being "'duced the EAL ls NOT appl<:able RBAREA ARMchann,J MnSafo Unit 1:
~~EhwHon RdUrnlt 0HCrlJ1!1Gn . 1A201~~
~~. 1A202~~
1A203

1A204 RWCIJRecltcPPA,:c~,s FllolPootPPAru CRDHarth CRDSCIUl!I Unit 2:
~~, 2A201 , 2A202 HPCPP&Tu,btnoRcan RCl<::PP1.Tur1,in"R"""'~~
2A203 RHRACPPRoan RHRilDPPRoom

2A204 Susquehanna o:::J CI] [TI CI:::] [ I ] L[]
FonnEP*RM-1104-C Modes: Rev.a, P~ge 1 or 1 PawcrOp,:rallons Stllrtup f3/4tSht.tdawn ColdShutdown Rcfl..tl!ling Oefueled Nuclear, LLC COLD CONDITIONS FORM EP-RM-004-C, Rev. 7, Page 1 of 1
Enclosure 2 to PLA-8077, Page 446 of 560 Attachment 5 EP-RM-004 Revision 21 Page 293 of 298
~~.,,,,, j '**~j ~ f /i j *"" j Ip!!, IJ}~~
~~CONl'AtNIJENTCLOS\IREo,1111,l!ll,od AWi, RPV~cl CANNOT be dcl..,,,<led lor ~ 15 min. !Nol.: 1\ UNPlANNEOhueasd1Abtt'..TebleC-101rnpcrllnk~~
!o.eolsduolaalo.ssofRPVlmen1ory Rl'Vl<t<clc:ANNOTboitelolm\ned UNPLANNEDiiacuclnAllYT.tilcC.ISl!"'f'Orllnlc RPVlardCANNOTbodcl<1n1h<<lflr1tlOm\-qN01<1) R~<<-\& 1 \i.(TAFI lovd*<llolDa(buofRPVlnvorilo,y 1No1es 1,~!
~~1.111~a,<1........ m!ICLT,d,t,.C-1"'"'P"'""'klo'-"1.llel*U.a\13ilabllltyofCoroSp"")'~~
~~~~PV-l<ryoloullld<rtm,,.illldelol..1t:,lo<,... c:s1,.,j *--\ ,,j., ,~ j S j-.j(pg.Sl)~~
~~RPV!cvelCANNOTbodolenn<IC<!fon:JOmln.tNole1! UtlP\.IJ-lN~IIIOr..,,r..wr_r.i,i,,e-1..,.,po,t,0~1...... ; ...~~
~~olf'IPl/-.,Yotsllffl<lot\1.,.goillldolalndutocun <1n5VDCbu*Vt&~*nllcalouonTWltll"1l Sp*cl!callonRE"aUIRED1UVDCbusuonlMaffoclod 1Jnlllor,,.15mrl.(Nole11 IC: lnab~ll'J to maintain plant In cold shut:lown IC: UNPLANNED lncr.!!ase In RCS lempenil!Jre UNPLANNEDlncu.nlnRCS!emf0,0111tnlo,.3){1'F UNPLANl'IEDlncrea.-.1nRCSl<mperawra1a~100-Frcr >Tabl~e-:idon,lcn(Noles 1, 1DJ ***""***r.t...,n.,,,...,,.... ..,,b~,1 UNPI.ANNEDRPVpro=n=ou>-10p,:lg.i., ...
i....,rdcnyti.a1rco,..valeapab&y CUl.2 p~,-+,=-i'"""' 4 j .! I"'" Lo.. ofAIJ,,RCSWl\p1tt5IIU*ondRP\flovallndialon ror ... 15mh.(Wolo1\ j (pg.117) Ln&>.orAIJ.TobloC-lond"'tlllnmunlcaUonmetkold* LossolAL.LTab!<C-INRCCl>'llfflunbllanmeUiotb
~~~~~*i~~
~~c ..u.1 I -.~j -*- j *-s-/ ~ I $ J-*~*ll*g.123] Thaoc,:11°todA.l,IY_TabloCShomn!ous""*"t~~
~~'"""'Ever,ldamogoha...roadlndloatton,ofdognid,d p..-rorm=ln*JC11,:tonolnorlofaS>.F:n'i'ISTE"l,d n0<dedforlhoairrcntopC111lngmcd.,_ ~~~
~~Not!! 1: Thi! EDJRl..t should declare the =lpromplly upon ddermlnlng that lime llmij hasbeen~ceeded,i;irwiUtikefybeexc,,eded Note 6: If CONTAINMENT CLOSURE ls ~rabUsl\t!d p~or to ~cel!dlngthe~~
Drywell equipment drain tank

CONTAINMENT CLOSURE N.QI established 30-mlnul!! dm,.llml~ der.larallnn of a General EmergentYlafilUtequJred.

Drywell sumps (Note6)
~~Note9: /flheoondrtlcnsspedUedlnlhlsEALlastlongerthan15minutes,CA1.2~~
Reactor Building sump

PC hydrogen conoentratlon > 6%
~~apples.~~
LRW collection tanks

UNPLANNED rise In PC pressure Note1G:lnlheabsencl!cfreflableRCSl!!mpe131Urelndlcallcncaus.edbylhel11SSal'

Main condenser hotwell

Exceeding one or more Secondary decayhnt~moval capability, clasdi..ittcn should b11. ba!ll!d on the RPV Containment Control Max Safe Radiation pressurelnc:r- cril!!rlawh!!n the RCS ls INTACT In Mode~ or based on

Suppression pool dme to bolld~tawhen ln Mode 5 crthc RCS Is li.QilNTACT In Mode . Levels (EO-000-107C (Mode 4) or EO-000-

VJsualobservation 107R (Mode 5), Table SC-2) that can be read CONTAINMENT CLClSURE-Thc proc:.oduratydcllncd conditions oracHorn; taken h>
il!CUrl! Primary or Secondary O>nlalnmenl and Its a&!Hlclated r:tuctur,,,s, systems, In the Control Room (Table C-6) andccmpcnenlsasafunclionalbarricrh>lisslcnpradm:treli!a$o!!undcrshuldown conditions COlfTAINUENT Huto!Jp CLOSURESt:,tus Dur.atlon System Onsite ORO NRC
~~. High winds or tornado strike OITACT samn.~~~
UHF Radio X

FIRE

Plant PA System X

EXPLOSION Dedicated Conference Lines X NOT INTACT

other events with similar hazard Commercial Telephone Systems X X X characteristics as determined by the Shift

CellutarTelephone X X Manager

Iran RCS h!!alRmavals)'Slem Is In opera.Uonwithln this Ume frame and RCS temperature Is be!n11 reduced the EAL Is NOT

FTS-2001 {ENS) X X appflGilblc RBARfA ARIH,:lolM*I Unit 1:
~~El..,,.1!on Deo:tlpd<>n~~
1A201

1A202

1A203

1A204 CRON<rlh CROSmffh Unit 2:

2A201 g
~~HPCIPP&nmrn.11 ..... IU::ICPP&TlnlMlloom RHAACPPJ!oo,a IIHIIBO?P""""~~
2A202

2A203

2A204 Susquehanna F,mnEP-RU-110"4-C Modes: [TI [ I ]
Pov.erOperallon& SlaltUp CD o:J [TI CLJ HclShutm>Wll ColdShUldown RefUer.ng Derueted Nuclear, LLC Rav.7,Pag 1,;,f1 COLD CONDITIONS FORM EP-RM-004-C, Rev. 7, Page 1 of 1
Enclosure 2 to PLA-8077, Page 447 of560 Attachment6 EP-RM-004 Revision 21 Page 294 of 301 Attachment 6 Table H - Hazards (Form EP-RM-004-H) SITE AREA EMERGENCY ALERT UNUSUAL EVENT IC: HOSTlLE ACTIOl>J ruuldng In loss of physlcal IC: HOSTILE ACTlON,..;lhln Iha PROTECTED IC: HOSTILE ACTION within th~ OWNER IC: C1mffnnedSECURITY CONDITION orlhrut contratoftho fat!lty ARSA CCNTROLlEtl AREA oralrbome attack thrcal Within 30mfnums HG1.111 j? j 1 i 4 I,! j Q fl*g.12?l H.1:1.1 j 1 I 1 f 1 f
j ,! j Q j /pg.113! H.>,1.1j l j 1 j J f

j § j p j(pg.131) HUM j 1 11 j ] j

j § j Q ,,Jl!l.1:D)
~~AHOSTILEACnct11.~ort>a*=*"11hhlhc AHOSTILEACTIONJ,<=lllrl,,gorhoso<CIZtedWhhln~~
~~;~;~;;;~!~~-~~
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Enclosure 2 to PLA-8077, Page 448 of560 Attachment6 EP-RM-004 Revision 21 Page 295 of 301 _-: __,;- __ - GENERAL EMERGENCY UNUSUAL EVENT IC: HOSTILE ACTloN resulting 1n laH of phylilc:il IC: HOSTILE ACTION wllhln lhc PROTEClEO IC: HOSTILE ACTION within the OIM>JER Jc; CoJ'lflrmed SECURITY CONDITION or ccnllt>I or tM. fac,lity AREA CONTROLLED AREAaralrilomc abck-tlna\Wilhln lhreal JOmlnl.Jll!s HGMj 1 j 1 j 3 j " I I P j{p;.1ITJ HS1.1 j l ] 1 ] ii j
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~~PowerOpenitlons CD [TI Slilrlup HclShutdown~~
~~[I] Cold Shutdown o::J Rerudng~~
~~~ Defuoled FORM EP-RM-004-H, Rev. 3, Page 1 of 1~~
Enclosure 2 to PLA-8077, Page 449 of 560 Attachment 2, MIDAS vs URI Comparison Meteorological Information and Dose Assessment System (MIDAS) is the dose assessment (DA) code of choice implemented at SSES since 12/17/93 along with issuance of SSES Emergency Plan rev 20. Over the time, due to individual or maintenance contracts, MIDAS become highly customized at SSES. Unified RASCAL Interface (URI) is the industry standard DA code, used by over 70 units in North America, and is a computer interface on top of the RASCAL code developed by the NRC. URI is customizable through the interface, but the NRC RASCAL code is unchanged. Currently, URI interface is at revision 3.7 while the NRC RASCAL code considered at SSES is at revision 4.2. The main difference in conceptual design between the two codes is that MIDAS, as currently implemented at SSES, is geared towards Accident types and thus it is limited by the number of accidents the user defines in the design. URI employs a more modern way to perform dose assessment, first introduced by the NRC in in 1988 in NUREG-1228, in defining main compartments of a nuclear power plant and following the release pathway through the various compartments while modifying the source terms from compartment to compartment through plant specific or regulatory process reduction factors (PRF). As a notable example, MIDAS uses a fixed NG/I-131 and NG/Particulates ratio (for a filtered or un unfiltered monitored release), conservatively calculated by Design Engineering from a DBA analysis, while in URI, this ratio changes through the pathway selected and various compartments PRFs. Thus, only from this example, a much more conservative dose assessment result is expected for MIDAS when compared to URI that is expected to provide a more realistic dose assessment. Table 2-1 includes a more detailed comparison based on the radionuclide Mix, Magnitude Scaling Methods and Meteorological models within the 2 codes (Models). Thus, the URI DA methodology to start with a radioactive mix in the fuel, that gets altered by transfer thorough different compartments based on the selected pathway and various compartments PRF (Magnitude scaling method) and eventually released and dispersed in the environment, as calculated by the meteorological model is first discussed used in Table 2-1. The same concept of calculating dose also applies to MIDAS with the difference that the Magnitude Scaling Method for the forward menu in MIDAS is very limited as discussed above and in Table 2-1. Other diferences are also discussed at the end of Table 2-1.
Enclosure 2 to PLA-8077, Page 450 of 560 Table 2-1: MIDAS vs URI Comparison MIDAS URI Notes A. Radionuclide Mix 1. Accident Type Source Term Normal; Normal MIDAS contains an ATWS source term that is the ATWS; Spiked same as Normal mix - may add confusion to the Spiked; Clad Damage user. LOCA Clad Damage Fuel Melt URI does not contain an ATWS source term; it uses LOCA Fuel Melt Equipment / Fuel Handling the specific core condition present at the time of Equipment / Fuel Handling Spent Fuel the assessment in case of ATWS. In addition, URI Spent Fuel (only in ISFSI uses a user-defined factor for the spiked coolant NUREG1228 menu) that can be available from coolant samples. Also, URI has dedicated Spent Fuel Pathways (Equipment
/ Fuel Handling, 2 Spent Fuel Pool Accidents and additional ISFSI accident source terms). Thus, a monitored (through the RB / SBGT) accident at the refuel floor can be easily characterized in URI. To characterize such an accident, MIDAS requires significant data manipulation in the Forward menu that are not easy to describe and follow in the procedures.
Due to the addition of an ISFSI source term and addition of Spent Fuel source term in the monitored path, URI is superior to MIDAS. Note also that the unmonitored path embedded in MIDAS for spent fuel pool accidents (loss of inventory) contains 3 source terms (gap release from 1/3 of the pool, gap release from fully uncovered pool and Zr. Fire) vs 2 source terms in URI, gap release from ~ 1/3 uncovered fuel with steam cooling available and Zr. Fire). The additional full spent pool gap release is not necessary since, per industry benchmarking, Zr fire is expected to occur soon after the loss of steam cooling in the uncovered fuel and is likely to begin in the most recently discharged fuel.
Enclosure 2 to PLA-8077, Page 451 of 560 MIDAS URI Notes 2. Radionuclides 35 radionuclides 33 radionuclides MIDAS includes Co-58, Co-60, Pu-238, Pu-240, Pu-241, Cm-242 and Cm-244 isotopes when compared to URI. URI includes Xe-131m (FP and activation, 11.8 d), Sr-91 (FP, 9.63 h), Y-91 (FP, 58.51 d), Sb-127 (FP, 3.85 d), Sb-129 (FP, 4.4 h) and La-140 (FP, 1.6781 d) isotopes when compared to MIDAS. In particular, URI contains significantly (greater than 5%) more Te-129m and Np-239 in the fuels source term than MIDAS and MIDAS contains significantly (greater than 5%) more Kr-85, Kr-85m, Kr-87, Cs-134, Cs-137, Sr-90 and Ru-106 in the fuel source term than URI. However, as discussed in A.3 and Enclosure 1, the overall dose difference at the EPB due to the URI vs MIDAS fuel source term mixes is below 5%. In addition, Co-58 and Co-60 are not fission products but activation products of Fe and are not expected in an accident release in quantities that would matter, as they are controlled through different plant processes. The Plutonium and Cerium isotopes are activation products of Uranium and they are produced in very small quantities in the fuel. Their contribution to the dose in an accident is minimum and is neglected by the NRC in the RASCAL code. On the other hand, all isotopes above, that are listed in URI and are not included in MIDAS, are fission products (FP) with relatively large half lives (~ days) that would contribute to the dose in larger quantities than Plutonium, Cerium and Cobalt isotopes. From this point of view, URI is superior to MIDAS.
Enclosure 2 to PLA-8077, Page 452 of 560 MIDAS URI Notes 3. Radionuclide mix in source term Uses proprietary GE Generic core source terms A comparison between 2 fuel sources was method to compute the from NUREG-1940 and performed by entering MIDAS and URI radionuclide fuel source term and consistent transfer concentration, representative for fuel clad and fuel various methods to derive fractions between melt source term mixes, and the same flow in the accident or normal source compartments (i.e. fuel _> Release point sample method in URI (see Enclosure terms for: gap -> rector coolant, etc) 1). The resulting doses at the EPB were then a. Forward menu for from m NUREG-1940 and compared. The comparison shows that, overall, the accident types defined NUREG-1228. EPB doses are within 5%, well within the dose in A.1 above assessment accepted uncertainty level. (Attachment C in NEP Also, although the 2 codes employ different Technical Basis (TB) methods, as explained above (accident type menus 21-001) vs release pathways), all accident menus in MIDAS b. Default (DBA) menu can be characterized by one or multiple pathways (Attachment B in NEP in URI, as follows: TB 21-001) - Forward menu in MIDAS corresponds to SSES c. NUREG-1228 menu URI Pathways A, B, E, G, H, J, L, N, P, R, T and U (Attachments D and E - Default menu in MIDAS corresponds to SSES in NEP TB 21-001) URI pathways I and M. d. Blowout panel menu - NUREG-1228 menu in MIDAS corresponds to (Attachment E in NEP SSES URI Pathways C, F, I, K, M, O, Q, S. TB 21-001) - Blowout panel menu in MIDAS corresponds to These various methods SSES URI Pathway D. also use transfer factors - Back calculation menu in MIDAS is a magnitude from NUREG-1228, scaling method in most of the SSES URI calculated by RADTRAD or pathways. from RTM 96. - Isotopic entry menu in MIDAS is a magnitude scaling method in most of the SSES URI pathways
~~- Up to 5 multi-unit, multi-source accident can be modeled in both MIDAS and URI.~~
As seen from above, URI is a more versatile model to describe a monitored (Forward menu) calculation than MIDAS. Note that a monitored pathway is expected in the vast majority of the accident scenario including the DBA. In addition, all of the venting pathways at SSES can be modeled in URI while some of the SSES-specific venting paths cannot be modeled or overlap others and require significant data manipulation that are not easy to describe and follow in the procedures if MIDAS code is used for these pathways.
Enclosure 2 to PLA-8077, Page 453 of 560 MIDAS URI Notes B. Magnitude Scaling Methods In essence there is only Based on the pathway The Monitored Magnitude Scaling method in URI is one method available in selected, there are approximately similar to the Forward menu in the MIDAS Forward menu, multiple magnitude MIDAS, but as discussed already above, MIDAS uses filtered or unfiltered, scaling methods in URI, as a fixed NG/I-131 and NG/Particulates ratio (for a release characterized by follows: filtered or un unfiltered release in the Forward fixed NG / I-131 and NG / * Monitored menu), conservatively calculated by Design Particulates rations. * Containment Leakage Engineering from a DBA analysis, while in URI this NUREG-1228 menu uses * RCS Leakage ratio changes based on the pathway selected and similar scaling methods as * Field Team various compartments PRFs. In other words, in URI. * Release Point Sample individual vents (SBGT, TB) have their own PRFs in These methods employ URI while there is only one way to characterize the following Process such a release in MIDAS. In addition, the Reduction Factors (PRF): magnitude scaling methods listed for URI can also x Filtered / Unfiltered be applied for unmonitored releases for the x Building Hold Up times respective pathway, while in MIDAS, only the x Containment Sprays Default (with no input other than the fuel clad for releases in Drywell damage information) or NUREG-1228 menus are x Suppression pool available to the user to characterize such releases. status Therefore, URI is expected to provide for much more flexibility for the user and more precise assessment when compared to MIDAS for both monitored and unmonitored releases C. Meteorological Model 1. Dispersion Model Modified Gaussian Plume Uses 2 models: The second URI method embeds the latest (circa model x Straight line Gaussian 2000) model for atmospheric dispersion and for smaller distances deposition as opposed of Gaussian models that are x Rectangular grid based on circa 1950 observations. Lagrangean - Gaussian Therefore, URI is expected to provide for much Puff model more precise assessment when compared to MIDAS. 2. Precipitation Includes Light, Moderate / Includes Light, Moderate / URI is expected to provide for much more precise Heavy rain Heavy rain as well as Light, assessment when compared to MIDAS for snowing Moderate / Heavy Snow conditions. 3. Release height 10 m (ground release) for Vent and HCVS releases By being able to default to appropriate release all menus are stack (60 m) releases heights, URI is expected to provide mor precise and all other assessment when compared with MIDAS. (unmonitored) pathways are ground releases.
Enclosure 2 to PLA-8077, Page 454 of 560 MIDAS URI Notes D. Other Parameters 1. Post Plume (Intermediate) Phase Calculates deposition with Requires post-plume data While MIDAS calculates deposition and population each run processing to determine dose during each run, a similar method as an overall plume phase performed in URI Integrate mode would be deposition. required for MIDAS as well, when individual release durations, wind speeds and directions and other parameters are known at the end of the plume phase and deposition and doses can be more precisely calculated. While URI does not calculate population dose, EP-PS-245 contains instructions on how to determine this parameter by using an excel spreadsheet developed for this purpose which contains the most updated population in various sectors. Rather than changing the MIDAS code with the updated population, the current population is updated in the Excel spreadsheet whenever EP-PS-108, Attachment B is changed, per the spreadsheet usage directions, that also links directions to update the potentially affected population with other EP procedures such as EP-102 and EP-107. 2. Rapid Mode On shift staff is trained Specific mode (Rapid) for While the Rapid mode in URI does not include Back only in Forward and Back on-shift staff calculation, it includes a blowout panel scenario Calculation menus (with or without line isolation) for the on-shift staff, specifically designed for SSES. The Back calculation assumes a field monitoring team is available to report field data and this can occur after some time due to minimum RP equipment checks. Therefore, the industry decided that a field calculation is not added in in the Rapid mode. However, a blowout panel scenario can happen before the TSC takes control and therefore, the Rapid mode for SSES URI represents an important addition of the capability of the on-shift staff to characterize such a scenario. 3. User Input Manual Manual, semi-automatic The setup for URI includes linking vent release, (drag and drop) and meteorological information and other parameters automatic data entry from R*Time computers and adding this input to URI via a semi-automatic (drag and drop) and automatic data entry (only in rapid mode) method. Therefore, URI is much more user friendly and less error prone when compared with the current version of MIDAS code at SSES.
Enclosure 2 to PLA-8077, Page 455 of 560 MIDAS URI Notes 4. User Output Saved on stand alone Saved on network The setup for URI includes saving the data on computers. network, thus making it accessible to both TSC and EOF responders. Therefore, URI is much more user friendly when compared with the current MIDAS code at SSES. 5. User Input / Output design Although the Input is The input is echoed in the URI input can be adjusted and the code run without echoed in the Output output report, and the the need to enter any parameters that did not report, the Input screen is input / output can bs seen change, resulting in time savings on running separated from the on only one screen. individual runs. Output repot. Also, URI user can see both input and the DA results on same screen. D. Other Parameters (cont) 6. Procedures used (just) to run the code a. On-shift x EP-PS-130-1 (1 page) x EP-PS-130-1 (3 page) Easier to run URI code from the procedural x EP-RM-005- 1, -2 and - x EP-PS-001 new (3 standpoint than MIDAS 7 (6 pages) pages) Total: 7 pages Total: 6 pages b. ERO x EP-PS-001-22 (1 page) x EP-PS-001-22 (10 Much easier to run URI code from the procedural x EP-PS-001-61 (6 pages) standpoint than MIDAS pages) x EP-PS-001 new (3 x EP-PS-001-63 (1 pages) pages) x EP-RM-005, Section K (2 pages) x EP-RM-001-1 through 7 (14 pages) Total: 24 pages Total: 13 pages 7. Reactor shutdown adjustments in source term mix prior to release, release duration, mapping capabilities and other parameters and features not discussed here are similar in both MIDAS and URI.
Enclosure 2 to PLA-8077, Page 456 of 560 In conclusion, URI is a better code as compared with the current version and setup of MIDAS at SSES because: x Provides for more precise dose assessment calculations due to:
- calculation of PRFs and NG/I-131 and NG/Particulates ratios based on the selected pathway - a much-improved atmospheric dispersion model, including pathway dependent release heights and adjusting release based on snow. - inclusion in the source term of fission product isotopes with relatively large half-lives such as Xe-131m, Sr-91, Y-91, Sb-127, Sb-129, and La-140 x Addition of an ISFSI source term, addition of Spent Fuel source term in the monitored path and addition of Blowout panel scenarios in Rapid mode x Much more versatile and flexible model that includes multiple magnitude scaling methods (for potential unmonitored release) in the pathway itself and can characterize - ALL - SSES-specific containment vent pathways.
x Allows user to see both inputs and dose assessment results in one screen, as well as time savings in running the code as it needs to modify only the changing input parameters, without entering those that are not changed in individual runs. x Much more user friendly, and less error prone user input and output due to connectivity with R*Time computers and network data saving capabilities. x Much easier to run from the procedural standpoint.
Enclosure 2 to PLA-8077, Page 457 of 560 Enclosure 1 to Attachment 2 EPB Dose Comparison for Generic URI vs SSES-specific MIDAS Source Term Mixes for Clad Damage and Fuel Melt Accidents A comparison between MIDAS and URI fuel source terms was performed by entering MIDAS and URI radionuclide concentration, representative for clad damage and fuel melt source terms, and same flow in the Release point sample method in URI and comparing the EPB doses. The comparison (see results below) shows that, overall, the EPB doses are within 5%, well within the dose assessment accepted uncertainty level. Site boundary comparison: Clad Damage TEDE Child Thyroid CDE URI mix: 3400 64200 SSES mix: 3580 64900 Ratio (MIDAS/URI) 1.05 1.01 Fuel Melt URI mix: 1980 19200 SSES mix: 2060 19500 Ratio (MIDAS/URI) 1.04 1.02
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General Emergency of E2023-02-02-01 Page 10 of 13
Enclosure 2 to PLA-8077, Page 459 of560 Doses with MIDAS Mix
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Woijdng of E2023-02-02-01 Page 11 of 13
Enclosure 2 to PLA-8077, Page 460 of560 Note: the reactor core accident damage type is overridden when using release point sample method. Fuel Melt Doses with URI Mix
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~~Title:~~
~~Noble Gas Release Rate Limits For EAL's [8l NEW/ FULL REVISION 0 SUPERSEDED 0 MINOR REVISION 0 VOIDED~~
~~!E Minor, Superseded or Voided, FILL OUT next page for justification.~~
PROCESS Superseded and Voided Technical Basis only by completing this form. PROCESS Minor revision by updating, up-reving and issuing the Technical Basis in NIMS. Affected Procedures: Previous Basis Affected: NEP Technical Basis 02-005, Revision 3 Check Affected ERF: [8l Control Room [8l Emergency Operations Facility
~ Technical Support Center D Joint Information Center D Operations Support Center Prepared by: /1/i+-,.!..L..J_,_Q!.ti)~-'-'--"'""F-"'-==-....:::..-~;3/P'f-P-=~ Date:
~~Reviewed by *: A'DQt AtJ~~
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~~Approved by: ...h.) ~- & M---5 ~~ Date:~~
~~Not required for Minor, Superseded or Voided Technical Basis Electronic Form EP-101~1 Rev. 2, Page 1 of 3~~
~~Enclosure 2 to PLA-8077, Page 471 of 560 NEP Technical Basis 02-005 Rev 4~~

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Enclosure 2 to PLA-8077, Page 473 of 560 TABLE OF CONTENT CHANGE HISTORY 2 PURPOSE 4 BASIS AND METHODOLOGY 4 RESULTS 6 CONCLUSIONS 10 REFERENCES 10 ATTACHMENTS 10 ATTACHMENT 1 11
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Enclosure 2 to PLA-8077, Page 476 of560 Noble Gas Release Rate Limits for EALs NEP Technical Basis 02-005, Rev 4 Page 6 of 11 accident progression and plant operational behavior. The following assumptions on the accident conditions are used:
15 minutes time after shutdown

1 hour release duration

Clad damage

LOCA in the drywell

Drywell hold up time less than 2 hours (conservative)

Drywell sprays not activated on the source in the drywell (conservative)

Drywell leakage to the reactor building (conservative)

Reactor Building hold up time less than 2 hours (conservative

Reactor building ventilated through SBGT or RB vent

SBGT or RB filters in service These selected conditions create a specific isotopic mix at the effluent monitor and in the environment. These conditions, along with the meteorological data shown above are used in URI to develop the NG effluent monitor threshold limit values.
The 'dose point' for the threshold limit values is the site emergency planning boundary in the affected sector as defined in the dose assessment software system. Results The selected meteorological data and plant conditions described above are used in the URI dose assessment software system to determine the effluent monitor threshold limit values. The URI system configuration is defined by the program version number and the encrypted site data file Unique ID code as shown in the image below. About URI ... X Site: SSES, Veraion: 3.7.l.1 Computer JD: RSCS_L-075 EilCl)'p!ed Source Ale Name: SSES Dose Assessment Data.xml Encrypted Source Ale* Unique JD: ~ 7 4 Encrypted Frie Internal Date/Tone Stamp: Tuesday, August 30, 2022 06:39:34 Eilaypted Fdefreatcir UserlD: wjcooper RASCAL Me!eorologlcal Process Flle_(MobsProc40.dll): ** 8/G/2021 RASCAL Puff Model Process Ale CTADPUFF40.dH): RASCAL Plume Model j'roc:ess Hie CTADPLUME4Q.dll): S/G/2021
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The plant conditions are defined by selecting the URI Pathway that represents the pre-defined conditions: Clad damage-> LOCA in Drywell -> Drywell leak to Reactor Building -> SBGT or RB Filters -> RB or SBGT Vent-> Environment
Enclosure 2 to PLA-8077, Page 477 of560 Noble Gas Release Rate Limits for EALs NEP Technical Basis 02-005, Rev 4 Page 7 of 11 This plant condition is represented by pathway H in the URI software, as shown selected and highlighted in the image below. As discussed above, in addition to OBA LOCA in Drywell (OW), this event also assumes fuel clad damage, DW leak into the Reactor Building (RB), with RB intact and a filtered release through SBGT or RB vent for 1 hour. Pathways - SSES X
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T ilfllllli'D I Calculated Pro=, Retluctioli Fador (PRF): 8evallon ynelera): The pathway screen image from URI also shows the PRF options used for the assessment. Sequential URI calculations were performed, slightly changing the effluent monitor reading until either the TEDE or CDE Thyroid from the calculation was at the GE dose based EAL threshold of 1000 mrem TEOE or 5000 mrem COE Thyroid. The Detailed assessment form shown below shows the completed dose assessment at the GE EAL doses.
Enclosure 2 to PLA-8077, Page 478 of560 Noble Gas Release Rate Limits for EALs NEP Technical Basis 02-005, Rev 4 Page 8 of 11 eJ SSES - Detailed Asse531llent- Actual Event! X File yrew :ea1~1.itions Exp~rt Help i<fil I@J 111 i: +I (iJ Iii ForceReca!OJlation """1itored Jeon~~tL,,akageJ.RCSL~]_Rel.... eFt~~le[Fie!dTeaml :;,- l. : l Soorce Term
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/ Plume DOE . CEDE 2778-02 5.37E..01 237E+-01 2008-02 3.69£..ol 203E+01 1.JOE..02 2.28E..01 1.398-01 7.49E+01 1.31E+07 8.69E.OO 4.778-01 B.63E.OO 5.7:JE.OO 3.45E+-01 4.03E.OO 294E+-01 3.46E.OO 2.26E.00 262E+01 3.26E.OO
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Prticess-Reductioo Fader: 8evation6'neters): Diywell HUT: '<2 Hours RdlldgHUT: <2Houra . Dlywell5prays: ;-ReaCingsto PAfu OFF RE/SBGTRk""': Wo#!g Supp Pool HUT: NIA TUJb Bldg HUT: NIA Supp PoolS!atus: N/A Filters: NIA The URI Detailed assessment screen form shown above shows the clad damage condition is selected, 15 minutes of decay, and 1 hour release duration. The 1.72E10 µCi/min in the SBGT RB vent monitor reading results in a thyroid CDE dose of 5.00E+03 mrem. Normally, URI highlights in red doses exceeding the PAGs. In this case, the value may be just below or at the PAG level and not exceeding the actual PAG limit, so the dose calculation is useful here considering significant digits of the input and results, but this particular value is not necessarily greater than the PAG limit for highlighting. The individual isotope release rates are shown below. In previous revisions of this technical basis document, a fixed total noble gas to lodine-131 ratio (NG/I131) of 1000:1 was used. Since URI develops a specific release rate by isotope for each assessment, this fixed ratio is not used here. The total noble gas release rate for the conditions assumed for this assessment is shown at the bottom right of the image above as 287 Ci/sec. The 1-131 specific release rate is shown in the image below as 0.0978 Ci/sec. Therefore, the NG/I131 ratio used in this assessment is 287/0.0978 = 2930:1.
Enclosure 2 to PLA-8077, Page 479 of 560 Noble Gas Release Rate Limits for EALs NEP Technical Basis 02-005, Rev 4 Page 9 of 11
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La-14!). 0.!)0&110 Y-91 O.OOE+.QO Ci,.144 O.OOE+Oq Np,239-. . . 0.(JQEf,00 Based on this URI calculation, the EAL for the vent monitor would be (rounded to two significant digits) 1. 7E10 µCi/min for the GE. The previous revision of this technical basis documented the GE EAL to be 1.9E09 µCi/min, as determined by MIDAS-NU runs with the same scenario. An inspection of the previous revision of this technical document suggests two primary reasons for the almost factor of 10 difference between the previous and current calculation.
1) The total noble gas to Iodine 131 ratio is about 3 times larger in this revision, meaning that, for the same NG release rate, 1-131 concentration assumed in MIDAS is 3 times larger than the one calculated in URI for the selected pathway. This means that the COE thyroid dose would be smaller in URI for the same NG release rate. Since the limiting dose is for the child thyroid COE PAG, the smaller contribution from iodine in this dose assessment resulting from the higher NG/I131 ratio in this revision will cause the EAL (which is based on a noble gas monitor reading) to be higher.

2) URI uses the dispersion and dose model inherent in the NRG RASCAL code (reference 5).
The previous revisions to this technical document used the MIDAS dose assessment software system. URI uses the dispersion and dose model from RASCAL version 4.2. The RASCAL dispersion and dose model was extensively revised in RASCAL version 4 with a result that the dispersion determined by the model tends to be somewhat better (smaller X/Q, lower inhalation doses) than dispersion models previously used extensively in the industry (see figure 4-5 in reference 5) since the 1960s. The previous industry models and methods are still used in MIDAS. Per reference 1, the SAE and Alert EAL values are 10% (SAE) and 1% (Alert) of the GE value: SAE: 1.7E10 µCi/min* 0.1 = 1.7E9 uCi/min Alert: 1.7E10 µCi/min* 0.01 = 1.7E8 µCi/min
Enclosure 2 to PLA-8077, Page 480 of 560 Conclusions 7KHWKUHVKROGYDOXHVIRUWKHSODQWYHQWPRQLWRU($/VVKRXOGEHVHWDVVKRZQLQWKHWDEOHEHORZ ($/ 3ODQW9HQW7KUHVKROGIRU1*5HOHDVH5DWHV&LPLQ
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Enclosure 2 to PLA-8077, Page 481 of560 Noble Gas Release Rate Limits for EALs NEP Technical Basis 02-005, Rev 4 Page 11 of 11 Attachment 1 Frotm Jeffrey Baum <JBaum@absconrulting,com> Sent: Wednesday, September 21, 202:2 2:44 PM Ta: Mfrnn,..Adrian<AdriaJ1.Miron@talenenergy.com>; Hick~, Fr.ands J <Francis:.l-!ickey@talenenergy.com> Subj,ero, RE: Susquehanna Meteorolo!W For New EAL's [hternal Email] Adrian, Below are the same values using the 60m sensors. The stability class and rainfall values are the same as previously5entc Ptease let me know if you need. anythingersea Thank you Jeff Variable 2019 2020&2021 3 year Average WiooSpeecl 7.7 7J, 7.6 Wind lmr-ectfon 147 158 151 (SE} Stability D o, D Precipitation 50.87 4538 46.63 From, Miron, Adrian <Adrian.Mfron@talenenerey.com:;, Sent: Tuesday, September 20, 20-22 5-:58 PM Tm Jeffrecy Baum <JBaum@abscoosulting.com>; Hickey, Francis J <::Fr.ancis.Hickey@talenenergy.oom> Subj,ect:, [EXTERNAL]: RE: Susquehanna Metecrn[cgy For New EAl's Please give me the same info fur the 60 m sens,ar_ Thank you very much. Ff'CIITllJeffrey Baum <JBaum@absconrulting£om> Sent: licres:day, September 20, 202212:37 PM Ta: Mfrnn,..Adrian <Adrian.Miron@talenemergy.com>; Hickay, Francis J <Francis.Hickey@talenenergy.com::> Subj,em RE: Susquehanna Meteorology For New EAL'5 fExternal Email] Adrian, This wind dire.ction i's from and I only used the 10m sans,ar_ [t you v.roufd like I can give yoLI the same infonmation for the 60m sensor. Page 1 of 1
Enclosure 2 to PLA-8077, Page 482 of 560

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~~Enclosure 2 to PLA-8077, Page 483 of560 Attachment A, EP Technical Basis Cover Sheet Tracking No.: 001~~
~~------------ Revision: 4~~
~~Title:~~
Frisker Response in Support of EAL Implementation and Determination of Release In Progress IZi NEW/ FULL REVISION SUPERSEDED MINOR REVISION VOIDED IF Minor, Superseded or Voided, FILL OUT next page for justification. PROCESS Superseded and Voided Technical Basis only by completing this form. PROCESS Minor revision by updating, up-reving and issuing the Technical Basis in NIMS. Affected Procedures: Previous Basis Affected: EP-PS-001 EP-PS-222 NEP TB 16-001 Rev 3 EP-PS-104 EP-PS-245 EP-PS-108 EP-PS-247 EP-PS-134 Check Affected ERF: IZI Control Room IZI Emergency Operations Facility IZI Technical Support Center D Joint Information Center D Operations Support Center Prepared by: __.:A6Q.drd!ia~n!_M~ir2_on!!J,~:!:.!2.:____=:~~~:_ Date: 8/3/23 Aug 9, 2023 Reviewed by *: Shane Jurek ?C"Q,<L Date: Aug 16, 2023 Approved by: Jay A. Barnes " Date:
~~Not required for Minor, Superseded or Voided Technical Basis Electronic Form EP-101-1 Rev. 2, Page 1 of 3~~
Enclosure 2 to PLA-8077, Page 484 of 560 Attachment A, EP Technical Basis Cover Sheet, Continued For Minor Changes Only Description of Change(s): Reference for the change (e.g. CR #, AR #, EC #): Expected impact of the change on the Results and Conclusions including consideration of all outstanding minor changes against the Technical Basis: Explain how the expected impact meet the acceptance criteria or purpose of the Technical Bases: For Superseded and Voided Technical Basis Only Explain why the Technical Basis is voided or superseded: Prepared By: EP Manager Concurrence: Electronic Form EP-101-1 Rev. 2, Page 2 of 3
Enclosure 2 to PLA-8077, Page 485 of 560 Attachment A, EP Technical Basis Cover Sheet, Continued Comment Resolution Sheet Name Comment Resolution Electronic Form EP-101-1 Rev. 2, Page 3 of 3
Enclosure 2 to PLA-8077, Page 486 of 560 EP Technical Basis 16-001 Revision 4 Frisker Response in Support of EAL Implementation Replaces NEP Technical Basis 92-004 and 94-001 and 16-001, Rev 0 through 3
Enclosure 2 to PLA-8077, Page 487 of 560 NEP Technical Basis 16-001 Rev 4 Page 2 of 21 Table of Contents Revision Summary...................................................................................................................................... 3 A. Purpose................................................................................................................................................... 4 B. Background and Discussion ................................................................................................................... 5 C. Inputs and Assumptions ......................................................................................................................... 9 D. Method ................................................................................................................................................. 13 E. Results .................................................................................................................................................. 14 F. Conclusions........................................................................................................................................... 17 References ................................................................................................................................................. 19 Attachment A Method to Calculate Child to Adult Thyroid CDE Ratio .................................................. 20
Enclosure 2 to PLA-8077, Page 488 of 560 NEP Technical Basis 16-001 Rev 4 Page 3 of 21 Revision Summary
1. Added Table of Contents

2. Clarified Purpose section

3. Removed references to OSCAR automatic method.

4. Simplified, consolidated information and rewrote document based on dose assessment method changes (MIDAS to URI):
- Removed extraneous information - Latest updates of EC-RADN-1164 (rev 6) with Atrium 11 source term - Removed reference to EC-RADN-1140 and EC-RADN-1002 and replaced with NET Technical Bases 21-001 containing Atrium 11 source term - Updated with the URI source term. - Updated release in progress guidance and change title. - Deleted Appendix A. - Deleted Attachment A and replaced the theoretical detector efficiency method with a robust value based on HP Technical Bases 92-003 - Updated reference section
5. Added current Attachment A.

6. Perform other formatting changes.
Enclosure 2 to PLA-8077, Page 489 of 560 NEP Technical Basis 16-001 Rev 4 Page 4 of 21 A. Purpose The purpose of this evaluation is to provide the following input to the applicable dose assessment procedures:
1. Iodine filter cartridge conversion factor for field team manual sampling to convert measured iodine filter cartridge ccpm to an air concentration of the radioiodine mix in µCi/cc.

2. Iodine filter cartridge conversion factor for field team manual sampling to convert measured iodine filter cartridge ccpm to Child Thyroid Committed Dose Equivalent (CDE) rate inmrem/hr.

3. Field team data (ccpm) used to identify EALs related to measured field team readings of Child Thyroid CDE for one hour of exposure. Since field teams cannot directly measure Child Thyroid CDE, measured equivalent iodine cartridge count rates are used to identify measured Child Thyroid CDE dose rates. The following are required:
EAL RA1.4 Alert- Field Team Reading > 50 mrem Child Thyroid CDE for 60 minutes of exposure (Equivalent ccpm).

EAL RS1.3 Site Area Emergency- Field Team Reading > 500 mrem Child Thyroid CDE for 60 minutes of exposure (Equivalent ccpm).

EAL RG1.3 General Emergency Alert- Field Team Reading > 5000 mrem Child Thyroid CDE for 60 minutes of exposure (Equivalent ccpm).
~~In addition, these values are used in EP-PS-001-42, Field to Projection Measurement Comparison~~
4. Iodine filter cartridge conversion factor for field team manual sampling to convert measured iodine filter cartridge ccpm to adult thyroid CDE rate inmrem/hr. This value (10% of the 10 rem/h Adult Thyroid CDE rate) is used to begin tracking thyroid doses for the field team members, in accordance with EP-PS-001-28, Calculation And Tracking Sheet For Estimated Iodine CDE and Total Effective Dose Equivalent (TEDE) Doses, EP-PS-001-35, Field Team Monitoring Strategy Notes, and the following dose assessment procedures EP-PS-104, EP-PS-108, EP-PS-134, EP-PS-245 and EP-PS-247.

5. Document the I-131 ratio in the mix to input in URI code.
Enclosure 2 to PLA-8077, Page 490 of 560 NEP Technical Basis 16-001 Rev 4 Page 5 of 21 B. Background and Discussion This document uses Iodine source terms in SSES Unified RASCAL Interface (URI) dose assessment code as documented in NEP Technical Bases (NEP TB) 23-001 and 23-002 and its conclusions should be checked for validity any time these documents are updated. The NEP TB 23-001 source terms are based on NUREG-1228. In addition, EC-RADN-1164 is used for source term comparison and additional verification. An Excel spreadsheet associated with this document was developed and can be used to perform necessary calculation or to document and track changes in the in NEP Technical Bases 23-001 and EC-RADN-1164 that do not result in any changes for this document. The Excel spreadsheet for this document is located in T:\SSES\Nuclear Emergency Planning\NEP Technical Bases\16-001\Rev 4\Probe Calcs R4.xlsx. However, for major projects, this document needs to be updated even if its conclusions do not change. Examples include, but are not limited to, fuel source term changes like Atrium 11 fuel, updating dose assessment methodology to an event tree assessment, or changing Dose Conversion Factors (DCFs) in URI. In this case, adding an Attachment to document that the analysis was performed but it does not change the conclusions is acceptable if it is more efficient to do so. Revisions 0 through 3 of this document contain description of historical events that led to establishing the current methodology. These were eliminated beginning with Revision 4 for brevity and due to different methodologies employed in Revision 4 of this document. In accordance with the EP implementing procedures (multiple forms in EP-PS-001, EP-PS-104, EP-PS-105, EP-PS-134, EP-PS-244, EP-PS-245 and EP-PS-247) the field team results are used to check and adjust any other calculation performed by the SSES URI computer code. If exposure rate (measured)/ exposure rate (calculated by URI) or if Thyroid CDE rate (measured) / Thyroid CDE rate (calculated by URI) is greater than 5, EP procedures direct performing a back calculation using the URI field team (back) method. The back calculation is performed in URI as follows:
Meteorological data, distance downwind, and the measured field data, e.g., plume exposure rate Closed Window Field Monitor Reading (mR/hr) and (optionally) the Iodine Cartridge Manual Sample concentration (I-131 fraction) are inputs into the Field Team (Back) Calculation method.

Using the field data, current meteorology and release data, the plume is scaled to the field team results.
- If only a plume exposure rate is available, the plume is scaled to the observed exposure rate using the isotopic mix derived from the selected pathway and process reduction factor selections. - If an I-131 sample result is also available, the plume exposure and plume DDE is scaled to the observed exposure rate while the deposition, CEDE inhalation and CDE Thyroid inhalation is scaled to the I-131 concentration at the sample location.
The field team back calculation scales an effective plume based on the observed sample results and the meteorology. It does not calculate release rates by isotope.

Field team back calculation is available only for 10 mile radius assessments.
Enclosure 2 to PLA-8077, Page 491 of 560 NEP Technical Basis 16-001 Rev 4 Page 6 of 21 Note also that only the magnitude of the release rates is adjusted per the Back Calculation method described above, but the radioiodine mix for dose projection remains the same as it was in the predetermined Accident Type mix. The URI radioiodine activity distribution is compared with the one calculated in EC-RADN-1164 for Atrium 11 fuel in Table 1. Although all DBA-LOCA source terms (coolant, coolant with spike, clad damage, fuel melt and fuel handling accident) from EC-RADN-1164 were compared and documented in the Excel spreadsheet associated with this revision, only clad damage and fuel melt mixes are shown in Table 1 because, as discussed in previous revisions of this technical basis:
Normal coolant source does not contain much iodine in its overall source term and is unlikely to exceed unusual event level doses for any envisioned scenario (worst case was considered to be Pathway F in URI with 12 hours release duration).

Spiked coolant source is unlikely to exceed alert level doses for any envisioned scenario (worst case was considered to be Pathway F with 12 hours release duration).

Worst case DBA Accident/ Fuel handling accident is unlikely to exceed alert level doses per EC-RADN-1126 (worst case is also included in FSAR Table 15.7-16)

Other spent fuel sources are not expected to contain Iodine.
The comparison of iodine distributions in Table 1 shows that URIs and EC-RADN-1164 relative distributions for iodine are very similar (see 1 Hour column in Table 1 for EC-RADN-1164 calculations vs the corresponding isotopic mix fractions in URI). The slight differences can be attributable to the fact that EC-RADN-1164 mixes are obtained from an hourly activity release in the environment while the mixes in the other columns are instantaneous mixes from release rates given by URI code for various times following the reactor shutdown. Revisions 1 through 3 of this document include a discussion on previous SSES dose assessment code (MIDAS-NU) verification that the MIDAS mixes (MCAi) defined in the supporting documentation are the same as the MCAi obtained by running Forward and Back calculations in MIDAS-NU (see Table 3 in revs 1 through 3 of this document). This discussion is not reproduced in this revision as is not relevant to the calculations perform therein, but the historic documentation serves as a verification that the MIDAS code was implemented in accordance with the supporting documentation. However, this revision of the technical basis deals with URI implementation and comparison with Atrium 11 source updates in EC-RADN-1164. The radionuclide mix changes over time following the reactor shutdown due to various source term (Iodine) decay half lives that change the radioiodine mix, as shown in the last columns of Table 1. While values shown in T=0 column in Table 1 are representative for an URI a release rate mix at the time of reactor shutdown, all others mixes were obtained by performing URI calculations for fuel clad damage /melt up to 96 hours following the shutdown. However, it is expected that the release is stopped well before this time. By comparing highlighted columns in Table 1, it is concluded that the iodine mixes used in URI are similar with the relative distributions in EC-RADN-1164, even though they are obtained using totally different methods (RADTRAD with AST timing and specific Atrium 11 fuel source term vs URI method with generic source term and release fractions in NUREG-1228 and NUREG-1940,
Enclosure 2 to PLA-8077, Page 492 of 560 NEP Technical Basis 16-001 Rev 4 Page 7 of 21 respectively). This also provides for a successful verification of consistency between various DBA SSES calculations and documentation in support of the URI code. As shown in Table 1, the mixes for clad damage and fuel melt are the same in URI and are combined in the next columns. In conclusion, the URI mixes can be used as an approximation for the iodine isotopic distributions expected in the field until more details become available to the organization through spectroscopy analysis on the Iodine cartridge. These URI mixes are representative for fuel clad damage or fuel melt. The mixes for other URI accident types were not calculated as they either are not expected to contain Iodine (normal coolant, spent fuel) or they cannot provide for significant doses in the worst case scenarios (spiked coolant, DBA fuel handling accident). The proportionality between the available activity in fuel and the activity released in the environment, as implemented in the URI code through various release fractions or process reduction factors between compartments, will ensure that the radioactive mix for the fuel clad damage or fuel melt remains the same regardless of the chosen pathway. Therefore, as discussed above, only the time from shutdown influences the iodine mix due to different decay half lives for the various Iodines in the mix. Table 1: Comparison Of Iodine Isotopic Activity Distributions For Core Activity (DBA-LOCA Activity Released To Environment (EC-RADN-1164 vs URI mixes at various times after Rx shutdown) EC-RADN-1164, Table 5. EC-RADN-1164, Table 2. URI, Clad URI, Fuel Radio- DBA-LOCA 100% Clad DBA-LOCA 100% Fuel damage, melt, nuclide Failure Melt mixes mixes 1-H column 1-H column T*=0 T*=0 I-131 13% 13% 12% 12% I-132 17% 18% 17% 17% I-133 26% 27% 24% 23% I-134 19% 18% 25% 26% I-135 24% 24% 23% 22% Total 100% 100% 100% 100% Radio- URI mixes for fuel damage nuclide T*=1 H T*=2 H T*=3 H T*=4 H T*=5 H T*=6 H T*=12 H T*=24 H T*=48 H T*=96 H I-131 15% 17% 20% 22% 23% 25% 33% 46% 67% 90% I-132 16% 14% 12% 10% 8% 6% 1% 0% 0% 0% I-133 29% 33% 36% 39% 41% 42% 47% 46% 32% 10% I-134 15% 8% 4% 2% 1% 0% 0% 0% 0% 0% I-135 26% 27% 28% 28% 27% 26% 19% 8% 1% 0% Total 100% 100% 100% 100% 100% 100% 100% 100% 100% 100%
~~T corresponds with start of the release at shutdown or operating mix for fuel clad /melt scenarios, i.e.,~~
T* = 6 Hours is 6 hours post start of the release and shutdown.
Enclosure 2 to PLA-8077, Page 493 of560 NEP Technical Basis 16-001 Rev4 Page 8 of21 The URI system configuration for all the calculations in Table 1 is defined by the program version number and the encrypted site data file Unique ID code as shown in the image below. AhdutURL,
~~$ite; S$~S* {r;rsioii: 3)7.i.i ' ~.(#!!!rib: . §(;@~?}'~~
~~EnCl}'ptedS~t.imef-lle Name,. *. SSES* Dose Assessment OmaJanl~~
* *Enc:fypted Siiuroe file ,Unique-{El: ' 2854a981. *~ell, ~it~lrit~al)~~e(tifrte;Starni:t; * $.tJnQ.~;, Nov~~(il'. 10Z2 )0;'1~?,7' *Em:1ffeed.RleCreai:or .User.JO: v.1cooper *: -*. ,.c:***'** . .. F'm!,e$'Rie:{lyiobs,Proc4{}.dllj:
~~F!AscAL'Meteorological~~
":" **- ,.* *- .-., **,* , .... *.* -**. *' *~t* *RASgAL Puff Model Pro~-fiie (TADPUFF.40.dR); .8l61202f *
RASCALPlume:*ModelPro~.RleffADPLUME40.dfll:

B/6/2021 .*
Enclosure 2 to PLA-8077, Page 494 of 560 NEP Technical Basis 16-001 Rev 4 Page 9 of 21 C. Inputs and Assumptions The following assumptions and inputs were used in this Technical Basis: Input 1: Assume 100 net counts per minute or corrected counts per minute (ccpm) as minimum (user-related) limit of detection for a HP-210 probe. Input 2: SSES RP department calculated in HP Technical Bases (TB) 92-003 a pancake probe efficiency of 0.18% (i.e., a factor of 0.0018) for I-131. This calculation used a certified I-131 source spread out on an Iodine cartridge and measured by the pancake probe at 3 different times, in the same geometry as the field measurements. Note that revisions 1 through 3 of this document calculated a theoretical detector efficiency for a large range of the Iodine mix of 0.26%, including bothy and p radiation types. However, this value was calculated for various Iodine y energies for a 4 1t geometry. In reality, the cartridge - detector geometry is similar to a 2 1t geometry so the efficiency for y should have been half. Nevertheless, the detector efficiency for I-131 determined in HP TB 92-003 mimics the detector - cartridge geometry as well as includes an (National Laboratory certified) source. In addition, previous revision of this document assumed only one detector efficiency for the subsequent calculations. Similarly, the same is assumed in this revision. However, instead of using the theoretical detector efficiency calculated at 0.26% in the previous revisions, an empirical detector efficiency of 0.18% determined for I-131 is assumed for all other radionuclides in the mix. This assumption is valid for the following reasons:
This value was obtained using the field detector - cartridge geometry and a certified source.

It can be shown (see associated Excel spreadsheet, not reproduced in this document) that theoretically, the p and y efficiencies for all the other Iodines in the mix is greater than the detector efficiency for I-131. Therefore this is also a conservative assumption.

As shown in associated Excel spreadsheet, (not reproduced in this document), although correct theoretical detector efficiency can be calculated, the uncertainty associated with various individual detectors as well uncertainty associated with the (user) limit of detection described in Input 1, the conservative value determined in HP TB 92-003 is valid for the field team measurement conditions and associated geometry for the measurement.
In conclusion, several methodologies have been applied to determining the counting efficiency for a pancake GM probe for counting iodine activity collected on a cartridge for emergency field air sampling in the previous and current revision of this document. A certified source of I-131 was measured repeatedly with a result of 0.18% efficiency in the same geometry as for the field measurements. A separate (theoretical) method which used various time dependent mixes of Iodines and a published energy dependent efficiency curve indicates that the efficiency for all of the Iodines in the core mix considered here is higher than that of I131. However, given the optimal methodology of using
Enclosure 2 to PLA-8077, Page 495 of 560 NEP Technical Basis 16-001 Rev 4 Page 10 of 21 a certified source, the inherent uncertainties in field team air sample collection and counting, the intrinsic variation of efficiencies for same detector type and the variability of the radioiodine mix with time, the single I-131 efficiency derived from the certified source in HP TB 92-003 of 0.18% is used here as a simplified best estimate for the field team screening counting efficiency for pancake GM probes for Ioiodine emergency field air sample cartridge counting. Input 3: The following equation is used to evaluate the airborne activity concentration for a filter cartridge count rate using a HP-210 probe: netcpm Activity ( µCi/cc) = (1) ( 2 . 22 E+06)( Air Volume , L)( 1000~)( DE)( CE) L Where: Activity airborne activity concentration at filter cartridge sample location (µCi/cc) net cpm ccpm on a HP 210 pancake GM probe used at SSES and throughout the industry to measure the radioiodine air on a standard F&J AGZ-58 cartridge. The ccpm is the difference between the cartridge cpm and the background cpm, per SSES procedures. 2.22E+06 is a conversion factor for converting disintegrations per minute to µC.
~~= (3.7E+10 dis/sec per Ci)(60 sec/ min)(l Ci/ 106 µCi)~~
Air Volume is the air sample volume collected on the Silver Zeolite Iodine cartridge (cc). The SSES procedures currently assume 20 cf, i.e (2 cfm) * (10 min) * (30.483 cc / cf) * (1 L / 1000 cc ) or 566 L collected on the Silver Zeolite cartridge. DE 0.18% (see input 2 above) CE is the iodine collection efficiency and measures the quantity of the radioiodine retained in the cartridge. SSES RP department assumed 95% in their research performed under ACT CR-2016-15777, value that is consistent with industry benchmarking and subject papers. (see rev 1 through 3 of this document) By entering these values in equation (1), it results that 100 ccpm (assumed limit of detection on a HP-210 probe from Input 1) corresponds to a radioiodine gross activity of 4.65E- 8 µCi/cc for a 20 cf air sample collected on a silver zeolite cartridge. This value should be recalculated if detector, collection method or detection limit in Input 1 change at SSES. Note that this value is below NRCs I.9 criterion in NUREG-0654 Rev 1 which states: Each organization shall have a capability to detect and measure radioiodine concentrations in air in the plume exposure EPZ as low as l0-7 µCi/cc (microcuries per cubic centimeter) under field conditions. A
Enclosure 2 to PLA-8077, Page 496 of 560 NEP Technical Basis 16-001 Rev 4 Page 11 of 21 value of 215 ccpm for a 20 cf air sample collected on a silver zeolite cartridge would corresponds with this criterion, which is well above the assumed (user) detection limit of 100 ccpm. Input 4: Used Dose Conversion Factors (DCFs) for adult thyroid CDE from the URI code. URI is currently using ICRP26/30 adult DCFs (see Table C.9 in NEP Technical Basis 23-001) and these are the same as DCFs used in EPA 400 (1992) (see Table 5-2) and in accordance with the SSES Emergency Plan. These conversion factors are listed in Table 2. Input 5: Used adult breathing rates from URI that are the same as those listed in in EPA 400 (1992). This value is shown in Table 2. Table 2: Adult Thyroid DCFs used in URI code BR, cc / h DCF, mrem / Ci I-131 I-132 I-133 I-134 I-135 1.20E+06 1.08E+03 6.62E+00 1.80E+02 1.07E+00 3.13E+01 If any of the DCFs or BR factors change, this document need to change. Examples include but are not limited to implementation of ICRP 90 or 103 or EPA 400 (2017) in URI. Input 6: To determine the Child Thyroid CDE, URI calculates a child to adult ratio of 2.15 for the initial radioiodine mix and information from NUREG 1940 Supplement 1 Figure 3.5 and Table 3-2 (see Section A.9 in NEP Technical Basis 23-002). Because of code limitations, this value is kept constant for any other mixes and thus, after calculating the adult thyroid CDE, the code reports the Child Thyroid CDE by multiplying this ratio with the adult thyroid CDE. To account for radioactive decay after reactor shutdown, this technical basis adjusted the child to adult ratio by the method described in Attachment A. The results are shown in Table 3 and reinforced the fact that the URI method to keep this ratio constant is valid, as there is little variation between child to adult ratios for I-131 only and the initial mix at T=0. Table 3: Child to Adult Ratios as a function of reactor Shutdown time calculated based on the method described in Attachment B T*=0 T*=1 H T*=2 H T*=3 H T*=4 H T*=5 H T*=6 H T*=12 H T*=24 H T*=48 T*= 96 H Only I-131 2.12 2.11 2.11 2.10 2.10 2.10 2.09 2.07 2.04 2.01 1.98 1.96 Note that the ratio of 2.15 calculated by URI for the initial mix is in agreement with the value calculated by the method described in Attachment A corresponding with T=0. If any of the DCFs or Iodine mixes change, this document needs to change.
Enclosure 2 to PLA-8077, Page 497 of 560 NEP Technical Basis 16-001 Rev 4 Page 12 of 21 Input 7: Exposure duration of 1 hour per EAL requirements shown in item 3 in Purpose section. If the EAL criteria change, this document needs to be updated. Input 8: Using the corresponding activity in air for each radioiodine, the adult thyroid CDE corresponding to various times after reactor shutdown is calculated based on the following formula: Adult Thyroid CDE ( t ) = ( ( ) ) (2) where i are the 5 Iodines of interest, texp is the exposure time assumed to be one hour (see Input 7) and Ai(t) corresponds to the radionuclide of interest at the associated time in Table 4 below (Activity in air column). Input 9: The child thyroid CDE is obtained by multiplying the adult Thyroid CDE from Input 8 with the child to adult ratio calculated in Input 6 (Table 3) for the radioiodine mixes of concern.
Enclosure 2 to PLA-8077, Page 498 of 560 NEP Technical Basis 16-001 Rev 4 Page 13 of 21 D. Method The following method is employed in development of this document and can be used as guidance for further changes if criteria discussed in the Sections B and C are met:
1. Determine the need to run URI calcs to check whether the correct mixes were implemented.

a. If this is necessary, run calculations per methods described in Section B.
~~(1) Update or expand Table 1, if necessary.~~
2. Determine the need to update Section C and perform updates in Attachment A or the Inputs described in Section C, if necessary. Examples when this step is appropriate were provided in Section C.

3. Distribute the gross Iodine concentration corresponding to 100 ccpm calculated in Input 3 using the distributions shown in the last columns in Table 1 for URI clad damage or fuel melt iodine mixes.

4. Calculate Adult Thyroid CDE using values in Table 2 and the results in Step 3

a. Summarize step 3 and 4 calculations in Table 4.

5. Calculate Child Thyroid CDE per the method in Attachment A (see equation A-2 and child to adult ratios in Table 3 for all cases in Step 3 and Input 9).

6. Choose and justify an appropriate adult and child dose conversion factor (DCF) in mrem/h per ccpm.

7. Based on Step 5,

a. Determine whether the NRCs criterion in Input 3 of 1x10-7 µCi/cc of gross Iodine concentration is met or the detector or collection method needs to change to meet this criterion

b. Once a. above is met, determine the ccpm value corresponding to the EAL values

c. Determine the start of field monitoring thyroid CDE tracking as shown in the Purpose section.

d. Determine I-131 percentage of the gross Iodine mix to input in URI.

8. If any values in Step 7 changed, update applicable EP procedures and inform the URI code developer of the change.
Enclosure 2 to PLA-8077, Page 499 of 560 NEP Technical Basis 16-001 Rev 4 Page 14 of 21 E. Results Step 1 was performed the results are shown in Table 1. Step 2 was performed and all sections were updated. In addition, Attachment A was created as part of Revision 4 of this document. Steps 3 The gross Iodine activity calculated in Input 3 was distributed for individual Ines of interest, in accordance with radioiodine mix in the last columns in Table 1 above. The results are reproduced in the second through 11th column in Section I of Table 4 below. The last column corresponds to the 100% I-131 concentration, which will be the limiting value for all calculations in the respective column after all other Iodines decay away (after a little over 6 days). Steps 4 and 5 Table 2 and equation (2) (see Inputs 5, 6 and 8) were used to calculate the adult thyroid CDE corresponding to one hour of exposure for each of the activity distribution corresponding to Section I in Table 4. Equation A-2 and Table 3 (see Input 6) were used to determine a child thyroid CDE corresponding to one hour of exposure for each of the activity distribution in Section I of Table 4. The results are shown in Section II of Table 4. Step 6 A DCF for adult and child in mrem/h per ccpm was calculated in Section III of Table 4, respectively. This data shows that adult DCF varies by 6 times, from the 9.9E-2 mrem/h per ccpm corresponding to no reactor shutdown (T=0) to 60.2E-2 mrem/h per ccpm corresponding to the I-131 only at about 144 h after reactor shutdown. This is expected as I-132, I-134 and I-134 decays much more rapidly as compared with I-131 and I-133 and eventually only I-131, with the highest DCF, will remain to deliver thyroid dose. Similarly, the data shows that the child DCF also varies by 6 times, from the 0.21 mrem/h per ccpm corresponding to no reactor shutdown (T=0) to the maximum value of 1.18 mrem/h per ccpm corresponding to dose delivered only by I-131. Note that the I-131 DCF is used here only as the maximum possible value for this factor. Step 7 The EAL and FMT Dose Tracking Limits, ccpm, were calculated in Section IV of Table 4 using criteria in Section A and DCFs obtained in Section III of Table 4.
Enclosure 2 to PLA-8077, Page 500 of 560 NEP Technical Basis 16-001 Rev 4 Page 15 of 21 For the final guidance, the following values were considered (see Section V in Table 4):
Average of the limits in Sections III and IV of Table 4 (121 ccpm);

Average of the limits for the first 48 hours after reactor shutdown from Sections III and IV of Table 4 (136 ccpm);

Arbitrary limit of 100 ccpm which is the user detection limit in Input 1 and coincidentally the value corresponding to 12 hours from the reactor shutdown.
By examining Section IV in Table 4, if the first value above (121 ccpm) is selected as final guidance, SSES would declare an EAL earlier for the first 5 h (conservative) and late for greater than 6 hours and beyond. The latter is not desirable and thus this value was not considered as the final guidance. Similarly, for the second value above (136 ccpm), SSES would declare earlier for the first 3 h (conservative) and late for greater than 5 hours and beyond. However, if the third arbitrary value of 100 ccpm is selected, SSES would declare earlier for the first 6 h (conservative) and late for greater than 24 to 48 hours and beyond. As beyond 24 to 48 hours a more detailed analysis of the cartridge is possible or the release is expected to be stopped, this value was selected as the final guidance. Therefore, a unique value of 0.52 mrem/h per ccpm was selected for the child DCF and a 0.25 mrem/h per ccpm was selected for the adult DCF in this technical basis. As discussed in Section A (see Table 1), I-131 is expected to account for approximately 33% of the gross Iodine collected on the cartridge. Based on the EAL and DA procedures, the following triggers (highlighted), corresponding ccpm and DCFs are calculated and summarized in Section V of Table 4. As discussed in step 6 above, the selected 100 ccpm value is based on a conservative but reasonable mix of Iodines corresponding to 12 hours after reactor shutdown, is valid for up to 48 hours after the reactor shutdown and also represents the user limit of detection for the HP-210 probe. Step 8 All values from step 7 above were updated in the EP procedures. In addition, the URI developer was informed that I-131 approximately accounts for 33% in the expected gross Iodine collected on a cartridge. This value was entered in URI and is used in the back calculation (field team) method (see Table B.1.1a in NEP TB 23-002).
Enclosure 2 to PLA-8077, Page 501 of 560 NEP Technical Basis 16-001 Rev 4 Page 16 of 21 Table 4: Activity and Thyroid CDE Rate for Fuel Damage Corresponding to 4.65E- 8 µCi/cc of gross Iodine activity (100 ccpm on a cartridge) as a Function of Rx Shutdown and Corresponding Adult and Child Thyroid CDE rates, DCFs and EAL criteria T*=144 T*=0 T*=1 H T*=2 H T*=3 H T*=4 H T*=5 H T*=6 H T*=12 H T*=24 H T*=48 H T*= 96 H (Only I-131) Nuclide Section I: Activity, µCi/cc I-131 5.44E-09 6.80E-09 8.12E-09 9.15E-09 1.00E-08 1.08E-08 1.16E-08 1.53E-08 2.15E-08 3.09E-08 4.16E-08 4.65E-08 I-132 7.80E-09 7.37E-09 6.50E-09 5.44E-09 4.42E-09 3.56E-09 2.82E-09 6.25E-10 2.47E-11 2.79E-14 2.33E-20 I-133 1.10E-08 1.35E-08 1.56E-08 1.69E-08 1.81E-08 1.90E-08 1.96E-08 2.18E-08 2.14E-08 1.51E-08 4.87E-09 I-134 1.17E-08 6.95E-09 3.77E-09 1.93E-09 9.62E-10 4.75E-10 2.30E-10 2.72E-12 3.02E-16 2.75E-24 1.47E-40 I-135 1.05E-08 1.19E-08 1.26E-08 1.31E-08 1.30E-08 1.27E-08 1.22E-08 8.82E-09 3.67E-09 4.67E-10 4.84E-12 Total 4.65E-08 4.65E-08 4.65E-08 4.65E-08 4.65E-08 4.65E-08 4.65E-08 4.65E-08 4.65E-08 4.65E-08 4.65E-08 4.65E-08 Section II: Corresponding Adult and Child CDE Rate, mrem/h 1.44E+0 Adult 9.90E+00 1.22E+01 1.60E+01 1.74E+01 1.86E+01 1.97E+01 2.48E+01 3.25E+01 4.33E+01 5.50E+01 6.02E+01 1 3.04E+0 Child 2.10E+01 2.58E+01 3.37E+01 3.66E+01 3.91E+01 4.13E+01 5.15E+01 6.65E+01 8.69E+01 1.09E+02 1.18E+02 1 Section III: Adult and Child DCFs, mrem/h per ccpm Adult 9.90E-02 1.22E-01 1.44E-01 1.60E-01 1.74E-01 1.86E-01 1.97E-01 2.48E-01 3.25E-01 4.33E-01 5.50E-01 6.02E-01 Child 2.10E-01 2.58E-01 3.04E-01 3.37E-01 3.66E-01 3.91E-01 4.13E-01 5.15E-01 6.65E-01 8.69E-01 1.09E+00 1.18E+00 Section IV: EAL and FMT Dose Tracking Limits, ccpm Alert 238 193 165 148 137 128 121 97 75 58 46 42 SAE 2384 1935 1647 1482 1368 1280 1212 971 752 575 461 423 GE 23842 19345 16471 14821 13679 12796 12119 9705 7521 5752 4606 4225 FMT 10102 8179 6947 6238 5748 5366 5073 4024 3073 2307 1819 1661 Section V: Final Guidance Average Average (first 48 hours) Final Alert Limit, ccpm 121 136 100 SAE Limit, ccpm 1207 1361 1000 GE Limit, ccpm 12074 13605 10000 FMT Dose Tracking Limit, ccpm 5045 5706 4000 Corresponding Adult DCF, mrem/h per ccpm 0.27 0.21 0.25 Corresponding Child DCF, mrem/h per ccpm 0.55 0.43 0.52
Enclosure 2 to PLA-8077, Page 502 of 560 NEP Technical Basis 16-001 Rev 4 Page 17 of 21 F. Conclusions The radioiodine mix used in this revision of the technical basis was aligned with the mix used in URI and its associated documentation (NEP TB 23-001 and 23-002) and is similar with the mix developed for Atrium 11 fuel in EC-RADN-1164. The dose conversion factors were also aligned with the ones used in URI and EPA 400 (1992), as directed by the Emergency Plan. This technical basis showed that, to be able to implement the Alert EAL (50 mrem child thyroid CDE for 1 hour of exposure) SSES needs to collect at least 20 cf of air on a silver zeolite cartridge. This can be achieved with the current equipment installed in the three monitoring vehicles (ALPHA, BRAVO and OSCAR equipment for manual air sample) as well as per the current field team monitoring procedures. Similarly with previous revisions, a fixed detector efficiency was assumed in this document as well. However, an empirical detector efficiency of 0.18%, as determined in HP Technical Bases 92-003, was used instead of the theoretical one calculated in revisions 1 through 3. This value was representative of I-131 but it has the advantage that it was calculated based on a National Laboratory certified source spread on an Iodine cartridge and under the same geometry expected for the field measurements. This value is also conservative as it can be shown that the efficiencies for all the other Iodines considered in this document can only increase. Uncertainty in DE has large effects on the Alert level and it propagates to SAE and GE as well, as the same fixed DE value is also used to determine those levels as well. In addition, 100 ccpm is the usual detection limit for the pancake probe that can be identified by the user. As such 100 ccpm on the frisker was selected for the Alert threshold. As it turns out, this value corresponds to the values calculated for 12 hours after reactor shutdown, which is consistent with revision 3 of this document, as well as to the final selection for the Alert threshold. When counting the user detection limit for the pancake probe and the uncertainty in the detector efficiencies, on top of the uncertainty on Iodine mix percentages, this value is valid over a large range of hours after shutdown (from about 1 hour and up to about 24 to 48 hours after reactor shutdown). Note that this threshold should not be used after more than 48 hours after reactor shutdown as is starting to underestimate the dose. For any time after 48 hours after SD, a more detailed analysis should be performed on the cartridge as I- 131 starts to predominate and / or a higher volume of air should be collected (about 2 times more or 40 cf) in order to use the same threshold. This technical basis also showed that for 20 cf of air collected through a silver zeolite cartridge, the associated activity for 100 ccpm corresponds to 4.65E- 8 µCi/cc of gross iodine concentration in the air, below the NRCs I.9 criterion in NUREG-0654 Rev 1 of l0-7 µCi/cc under field conditions. Revisions 0 to 3 of this document stated that 100 ccpm on the Iodine cartridge should be the trigger for the release in progress at SSES. This document corrects this error since, as discussed here, this value represents the trigger for the Alert which is approximately 50 mrem / h child thyroid CDE rate, i.e., well beyond a release in progress criterion. Therefore, the trigger for the release in progress is set to 100
Enclosure 2 to PLA-8077, Page 503 of 560 NEP Technical Basis 16-001 Rev 4 Page 18 of 21 ccpm on the pancake probe as is the common practice for contamination identification throughout the industry. The release in progress exposure rate trigger of 0.1 mR / h remains unchanged. Based on a conservative iodine mix corresponding to the 12 hours after shutdown, when release is expected to be terminated, a unique and conservative value of 0.25 mrem/h per ccpm was calculated fo r the Adult DCF and a value of 0.52 mrem/h per ccpm was calculated for the child DCF. The EAL value corresponding to the child thyroid CDE greater than 50 mrem for one hour of inhalation would conservatively correspond to about 100 ccpm. In addition, AS1(3) and AG1(3) are set to 1,000 ccpm and 10,000 ccpm respectively in all affected EP procedures. In addition, a conservative value for 1 rem adult thyroid CDE for one hour of exposure was calculated to correspond to about 4,000 ccpm. This value can be used to begin tracking thyroid doses for the field team members, per applicable EP procedures. All applicable EP procedures should be aligned with these values. Given the fact that all limits in this research are much smaller than 100,000 ccpm, a dead time correction factor for the Ludlum I HP-210 system is not required. I-131 is expected to conservatively account for approximately 33% of the gross Iodine collected on the cartridge and the value was communicated to URI developer and entered in URI for back calculation (field team) method (see Table B.1.1a in NEP TB 23-002). The NEP Technical Basis 92-004 and 94-001 were deleted and replaced by this NEP Technical Basis.
Enclosure 2 to PLA-8077, Page 504 of 560 NEP Technical Basis 16-001 Rev 4 Page 19 of 21 References
1. SSES Emergency Plan

2. HP-TP-720, Airborne Concentration Sampling And Evaluation. (historical, not used any more)

3. HP Technical Bases 92-003, Detection Efficiency of Pancake GM For I-131 On Face Loaded Cartridges

4. NEP Technical Basis 92-004, Air Sample Frisker Guidelines (historical; replaced by this document).

5. NEP Technical Basis 94-001, EOF Gamma Spectroscopy System Dose Conversion Factors (historical; replaced by this document).

6. SSES RP Department calculations performed under ACT-01-CR-2016-15777

7. EC-RADN-1002, SSES Plant Specific Input For MIDAS Computer Program. (historical; valid for Atrium 10 fuel; replaced by NEP TB 21-001 for Atrium 11 fuel)

8. EC-RADN-1140, Evaluation Of Activity Source Term Distribution For The MIDAS Computer Program. (historical; valid for Atrium 10 fuel; replaced by NEP TB 21-001 for Atrium 11 fuel)

9. EC-RADN-1126, CRHE & Offsite FHA/EHADoses AST and FSAR Table 15.7-16.

10. EC-RADN-1164, Default Accident Activity Releases for the MIDAS Computer Code

11. NEP Technical Basis 21-001, Susquehanna MIDAS Data Specification (historical, replaced by NEP Technical Basis 23-001 and NEP Technical Basis 23-002)

12. NEP Technical Basis 23-001, Requirements Specification - Unified RASCAL Interface Version 3.7

13. NEP Technical Basis 23-002, Unified RASCAL Interface Requirements Specification -
~~Susquehanna Site Annex Version 3.7~~
14. NUREG-0654 Rev 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants

15. NUREG-1228, Source Term Estimation during Incident Response to Severe Nuclear Plant Accidents

16. NUREG-1940, RASCAL 4: Description of Models and Methods

17. NUREG-1940, Supplement 1, RASCAL 4.3: Description of Models and Methods
Enclosure 2 to PLA-8077, Page 505 of 560 NEP Technical Basis 16-001 Rev 4 Page 20 of 21 Attachment A Method to Calculate Child to Adult Thyroid CDE Ratio Adult Thyroid CDE [mrem] = [ ] (A-1) Where: BRa is the adult breathing rate (see Table 2) is the adult thyroid dose conversion factor for radionuclide i (see Table 2) Ci is the radionuclide i concentration in air and texp is the exposure time Equation A-1 is valid with the assumption that Ci does not change during the exposure time which is assumed to be 1 h for this calculation. This is a conservative assumption. Child Thyroid CDE [mrem ] = Rc;a Adult Thyroid CDE [mrem] (A-2) where is the child to adult ratio to be determined here. Li BRc[cc/h]DCF{[mrem/ µcJci[µCifcc]texp [ h ] At the same time, = (A-3) Li BRa[cc/ h]DCF?[mrem;µci]ci[µCifcc]texp [ h ] Where: BRc is the child breathing rate DCF.C i is the child thyroid dose conversion factor for radionuclide i As discussed in Section C (see Input 6) of this technical basis, to determine the Child Thyroid CDE, URI calculates a child to adult ratio of 2.15 for the initial radioiodine mix and information from NUREG-1940 Supplement 1 Figure 3.5 and Table 3-2. For completion, the NRC calculation is reproduced in Table A-1. Table A-1: NUREG-1940 suppl 1 calculations Table 3-2 in NUREG-1940 suppl 1 calculations Breathing Dose Coefficients (Sv/Bq) Sum of (BR x DCFi), Age Rate (m3/s) I-131 I-132 I-133 I-134 I-135 Sv/Bq per m3/s 100 d 5.28E-05 2.52E-06 3.40E-08 6.78E-07 7.02E-09 1.39E-07 1.78E-10 1y 9.72E-05 2.47E-06 3.03E-08 6.12E-07 6.24E-09 1.24E-07 3.15E-10 5y 1.58E-04 1.40E-06 1.57E-08 3.18E-07 3.23E-09 6.43E-08 2.85E-10 10 y 3.11E-04 7.10E-07 7.02E-09 1.42E-07 1.44E-09 2.88E-08 2.77E-10 15 y 3.83E-04 4.59E-07 4.53E-09 9.09E-08 9.30E-10 1.85E-08 2.20E-10 20 y 4.17E-04 2.93E-07 2.87E-09 5.70E-08 5.90E-10 1.17E-08 1.52E-10 Figure 3.5, Child (1y) / Adult Ratio, ri 1.96E+00 2.46E+00 2.50E+00 2.47E+00 2.47E+00 Attachment A Page A-1 of A-2
Enclosure 2 to PLA-8077, Page 506 of 560 NEP Technical Basis 16-001 Rev 4 Page 21 of 21 First note that the highest dose for child is expected for a 1-year old as shown by last column where breathing ratios were multiplied by the corresponding DCFs and then summed up in accordance with equation A-1 with child DCFs and breathing ratio factors from ICRP 60. Therefore, as discussed in the NUREG-1940 Supplement 1, the 1 year old child was conservatively used to calculate the child to adult ratios in the last row in Table A-1. Second, note the that the BR and DCFs are from ICRP 60 and NOT from ICRP 30 as currently used in URI. However, this has little influence on the ratios calculated in the last row and therefore this child to adult ratios corresponding to each nuclide will be used henceforth. BR 1 YDCF.1 y Therefore, = ! ! or, with notations from equations A-1 and A-3, BRfDCF? BRcDCF{ =riBRaDCFt (A-4) Li riBRa[cc /h]DCFia[mrem;µcJci[µCifcc]texp [ h ] Plugging equation A-4 into A-2 one gets = , and LiBRa[cc;h]DCFia[mrem/µcJci[µCifcc]texp [ h ] as BRa and texp are constants, equation above simplifies to
~~= (A-5)~~
~~If multiply both numerator and denominator in Eq A-5 with equation A-5 becomes:~~
~~~ -r t*f t*DCFP[mrem; L...t t µCi*] = (A-6) ~-f*DCF*a[mrem; L...t t t µCi*]~~
where = . As assumed throughout this technical basis, the activities, release rates and radionuclide concentration are directly proportional with the radioiodine mixes calculated in Table 1. At this time, all quantities in Equation A-6 are known, as follows,
fi are the radioiodine mixes calculated in Table 1 for various times since reactor shutdown,

ri are calculated in the last row of Table A-1 and

is the adult thyroid dose conversion factor for radionuclide i in Table 2 Attachment A Page A-2 of A-2
Enclosure 2 to PLA-8077, Page 507 of 560 NEP TB 16-001 R4 Final Audit Report 2023-08-16 Created: 2023-08-09 By: Adrian Miron (Adrian.Miron@TalenEnergy.com) Status: Signed Transaction ID: CBJCHBCAABAA1T4pAcYnbl-pcz1 vdcM5nHOZsKail5ME "NEP TB 16-001 R4" History ~ Document created by Adrian Miron (Adrian.Miron@TalenEnergy.com) 2023-08 12:49:59 PM GMT- IP address: 50.122.98.202 g Document emailed to Shane Jurek (shane.jurek@talenenergy.com) for signature 2023-08 12:51 :51 PM GMT ~ Email viewed by Shane Jurek (shane.jurek@talenenergy.com) 2023-08 1:05:00 PM GMT- IP address: 73.18.57.68 0o Document e-signed by Shane Jurek (shane.jurek@talenenergy.com) Signature Date: 2023-08-09-1 :05:26 PM GMT-Time Source: server- IP address: 73.18.57.68 [4 Document emailed to Jay Barnes Uay.barnes@talenenergy.com) for signature 2023-08 1:05:27 PM GMT ~ Email viewed by Jay Barnes Uay.barnes@talenenergy.com) 2023-08 1:48:02 PM GMT- IP address: 50.122.98.202 g New document URL requested by Jay Barnes Uay.barnes@talenenergy.com) 2023-08 1:48:09 PM GMT- IP address: 50.122.98.202 0'0 Document e-signed by Jay Barnes Uay.barnes@talenenergy.com) Signature Date: 2023-08 1:49:22 PM GMT - Time Source: server- IP address: 50.122.98.202 G Agreement completed. 2023-08 1:49:22 PM GMT Adobe Acrobat Sign
Enclosure 2 to PLA-8077, Page 508 of 560
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Enclosure 2 to PLA-8077, Page 512 of560 Miron, Adrian From: Baracco, David <dbaracco@pa.gov> Sent: Monday, July 31, 2023 10:08 AM To: Shoup, Jessica; NUC, SanSilva; Linkimer, Dave Cc: Kuchmay, Nicholas D; Miron, Adrian; NUC, TMull
~~Subject:~~
RE: [External] Concurrence on change to SSES ENR Form Follow Up Flag: Follow up Flag Status: Flagged [External Email] Good morning Jessica, Sorry for the late response. BRP does not have any concerns and is aligned with the change. Dave From: Shoup, Jessica <Jessica.Shoup@talenenergy.com> Sent: Monday, July 31, 2023 10:02 AM To: Silva, Sandra <sansilva@pa.gov>; Linkimer, Dave <Dave.Linkimer@talenenergy.com>; Baracco, David
~~<d ba racco@pa.gov>~~
~~Cc: Kuchmay, Nicholas D <Nicholas.Kuchmay@talenenergy.com>; Miron, Adrian <Adrian.Miron@talenenergy.com>; Mull, Robert <robemull@pa.gov>~~
~~Subject:~~
RE: [External] Concurrence on change to SSES ENR Form Good morning Dave, I wanted to follow up on the call last week and ensure that we have DEP/BRP concurrence before we proceed any further with the changes to our Emergency Notification Report. Please let us know if there are any concerns with moving forward as proposed. Thank you, Jessica Shoup Emergency Preparedness Supervisor I Talen Energy Jessica.Shoup@TalenEnergy.com Office: 570.542.6556 I Mobile: 570.336.8089 252 Confers Lane I Berwick, PA 18603 TALEN4
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EM!>LU~fR!, ENERGY From: Silva, Sandra <sansilva@pa.gov> Sent: Friday, July 28, 2023 7:57 AM To: Linkimer, Dave <Dave.Linkimer@talenenergy.com>; Baracco, David <dbaracco@pa.gov> Cc: Shoup, Jessica <Jessica.Shoup@talenenergy.com>; Kuchmay, Nicholas D <Nicholas.Kuchmay@talenenergy.com>; 1
Enclosure 2 to PLA-8077, Page 513 of560 Miron, Adrian <Adrian.Miron@talenenergy.com>; NUC, TMull <robemull@pa.gov>
~~Subject:~~
RE: [External] Concurrence on change to SSES ENR Form [External Email] Good morning Dave, PEMA concurs with the change. Thank you for the update. Regards, g~g~,q Sandra B. Silva I Planning Administrator (Division Chief) Pennsylvania Emergency Management Agency Nuclear Power Plants Division Bureau of Technological Hazards Phone: 717.651.2235 I Cell: 717.303.7563 From: Linkimer, Dave <Dave.Linkimer@talenenergy.com> Sent: Thursday, July 27, 2023 3:35 PM To: Silva, Sandra <sansilva@pa.gov>; Baracco, David <dbaracco@pa.gov> Cc: Shoup, Jessica <Jessica.Shoup@talenenergy.com>; Kuchmay, Nicholas D <Nicholas.Kuchmay@talenenergy.com>; Miron, Adrian <Adrian.Miron@talenenergy.com>; Mull, Robert <robemull@pa.gov>
~~Subject:~~
[External] Concurrence on change to SSES ENR Form ATTENTION: This email message is from an external sender. Do not open links or attachments from unknown senders. To report suspicious email, use the Report Phishinq button in Outlook. Sandra and David, Per our discussion on July 27, 2023 regarding the implementation of URI at SSES which will require a change to our ENR form. Particularly Box 6 of the form will be revised to add a selection for 10 or 60 meter met tower for Wind Direction and Wind Speed. This change is to insure that the State is aware of the met tower height that SSES used for Dose Assessment and to determine the PAR. If you concur with this change please acknowledge in a reply to this email. Thank you, Dave Linkimer Sr. Emergency Preparedness Coordinator I Talen Energy Dave. Lin kimer@talenenergy.com Office: 570.542.3535 I Mobile: 412.720.2940 252 Confers Ln. I Berwick, PA, 18603 www.Susq uehanna Nuclear.com TALEN.t f'IMEnlCA'S lu1loe, E.MPL(J)'£RS ENERGY 2
Enclosure 2 to PLA-8077, Page 514 of 560 The information contained in this message is intended only for the personal and confidential use of the recipient(s) named above. If the reader of this message is not the intended recipient or an agent responsible for delivering it to the intended recipient, you are hereby notified that you have received this document in error and that any review, dissemination, distribution, or copying of this message is strictly prohibited. If you have received this communication in error, please notify us immediately, and delete the original message. ATTENTION:Thisemailoriginatedfromoutsideoftheorganization. Donotopenattachmentsorclickonlinksunlessyourecognizethesenderandknowthecontentissafe. The information contained in this message is intended only for the personal and confidential use of the recipient(s) named above. If the reader of this message is not the intended recipient or an agent responsible for delivering it to the intended recipient, you are hereby notified that you have received this document in error and that any review, dissemination, distribution, or copying of this message is strictly prohibited. If you have received this communication in error, please notify us immediately, and delete the original message. ATTENTION:Thisemailoriginatedfromoutsideoftheorganization. Donotopenattachmentsorclickonlinksunlessyourecognizethesenderandknowthecontentissafe. 3
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Enclosure 2 to PLA-8077, Page 524 of 560

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PLA-8077, Emergency Plan Revision 67 (PLA-8077)

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