ML18018B768

Revised Plant Emergency Procedures,Including 1.0 Re Emergency Classifications & Control Procedures & 2.0 Re Emergency Mgt Guides.Three Oversize Figures Encl.Aperture Cards Available in PDR

ML18018B768
Person / Time
Site:	Harris
Issue date:	09/12/1984
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18018B767	List: ML18018B766 ML18018B768
References
NLS-84-393, PROC-840912, NUDOCS 8409170398
Download: ML18018B768 (531)

Text

APR006 84091 0398 1 0

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CAROLINA POWER & LIGHT COHPANY~p~ (

SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART S PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: P-001 TITLE: MANUAL URPOSE AND USE REVISION APPROVED:

Signature Dat TITLE:

'EP-001 Rev. 0 Page 1 of 9

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4

APR006 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

2.1 . Controlling References 4 2.2 Other References 3.0 RESPONSIBILITIES 5 3.1 Plant General Manager 5 3.2 Assistant to the Plant General Manager 5 3.3 Plant Emergency Preparedness Specialist 5 3' Users 6 4.0 DEFINITIONS/ABBREVIATIONS 6 4.1 Terminology 6 4.2 Acronyms 6 5.0 GENERAL 6 5.1 Manual Organization 6 5.2 Color Coding 7 5.3 Miscellaneous 8 6.0 INITIATING CONDITIONS 8 7.0 PRECAUTIONS/LIMITATIONS 8 8.0 SPECIAL TOOLS AND EQUIPMENT 8 9.0 PROCEDURE STEPS 8 10.0 DIAGRAMS/ATTACHMENTS 8

1. Acronyms 9 PEP-001 Rev. 0 Page 2 of 9

APR006 LIST OF EFFECTIVE PAGES LEP

~Pa e Revision 1 thru 9 0 PEP-001 Rev. 0 Page 3 of 9

APR006 1.0 . PURPOSE The purpose of this portion of the plant operating manual is to provide a set of Plant Emergency Procedures (PEPs) to implement the emergency actions described in the Emergency Plan for the Shearon Harris Nuclear Power Plant (SHNPP), Plant Program PLP-201. This portion of the manual provides the SHNPP staff and supporting agencies with specific instructions, forms and data to ensure prompt dctions, proper notifications, and effective communications during potential and actual emergency conditions. It also denotes the means by which emergency preparedness is maintained by periodic training, exercises, and equipment inventories and checks. During and subsequent to an emergency, this manual will provide a means for recording the actions completed in fulfillment of established emergency response requirements'.0 REFERENCES This section contains a list of documents used in the development of the Plant Emergency Procedures (PEPs). By adhering to the require-ments of the Plant Emergency Procedures, compliance is achieved for applicable portions of the Controlling References. The guidance and recommendations contained in the other references have been incor-porated into the Plant Emergency Procedures as considered useful and appropriate.

2.1 CONTROLLING REFERENCES

1. Shearon Harris Nuclear Power Plant Emergency Plan, PIP-201

2. Carolina Power Ec Light Company Corporate Emergency Plan

3. Code of Federal Re lations, Part 50, Section 50.47, "Emergency Plans.

4. Code of Federal Re ulations, Part 50, Section 50.54(g), "Con-ditions of License.'.

Code of Federal Re ulations, Part 50, Appendix E, "Emergency Planning and Preparedness for Production and Utilization Facilities."

6. SHNPP Plant Administrative Manual, Sections 4 and 5.2.5.

7 ~ AP-002, "Plant Conduct of Operations"

8. AP-006, "Procedure Review and Approval" 2.2 OTHER REFERENCES

1. 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," November 1980.

PEP-001 Rev. 0 Page 4 of 9

APR006

2.0 REFERENCES

2.2 OTHER REFERENCES (Cont'd)

2. NUREG-0737, Supplement 1, "Requirements for Emergency Response Capability."

3.0 RESPONSIBILITIES This section presents responsibilities for development of Plant Emergency Procedures. Specific responsibilities for implementing the PEPs are assigned in individual procedures.

3.1 PLANT GENERAL MANAGER The Plant General Manager has overall responsibility for assuring the development, review, approval, maintenance, testing, and imple-mentation, when necessary, of the Plant Emergency Procedures.

3.2 ASSISTANT TO THE PLANT GENERAL MANAGER The Assistant to the Plant General Manager is responsible for maintaining, controlling, and distributing the Plant Emergency Procedures. He reviews the Plant Emergency Procedures against the controlling reference documents to determine if procedure revisions are needed in accordance with Section 5.0 of the Emergency Plan, AP-002 and AP-006. He approves all Plant Emergency Procedures and approves the list for distribution.

3.3 PLANT EMERGENCY PREPAREDNESS SPECIALIST The Plant Emergency Preparedness Specialist is responsible for developing, implementing, and maintaining an Emergency Preparedness Program for the Harris Plant which ensures that a "State of Readi-ness" is maintained in accordance with the plant and corporate emergency plans and regulatory requirements by:

~ Reviewing and revising the plant Emergency Plan to ensure regulatory compliance, incorporating provisions of the Corpo-xate and plant plans into the pxogram;

~ Supporting the licensing process by addressing NRC questions, SER open items and ASLB hearing contentions; Planning, scheduling, and conducting on-site and outside agency training; Preparing, executing,, and evaluating drill plans and exercises to test preparedness;

~ Ensuring that emergency facilities, equipment, and supplies are available and in operational readiness;

~ Developing plant specific implementation procedures to ensure procedural control;

~ Effectively interfacing with -federal, state, and local govern-mental and law enforcement agencies and plans.,

PEP"001 Rev. 0 Page 5 of 9

APR006 3.0 RESPONSIBILITIES 3.4 USERS Emergency Organization members are responsible for suggesting or recommending constructive improvements to the Plant Emergency Procedures based on operating experience or on use during drills and exercises. Users should make recommendations known through their supervisors or directly to the Plant Emergency Preparedness Specialist.

4.0 DEFINITIONS ABBREVIATIONS 4.1 TERMINOLOGY The following procedural terminology is used throughout the Plant Emergency Procedures:

1. "Mill"or "Shall" denotes a requirement. The action will be accomplished in the manner stated.

2. "Should" denotes a recommendation. The action will be accom-plished in the manner stated or by an equally effective alter-nate method.

3. "May" denotes permission - .neither a recommendation nor a requirement.

4. Statements of fact in the active present tense are used to assign responsibilities or to describe actions required by procedures or documents external to this manual.

Examples of active present tense verbs are; maintain, review, analyze, prepare, and distribute.

4.2 ACRONYMS Acronyms and abbreviations common to emergency planning use are provided as Attachment to this procedure.

5. 0 GENERAL 5.1 MANUAL ORGANIZATION The Plant Emergency Procedures are organized to facilitate immediate use by both on-site and off-site emergency response personnel.

1. Section 0, "Plant Emergency Procedures Introduction," denoted by'rocedures numbered 001-099, is the Introduction. This section describes the proper use of the manual.

PEP-001 Rev. 0 Page 6 of 9

APR006 5.0 GENERAL 5.1 MANUAL ORGANIZATION (Cont'd)

2. Section 1, "Emergency Classifications and Control Procedures,"

denoted by procedures numbered 100-199, consists of step-by-step immediate action procedures for the Control Room, Technical Support Center, and the Site Emergency Coordinator.

These include the classification scheme used by plant personnel in reporting potential emergency events, evaluating their extent, classifying them as an Unusual Event, Alert, -Site Emergency, General Emergency or as an event of lesser safety significance, and some methods for controlling the situation.

3. Section 2, "Emergency Management Guides," denoted by procedures numbered 200<<299, consists of management guidelines. These procedures provide guidance on performing the key emergency organization positions.

4. Section 3, "Emergency Action Procedures," denoted by procedures numbered 300-399, contains the specific procedures required to monitor, control and mitigate the consequences of classified emergencies. This section provides step-by-step instructions to direct specific personnel activities during an emergency.

5 ~ Section 4, "Supplemental Procedures," denoted by procedures numbered 400-499, includes the supplemental procedures required to assure the appropriate emergency personnel and equipment are prepared for the onset of emergency conditions.

5.2 INDEX TABS The controlled copies of this manual are indexed by section with white tabs.

PEP-001 Rev. 0 Page 7 of 9

APR006 5.0 GENERAL 5.3 MISCELLANEOUS For informational blanks and checkoffs, the use of "N.A." is permitted rather than spelling out none available or none applicable.

6..0 INITIATING CONDITIONS None Applicable 7.0 PRECAUTIONS LIMITATIONS None Applicable 8.0 SPECIAL TOOLS AND E UIPMENT None Applicable 9.0 PROCEDURE STEPS None Applicable 10.0 DIAGRAMS AND AT1'ACHtfENTS

1. Acronyms PEP-001 Rev. 0 Page 8 of 9

APR006 ATTACHMENT 1 ACRONYMS

~Acrcc AP Administrative Procedure ARD Automatic ring'down (Phone to County and State)

CP Chemistry Procedure DP Dosimetry Procedure EALs Emergency Action Levels EOP Emergency Operating Procedure EOP-EPP Emergency Operating Procedure - End Path Procedure EOP-PATH Emergency Operating Procedure - Flow Path Procedure ERC Environmental and Radiation Contxol Procedure EPZ Emergency Planning Zone ERFIS Emergency Response Facility Information System FPP Fire Protection Procedure FSAR Final Safety Analysis Report HPP Health Physics Procedure NRC Nuclear Regulatory Commission PEP Plant Emergency Procedure PLP Plant Program Procedure RCP Radio Chemistry Procedure SER Safety Evaluation Report SERT State Emergency Response 'Team SHE&EC Sheazon Harris Energy & Environmental Center SHNPP Shearon Harris Nuclear Power Plant SIC Survey Instrument Calibration Procedure SP Security Procedure Note: If definitions of above terms are needed, see SHNPP Emergency Plan, Annex C. Glossary of Terms.

{Final Page)

PEP-001 Rev. 0 Page 9 of 9

APR016 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-101 TITLE: INITIAL EMERGENCY ACTIONS REVISION 0 APPROVED:

Signature Date TITLE:

PEP-101 Rev. 0 Page 1 of 15

APR016 TABLE OF CONTENTS (INITIAL EMERGENCY ACTIONS)

~Pa e Table of Contents

'.0 2

List of Effective Pages 3 PURPOSE

2.0 REFERENCES

4 2.1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4 2.3 Other References 3.0 RESPONSIBILITIES 3.1 Authority 4' 3.2 Relief of Position 3.3 Designated Alternates 5 3.4 Duties 5 4.0 DEFINITIONS 5 5.0 GENERAL 5 6.0 INITIATING CONDITIONS 5 7.0 PRECAUTIONS AND LIMITATIONS 6 8.0 SPECIAL TOOLS AND LIMITATIONS 6 9.0 PROCEDURE STEPS. 6 10.0 DIAGRAMS AND ATI'ACHMENTS 8

'1 Emergency Action Level Network 9 2 Emergency Action Level Flowpath 10 3 List of Plant Procedures that Direct Emergency Action Level Network Entry 11 4 Fission Product Barrier Status Indications 13 PEP-101 Rev. 0 Page 2 of 15

APR016 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 through 15 0 PEP-101 Rev. 0 Page 3 of 15

APR016 1.0 PURPOSE The purpose of this procedure is to implement Section 4.1 of the SHNPP Emergency Plan, "Emergency Classification."

This procedure is to be used by the Shift Foreman or his alternate, in the Control Room upon recognition of an off-normal condition (as determined by instrument readings, direct observation, or reported events) to assist in determining whether an event should be cate-gorized as an emergency.

Once implemented, this procedure shall remain in effect until either:

1. An emergency is declared in accordance with an Emergency Action Level.

2. The off-normal condition is resolved.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 4.1, "Emergency Classification" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-102, "Site Emergency Coordinator - Control Room"

2. PEP-103, "Site Emergency Coordinator - Technical Support Center"

3. PEP-301, "Notification and Communications"

4. PEP-403, "Performance of Training 2.3 OTHER REFERENCES

1. AP-605, "Licensee Event Reports" 3.0 RESPONSIBILITIES 3.1 AUTHORITY The Shift Foreman on duty (or his designated alternate) has immedi>>

ate and unilateral authority to initiate and conduct this procedure.

He may delegate specific steps as necessary, but shall not delegate the final classification decision.

3.2 RELIEF OF POSITION The Shift Foreman may be relieved by a designated alternate trained (in accordance with procedure PEP-403) to conduct this procedure.

PEP-101 Rev. 0 Page 4 of 15

APR016 3.0 RESPONSIBILITIES

3. 3 DESIGNATED ALTERNATES In order of succession, the designated alternates for the Shift Foreman are as follows:

1. Control Room Senior Control Operator

2. Roving Senior Control Operator 3.4 DUTIES Until an emergency is declared, the Shift Foreman has the following responsibilities relating to the Emergency Plan:

1. Direct the activities of the Control Room staff.

2. Recognize an off-aormal condition as indicated by instru-ment readings or observation.

3. Implement any Emergency Operating Proceduzes.

4. Determine whether personnel injuries have occurred.

4.0 DEFINITIONS Fission Product Barrier- The fuel cladding, reactor coolant system boundary, or the containment boundary.

5. 0 GENERAL None Applicable 6.0 INITIATING CONDITIONS Entry into the Emergency Action Level network has been directed by any of the Emergency Operating Procedures, Fire Protection Procedures, Abnormal Operating Procedures, or Security Proce-dures listed in Attachment 3.

or

2. A Critical Safety Function Status Tree on the Safety Parameter Display System has produced a zed or orange output.

or Conditions exist which, in the judgement of the Shift Foreman, could be classified as an emergency.

PEP-101 Rev. 0 Page 5 of 15

APR016 ss 4 e 7..0 PRECAUTIONS AND LIMITATIONS Implementation of this procedure does not constitute an emer-gency. This piocedure serves as a guideline to assist in comparison of plant conditions with Emergency Action Levels to evaluate whether an Emergency should be declared.

2 The highest emergency class for which an emergency action level

~

is currently met should be declared. If an action level for a higher classification was exceeded but currently has abated or been resolved t,he higher clsssificetion should be ~re ected to the state, county, and Nuclear Regulatory Commission in accor-dance with PEP-301, but should not be declared.

3. Priority should be placed on saving lives and/or preventing excessive exposure to personnel over saving equipment or preventing the spread of contamination.

8.0 SPECIAL TOOLS AND E UIPMENT None Applicable 9.0 PROCEDURE STEPS 9.1; Enter the Emergency Action Level Network,'ttachment 1, at the appropriate point:

1. If you were directed to enter the network by another plant procedure, enter at the point specified by that procedure.

2. If you are entering the network because a Critical Safety Function Status Tree on the Safety Parameter Display System has produced a red or orange output, enter at point W.

3. In all other cases, enter at point X.

9.2. Proceed through the. Emergency Action Level Network (Attachment

1) until the network directs you to either declare or not declare an emergency.

If the network directs you to "UPDATE CSF STATUS BOARD,"

enter the output color of each Critical Safety Function Status Tree currently indicated on the Safety Parameter Display System in the data table provided on the network immediately below the instruction. Use the data in this table to answer subsequent, questions in the network logic.

PEP-101 Rev. 0 Pag'e 6 of 15

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APR016 9.0 PROCEDURE STEPS (Cont'd)

2. When the network directs you to "UPDATE FPB STATUS BOARD,"

enter the status of each fission product barrier in the data table provided on the network immediately below the instruction. If you entered the network at points T, U, or V, use the stated condition(s) for the entry point(s).

If you entered at point W, use the conditions from the immediately preceding logic.

3. When the network asks the question "ANY OTHER PLANT PARAMETER THAT INDICATES BREACH OF THE FPB", refer to Attachment, 4, "Fission Product Barrier Status Indications" for general guidance on instrumentation that may be useful in answering this question.

If the answer to the network question "EAL FLOWPATH REVIEWED" is NO, .enter the logic of Attachment 2, "Emergency Action Level Flowpath" at point Z. Proceed through the flowpath logic, re-enter the network (Attachment 1) at point Y,then enter the category (such as fire, loss of power, etc.), if any, that resulted in the highest classification in the appropriate blank in the table provided on the network immediately below the "EAL FLOWPATH REVIEWED" question.

5. Use the data entered in the fission product barrier and flowpath tables to answer the subsequent network ques-tions.

6. If the network directs you to "EVALUATE AGAINST UNUSUAL EVENT MATRIX," proceed through the "Unusual Event Matrix" at the bottom of Attachment 1, then continue with the network.

7. If the network directs you to "DECLARE" any class of emergency, implement PEP-102, "Site Emergency Coordina-tor - Control Room," or PEP-103, "Site Emergency Coordina-tor - Technical Support Center," whichever is appropriate, and enter the time below that point on the Attachment.

8. If the network result, is "NO EMERGENCY DECLARED," consult AP-605, "Licensee Event Reports," to determine whether the condition constitutes a reportable event other than an emergency.

9.3 If conditions dictate a continued evaluation or re"evaluation of Emergency Action Levels, re-enter the network at point W and repeat Section 9.2.

PEP-101 Rev. 0 Page 7 of 15

APR016 10.0 DIAGRAMS AND ATTACHMENTS 1 Emergency Action Level Network 2 Emergency Action Level Flowpath 3 List of Plant Procedures that Direct Emergency Action Level Network Entry Fission Product Barrier Status Indications PEP-101 Rev. 0 Page 8 of 15

APR016 ATTACHMENT 3 LEST OF PLANT PROCEDURES THAT DIRECT EMERGENCY ACTION LEVEL NETWORK ENTRY Procedure Number Ti.tie AOP-001 Malfunction of Reactor Control System AOP-002 Emergency Boration AOP-003 Malfunction of Rx MU Cont AOP-004 Control Room Inaccessibility AOP-005 Radiacion Monitoring Syscem AOP-006 Turbine Vibration AOP-007 Turbine Trip Vithout Reactor Trip Below P-7 AOP-008 Accidental Release of Liquid Waste AOP-009 Accidental Release of Gaseous Vaste AOP"010 Inadequate Feedwater Flow AOP-011 Loss of Circulating Pump AOP-012 Partial Loss of Condenser Vacuum AOP-013 Fuel Handling Accident AOP-014 Loss of Component Cooling Water AOP-015 Secondary Load Re)ection AOP-016 Excessive Primary Plant Leakage AOP-017 Loss of Instrument Air AOP-018 Reactor Coolant Pump Abnormal Condition AOP-019 Malfunction of RCS Pressure Control AOP-020 Loss of Residual Heat Removal (Shutdown Cooling)

AOP-021 Seismic Disturbances AOP-022 Loss of Service Water AOP"023 Loss of Containment Integrity AOP-024 Loss of Instrument Bus AOP-025 Loss of Emergency AC Buss (6.9KV) or One

}, Emergency DC (125VDC) Buss

}~

} AOP-026 Loss of Essential Chilled Water System Response to Acts Against Plant Equipment

~

AOP-027 EOP-EPP-001 Loss of All AC Power to 1A-SA and 1B-SB Busses EOP-EPP"002 Loss of All AC Power Recovery Vithout SE Required EOP-EPP-003 Loss of All AC Power Recovery Vith SE Required EOP"EPP-004 Reactor Trip Response EOP-EPP-005 Natural Circulation Cooldown EOP-EPP-006 Natural Circulation Cooldown Vith Steam Void. in Vessel - Vithout RVLES EOP-EPP-007 ,Natural Circulation Cooldown With Steam Void in Vessel'-Vichout RVLES EOP-EPP"008 SI Termination EOP-EPP-009 Post-LOCA Cooldown and Depressurization EOP-EPP-010 Transfer to Cold Leg Recirculation EOP-EPP"011 Transfer to Hot Leg Recirculation EOP-EPP-012 Loss of Emergency Coolant Recirculation EOP-EPP-013 LOCA Outside Containment PEP-101 Rev. 0 Page 11 of 15

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APR016 ATTACHMENT 3 (Cont'd)

LIST OF PLANT PROCEDURES THAT DIRECT EMERGENCY ACTION LEVEL NETWORK ENTRY Procedure Number Title C

V EOP-EPP-014 Faulted Steam Generator Isolation EOP-EPP-015 Uncontrolled Depressurization of All Steam Generators EOP-EPP-016 SGTR Isolation EOP-EPP-017 Post-SGTR Cooldown Using Backfill EOP"EPP-018 Post-SGTR Cooldown Using Blowdown EOP-EPP-019 Post-SGTR Cooldown Using Steam Dump

'EOP-EPP-020 SGTR With Loss of Coolant Accident:

Subcooled Recovery EOP-EPP"021 SGTR With Loss of Coolant Accident:

Saturated Recovery EOP-EPP-022 SGTR Without Pressurizer Pressure Control EOP-FRP-Cl Response to Inadequate Core Cooling EOP-FRP-C2 Response to Degraded Core Cooling EOP-FRP-C3 Response to Saturated Core Dooling EOP -FRP "Hl Response to Loss of Secondary Heat Sink EOP-FRP "H2 Response to Steam Generator Overpressure EOP-FRP-H3 Response to Steam Generator High Level EOP"FRP-H4 Response to Loss of Normal Steam Release Capability EOP-FRP "H5 Response to Steam Generator Low Level EOP-FRP"Il Response to High Pressurizer Level EOP-FRP-I2 Response to Low Pressurizer Level

~

'I EOP-FRP"I3 Response to Voids in Reactor Vessel EOP-FRP-Jl Response to High Containment Press

~ ~ EOP-FRP-J2 Response to Containment Flooding EOP-FRP-J3 Response to High Containment Radiation Level EOP-FRP"Pl Response to Imminent Pressurized Thermal Shock Conditions EOP-FRP-P2 Response to Anticipated Pressurized Thermal Shock Conditions EOP-FRP-Sl Response to Nuclear Po~er Generation/ATWS EOP-FRP-S2 Response to Loss of Core Shutdown EOP-PATH-1 PATE-1 EOP-PATH"2 PATH"2 FPP-002 Fire Emergency SP-017. Reporting of Physical Security Events PEP-101 Rev. 0 Page 12 of 15

APR016 ATTACHMENT 4 FISSION PRODUCT BARRIER STATUS INDICATIONS Barrier Status Indication All Intact All area and process radiation monitors indicate within their normal Operating Range Fuel Breached Gross Failed Fuel Detection System indicates '(later) CPM, which corresponds to 55 failed fuel, or is increasing (later) CPM/hour,'which corresponds to ZX failed fuel/hour Particulate, Iodine, and/or Noble Gas airborne radiation monitors for any area where thexe are normally small amounts of reactox coolant leakage, or in the Fuel Handling Building, indicate an increase greater than (later) times their normal reading Area radiation monitors in the vicinity of any piping or equipment through which reactor coolant is flowing indicate an increase greater than (later) times their normal reading RVLIS indicates that reactor vessel water level is below the top of active irradiated fuel, or Spent Fuel Pool level dxops below the top of irradiated fuel.

Reactox coolant sample indicates '100yCi/ml equivalent I-131 Reactor Coolant System Charging flow is more than 50 gpm greater Breached than letdown flow Decreasing pressurizer level with maximum charging flow Decreasing reactor coolant system pressure with maximum charging flow and all pressurizer heaters energized Steam Generator pressure corresponds to Reactor Coolant System pressure or Reactor Coolant System Saturation pressure, whichever is greater Containment sump level is increasing PEP-101 Rev. 0 Page 13 of 15

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APR016 ATI'ACHMEiK 4 (Cont'd)

FISSION PRODUCT BARRIER STATUS INDICATIONS Barrier Status Indication Reactor Coolant System Containment air or normal range area, Breached (Cont'd) and/or Condenser vacuum pump exhaust radiation monitors indicate an increase greater then (later) times their normal reading Steam Generator level is increasing with feed flow isolated Containment Breached Containment pressure 245 psig or Hydrogen concentration >4%%d Containment isolation failure Discovery of failure to conform with Technical Specification requirements for containment integrity Indicated steam and/or feedwater flow 215 seconds after a containment isolation signal One or more Main Steam Safety valves, Isolation valves, power-operated relief valve, or dump valves indicate failed open Fuel and Reactor Coolant Containment high-range (post-accident) area System Breached radiation monitor indicates >(later) R/hour Main Steam line radiation monitor(s) indicate greater than (later) pCi/cc A Steam Generaor sample indicates activity

>100pCi/ml A combination of the indications for breach of the individual barriers as listed above Reactor Coolant System Radiation levels throughout the plant Containment Breached and/or plant site are abnormally high but do not exceed (latez) Rem/hour A combination of the indications for breach of the individual b'arriers as listed above PEP-101 Rev. 0 Page 14 of 15

APR016 ATZACHMENT 0 (Cont'd)

FISSION PRODUCT BARRIER STATUS INDICATIONS Barrier Status Indication Containment and Fuel A combination of the indications for breach Breached of the individual barriers as listed above All three breached Plant Vent Stack 1 radiation monitor indicates activity '(later) uCi/cc with maximum ventilation flow A combination of the indications for breach of the individual barriers as listed above Environmetal Monitoring indicates whole body dose rates of 1 Rem/hour or a child thyroid dose committment rate of 5 Rem/hour at the Exclusion Area boundary PEP-101 Rev. 0 Page 15 of 15

CAROLINA POWER 5 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: Plant Emer gency Procedure (PEP)

NUMBER: PEP"102 TITLE: Site Emergency Coordinator

- Control Room REVISION 0 APPROVED:

Signature Date PEP-102 Rev. 0 page 1 of 21

TABLE OF CONTENTS Page Table of Contents...........................................2 List of Effective Pages.............'.......'; ..; ..'...'.....'...'3 1.0 PURPOSE ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4

2.0 REFERENCES

...........................,.................4 2.1 Emergency Plan References..........'...............4 2;2 Referenced Plant Emergency Procedures.............4 2.3 Corpor ate Emergency Plan and Implementation Procedur es References.............................4 2.4 Other References..................;,..............5

'3. 0 RESPONSIBILITIES .......;."...:....'...................5 3..1 Authority.........'..'..............................5 3.2 Relief of Position ......;...;..................'..5 3.3 Duties Prior to Activation of the Technical Suppor t Center....................................5 3.4 Duties Relinquished Upon Activation of the Emer gency Oper ating Facility .....................7 3.5 Delegation of Authority ............;..............7 4.0 DEFINITIONS.o.,o....o..o.o..oo..o.....o..o...o.o.......7 5.0 G ENERAL ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ s ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 6.0 INITIATING CONDITIONS ... ;. ...;........;....;;.;..;..'8

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7.0 PRECAUTIONS AND LIMITATIONS ..;........................8 8.0 SPECXAL TOOLS AND EQUIPMENT ......;...................:8 9.0 PROCEDURE STEPS . ~ .. .. .. ... .. .. .. . ........8

~ . ~ .

~ ~ ~ ~ ~ ~ ~ ~ ~

9.1 G eneral 8 9.2 Immediate Response Organization Assistance ...'.........9 9.3 Declar ation of Emergency, Change of Classification, or Termination .......................................10 9' Initial Actions ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 12 9.5 Direct Activation oi Emergency Response Facilities ...13 9.6 Initial Warnings arid Notifications On-Site and Off-Site .............................................14 9.7 Habitability of, Assembly Area Shelters and the Oper ational Suppor t Center ...........................16

.9. 8 Dose Projection'..................................'...17 9.9 Follow-up Notifications ..............................18

9. 10 Temporar y Procedures and Departure from License Conditions or Technical Specifications ...............19 9.11 Position Changeover for Site Emergency Coordinator ..........................................19

10. 0 DIAGRAMS/ATTACHMENTS ................................;20

1. Site Emergency Coordinator Tur nover Checklist 21 PEP-102 Rev. 0 Page 2 of 21

LEST OF EFFECTIVE PAGES Page Revision 1 through 21 0 PEP-102 Rev. 0 Page 3 of 21

1.0 PURPOSE The. purpose of this procedure is to implement Sections 2.3 "Command and Control" and 2.4.2 "Site Emergency Coordinator" of the SHNPP Emergency Plan while the emergency is managed from the Control Room. This procedure describes the actions of the Site Emergency Coordinator from the time an emergency is declared to the time when the emergency is terminated or when the Site Emergency Coordinator function is transferr ed to the Technical Support Center.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 2.3, "Command and Control" 2; Section 2;4.2, "Site Emer gency Coordinator<<

2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-101, <<initial Emergency Actions" 2; PEP-103, "Site Emergency Coordinator - Technical Support Center<<

3. PEP-104, "Protective Action Recommendations"

4. PEP-217, "Emergency Communicator<<

5; PEP-301, "Notification and Communications" 6; PEP-302, "Communication Activities" 7; PEP-303, <<Use of Communications Equipment" 8; PEP-321, "Notification of Emergency Personnel" 9; PEP-322, "Mobilization of Outside Organizations"

10. PEP-341, "Manual Dose Projection<<

11; PEP-342, "Automation of Dose Projection Pr ocedure-ERFIS<<

12. PEP-343, "Automation of Dose Projection Procedure - IBM PC<<

13. PEP-351, "Emergency Plant Environmental Monitoring" 1 4; PEP-381, "Evacuation" 15; PEP-382, "Personnel Accountability" 16: PEP-391, "First. Aid and Medical Car e<<

17." PEP-401, <<Record Keeping and Documentation" 18; PEP-403, "Performance of Training,"

19; PEP-405, "Preparation of Activity Logs" 2.3 CORPORATE EMERGENCY PLAN AND IMPLEMENTATION PROCEDURES REFERENCES CEPIP-1 - Corporate Emergency Plan Notification

2. CEPlP-3 - Emer gency Response Manager 3~ CEPIP-8 - Corpor ate Emer gency Operations Center Activation and Operations PEP-102 Rev. 0 Page 4 of 21

2.0 REFERENCES

2.4 OTHER REFERENCES 1 ~ AP-002, "Plant Conduct of Operations" 2~ AP-007, "Tempor ar y Procedure, Revision, Review and Approval" 3 ~ OMH-001, "Operations Conduct of Operations" 3.0 RESPONSIBILITIES 3.1 AUTHORITY The Site Emergency Coordinator is delegated the authority to act on behalf of the Company to manage and direct all emergency operations involving SHNPP.

3.2 RELIEF OF POSITION

1. The Site Emer gency Coordinator may be relieved by a designated alternate trained (in accordance with procedure (PEP-403) to perform the duties of this position.

2~ The primary person assigned to the position of Site Emergency Coor dinator Control Room is the Shift Foreman.

If the Shift Foreman is unavailable, the designated alternates in order of succession, until transfer of the Site Emer gency Coordinator position to the Technical Suppor t Center, ar e:

3.3 DUTIES PRIOR TO ACTIVATION OF THE TECHNICAL SUPPORT CENTER Un til tr ansfer of the Site Emer gency Coordinator position to the Technical Support Center, the Site Emergency Coordinator - Contro l Room performs the following duties:

1. Requests assistance fr om Immediate Emergency Response Organizations as needed.

2. Classifies the emergency and announces it in the Control Room.

3. Designates Leader personnel to fill the positions of Operations and the Emergency Communicator.

Coordinates and directs the activities of emergency response personnel in the Control Room, Operational Support Center, and elsewhere on the plant site.

PEP-102 Rev. 0 Page 5 of 21

3.0 RESPONSIBILITIES 3.3 DUTIES - PRIOR TO ACTIVATION OF THE TECHNICAL SUPPORT CENTER (CODD'N)

5. Orders the alerting of on-site personnel and the assembly and evacuation of nonessential personnel from local areas, the Protected Area, or the site when conditions warrant. He also orders the return of per sonnel to their work places after assembly for accountability pur poses when evacuation is unnecessary or the emergency condition is over.

6. Orders the activation of the Technical Support Center, the Operational Support Center, the Emergency Operations Facility, and the Plant Media Center when required.

7~ Ensures required notifications are made in a timely fashion.

8. Recommends to off-site government authorities protective actions which should be taken by the public until relieved of this responsibility by the Site Emergency Coordinator - Technical Support Center or the Emergency Response Manager (see Section 3.5).

9. In the absence of the Plant General Manager and the Manager-Envir onmental and Radiation Control, approves planned personnel exposures in excess of 3 rem or entry into radiation fields gr eater than 100 rem/hr.

10. Reviews and approves deviations from Technical Specifications or license conditions.

When contacted by the State after an initial notification of an emer gency, briefs the State on plant conditions and actions being taken.

12. Until the Emergency Operations Facility is activated, provides updates to the State on the emergency conditions and recommendations for protective actions at appr oximately 60 minute intervals or if necessary, more frequently.

13. Declares the emergency terminated when the situation is under control (see Section 3.5).

PEP-102 Rev. 0 Page 6 of 21

3.0 RESPONSIBILITIES 3.3 DUTXES " PRIOR TO ACTIVATION OF THE TECHNICAL SUPPORT CENTER (Cont~d)

NOTE: After the Technical Support Center is activated, the function of the Site Emergency Coordinator transfers from the Control Room in the person of the Site Emer gency Coor dinator-Control Room (Shift For eman) to the Technical Support Center in the per son of the Site Emergency Coordinator-Technical Support Center (Plant Manager). The Site Emer gency Coordinator-Control Room (Shift For eman) may then assume the position of Operations Leader in charge of the Control Room. For duties of the Site Emer gency Coordinator after .the Technical Support Center is activated see PEP-103.

3.4 DUTIES RELINQUISHED UPON ACTIVATION OF THE EMERGENCY OPERATING FACXLXTY I on U pon activation of the Emergency Operations Facility (EOF), the Emergency Response Manager will assume responsibility for off-site notifications, and inter face with the Corporate Emergency Operation Center and the State and County Governments for environmental monitoring and for off-site dose pr ojection.

3.5 DELEGATION OF AUTHORXTY The Site Emergency Coordinator shall not delegate the r esponsibilities of:

o Classifying the emergency, or o Recommending off-site pr otective actions to authorities responsible for off-site emergency measures, o Declaring the emergency terminated.

Other responsibilities may be delegated as necessary to expedite response to the emergency.

0.0 DEFINITIONS None Applicable 5.0 GENERA None Applicable PEP-102 Rev. 0 Page 7 of 21

6.0 INITIATING CONDITIONS Implementation of PEP-101 is a prerequisite to implementation of this'rocedure. Each time an emer gency condition is declared,'reclassified (upgraded or downgraded), or terminated, this procedure is implemented. All, or only selected portions of this procedur e, may be implemented, as necessary.

2. This procedure is terminated under the following conditions:

o The functions of the Site Emer gency Coordinator-Control Room are properly turned over to the primary Site Emergency Coordinator -Technical Support Center who implements PEP-103, "Site Emer gency Coordinator-Technical Support Center."

o The Site Emer gency Coordinator-Control Room declares that the Emergency is terminated.

7.0 PRECAUTIONS AND LIMITATIONS None Applicable 8.0 SPECIAL TOOLS AND EQUIPMENT

l. Emergency Log 9.0 PROCEDURE STEPS 9.1 GENERAL

1. Initiate an Emergency Log. Record in this log significant decisions or actions. As a minimum, record actions in, this procedure denoted by a star "~" before the step number .

2. Maintain this log per PEP-405 until you declare the emergency terminated or are relieved by the Site Emergency Coordinator Technical Support Center.

3. After the emergency, records are to be delivered to the Senior Specialist-Emergency Prepar edness.

PEP-'l02 Rev. 0 Page 8 of 21

9.0 PROCEDURE STEPS 9.2 IHMEDIATE RESPONSE ORGANIZATION ASSlSTANCE If assistance from an immediate response organization (Fire, Ambulance, Police, etc.) is needed, proceed as follows, otherwise go to Section 9.3, After a request for assistance fr om an immediate response or ganization has been received in the Control Room:

Fill out, Attachment 1 to procedure PEP-301 (Immediate Response Organization Notification Form), call the organization (or have the Emergency Communicator call) and request the specific assistance needed as per procedur e PEP-301.

Z~ If off-site assistance is r equested, verify security is notified and instructed to:

Prepare the appr opr iate number of security badges.

Prepare the appr opr iate number of dosimetry devices (if needed for the final destination).

Have sufficient security personnel ready as'scorts at the responding unit's initial arrival point.

Notify you and the requestor when the responding unit has arrived at the initial ar rival point and at their destination.

%3 ~ If off-site assistance is r equested, verify that the requestor (or person who will use their assistance) is notified of the following:

Type of assistance responding (Fire, Ambulance, Sheriff if security is requestor)..

0 Number of vehicles.and personnel expected.

0 Estimated. time of arrival.

0 Where they were instructed to r espond initially.

0 Wher e they were instructed to go on site.

0 Security will provide an escort to the final destinati.on.

4 ~ If the off-site assistance involves calling an ambulance refer to PEP-391 for details on medical care, personnel decontamination and transpor tation of contaminated injur ies.

%5 If the off-si e assistance r equires taking an injur ed person to the hospital, confirm with the ambulance personnel, First Aid Team, and/or Per sonnel Protection and Decontamination Team personnel whether the patient is contaminated, to which hospital he will be taken, and how 'I PEP"10Z Rev. 0 Page 9 of Zl

9.0 PROCEDURE STEPS 9.2 IMMEDIATE RESPONSE ORGANIZATION ASSISTANCE (Cont'd) soon he will be transpor ted. Notify the hospital of the information as per procedure PEP-301.

9.3 DECLARATION OF EMERGENCY, CHANGE OF CLASSIFICATION, OR TERMINATION

<<1. When an emergency classification is determined in accordance with PEP-101, declare aloud in the Control Room that:

An emergency exists-,

or The emergency classification has changed, or The 'emergency has.terminated, as follows:

NOTE: Use only those parts of the following message which coincide with the current conditions.

>++ EXAMPLE MESSAGE +++

o ATTENTION IN THE CONTROL ROOM! (Repeat if necessary)

AS SITE EMERGENCY COORDINATOR I AM DECLARING:

AN EMERGENCY CONDITION EXISTS AS OF:

(Give time) 'AND THE CLASSIFICATION IS:

(Give classification: Unusual Event, Alert, Site Emergency or General Emergency).

or THE PREVIOUS EMERGENCY CLASSIFICATION HAS CHANGED AS OF: (Give time) AND THE CLASSIFICATION IS NON: (Give present classifi.cation).

or THE EMERGENCY IS TERMINATED AS OF: (Give time).

THE CLASSIFICATION (or RECLASSIFICATION) IS BASED UPON EXCEEDING (or FALLING BELOW) THE EMERGENCY ACTION LEVEL OF:

0 (State Emergency Action Level)

PEP-102 Rev. 0 Page 10 of 21

9.0 PROCEDURE STEPS 9.3 DECLARATION OF EMERGENCY, CHANGE OF CLASSIFICATION, OR TERMINATION (Cont'd)

(For initial declaration only, continue announcement:)

I AM ASSUMING THE POSITION OF SITE EMERGENCY COORDINATOR.

I AM DESIGNATING: (Name) TO BE THE OPERATIONS LEADER AND TO BE IN CHARGE OF THE CONTROL ROOM. YOU ARE TO FOLLOW THE EMERGENCY OPERATIONS PROCEDURES AND TAKE OTHER ACTIONS AS NECESSARY TO BRING THE PLANT INTO A SAFE CONDITION UNTIL PROPERLY RELIEVED OF THAT POSITION BY ME OR A QUALIFIED REPLACEMENT.

I AM DESIGNATING: (Name) TO BE THE EMERGENCY COMMUNICATOR.

(For all cases, if appropriate:)

o AT PRESENT I ANTICIPATE ACTIVATING (DEACTIVATING)

THE FOLLOWING EMERGENCY FACILITIES:

(Specify which ones):

None Technical Support Center Operational Support Center Emergency Operations Facility (For terminations only, of the accident conditions:)

EMERGENCY COMMUNICATOR, NOTIFY ON-SITE PERSONNEL AS PER PEP-321 AND ALL OFF-SITE AGENCIES AND PERSONNEL THAT HAVE BEEN CONTACTED AS PER PEP-301 THAT THE EMERGENCY IS NOW TERMINATED.

AFTER FINISHING'YOUR CURRENT TASKS ALL PERSONNEL ARE RELIEVED FROM YOUR EMERGENCY POSITIONS. CLOSE OUT ANY EMERGENCY L'OGS, TURN THEM IN TO ME; AND RESUME 'YOUR NORMAL POSITIONS.

(To end all announcements:)

o PLEASE) CARRY ON!

2~ If the declared emergency is a result of emergency action- level(s) indicating a high classification (i.e.,

Site Emergency) that after a brief period is downgraded to a lower classification (i.e., Alert), the off-site notification must indicate the 'current classification, and it must also indicate the period(s) of time that the higher classification occurred and the mitigating conditions that caused the emer gency classification to be downgraded.

PEP-102 Rev. 0 Page 11 of 21

9.0 PROCEDURE STEPS 9.3 DECLARATION OF EMERGENCY, CHANGE OF CLASSIFICATION, OR TERMINATION {Cont'd)

For example, the emergency action levels in PEP-101 will show a site emer gency due to a relief valve failure to reseat concurrent with significant primary to secondary system leakage. Before the emer gency operating procedur es have been completed, and before the off-site notification begins, the valve seats and an Aler t condition exists. State that the emergency classification is an Alert, that the initiating condition was a failure of a valve to reseat, and that a Site Emergency existed from (time) to (time).

NOTE: If the downgrading of the emergency class occur s dur ing an initial notification immediately change the notification to state the new emergency class.

9.4 INITIAL ACTIONS

l. Instruct the Oper ations Leader to follow appr opriate operations procedures (or emergency operations procedures) applicable to the specific situation.

2. Designate an available reactor operator as the Dose Pro)ection Team Leader, if needed.

3. Instruct the Dose Pr objection Team Leader to immediately initiate PEP-342 or PEP-343 (or a manual calculation, if necessar y, as in PEP-341) to obtain an estimate of the off-site dose, both as an input to assist in determining what protective action recommendations will be made in the initial off-site warning message, and for comparison with Emer gency Action Levels.

Determine if an evacuation of personnel at the s'ite is necessary. (The basis whether to evacuate and the types of evacuation are discussed in PEP-381.) Select one of the following:

Assembly and Shelter Protected Area Evacuation Plant Site Evacuation {Protected Area, Other Operations Areas, and any of the construction Areas)

PEP-102 Rev. 0 Page 12 of 21

9.0 PROCEDURE STEPS 9.5 DIRECT ACTIVATION OF EMERGENCY RESPONSE FACILITIES Decide what emergency facilities, if any, should be activated for the emergency condition. Guidance for activation is as follows:

NOTE: "Activation" means fully oper ational and functional. To direct activation of a facility does not of the facility until the Manager of the constitute'ctivation facility announces that the facility is activated and functioning.

o If an UNUSUAL EVENT is declared, activation of the following emer gency facilitaies are not required but may be considered as an optional item:

-Technical Support Center

-Operational Support Center

-Emer gency Operating Facility o If an ALERT is declared, activate the, following facilities:

-Technical Support Center

-Operational Support Center The Emergency Operating Facility may optionally be activated if desired.

o If a SITE OR GENERAL EMERGENCY is declared, activate all of the following 'facilities:

-Technical Support Center

-Operational Support Center

-Emergency Operating Facility NOTE: Activation of the Emer gency Operations Facility is per formed by contacting the Emergency Response Manager (Vice President Harris Nuclear Project or nate) and requesting activation of the facility as his'lter specified in the Corporate Emergency Plan and Corporate Emergency Plan Implementation Procedure CEPIP-1.

Activation of other emergency response facilities, such as the Plant Media Center or Corporate Fmergency Operating Cent r is usually performed by corpor ate personnel as specified in CEPIP-1 and CEPIP-8. l'f it is desir ed to activate any of these'facil'ities, contact the Emergency Response Manager. General Information on or ganlzatlon, notification, emergency measures, and facilities can be found in Section 4 through 7 of the Cor porate Emergency Plan.

PEP-102 Rev. 0 Page 13 of 21

9.0 PROCEDURE STEPS 9.5 DIRECT ACTIVATION OF EMERGENCY RESPONSE FACILITIES {Cont'd)

2. Inform the Contr ol Room personnel and the Emergency Communicator of what facilities you have decided to activate.

9.6 INITIAL WARNINGS AND NOTIFICATIONS ON-SITE AND OFF"SITE NOTE: Steps 1 through 7 can be performed concur rently or in the order decided best by the Site Emer gency Coordinator.

Fill out the "Emergency Organization Notification Form,"

Attachment 1 of PEP-321, identifying CP8L personnel needed for the class of emergency declared.

%2 ~ Have the Emer gency Communicator (or another individual you designate) notify on-shift personnel (and others on site needed for the emergency) of their emergency assignments via the plant Public Address system (or other expeditious means) as per PEP-321.

NOTE: Step 2 can be combined with Step 3.

%3 War n, or assign someone to war n on-site personnel via siren, Public Address System, radio, pager, and/or telephone that an emergency has been declared. Specify the following in the announcement:

The classification of the emergency.

That personnel report in to their supervisors in assembly areas.

That supervisors account for their personnel and report the names and possible location of any unaccounted personnel within 20 minutes to the Assembly Area Leaders. Assembly Area Leaders report results to the'Emergency Security Team Leader at extension (specify)

What on-site emergency facilities are being activated (Operational Support Center, Technical Suppor t Center ) .

other necessar y'onfor mation.

%4 ~ Decide what protective actions you will r ecommend to the of f-site agencies. See procedure PEP-104.

NOTE: THE DECISION AS TO WHAT PROTECTIVE ACTION TO RECOMMEND TO OFF-SITE AGENCIES CANNOT SE DELEGATED. The initial notification must be made to the five off-site agencies within 15 minutes after the declan ation of an emer gency.

PEP-102 Rev. 0 Page 14 of 21

9.0 PROCEDURE STEPS 9.6 INITIAf WARNINGS AND NOTIFICATIONS ON-SITE AND OFF-SITE (Cont'd)

<<5. Prepare (or assign an available individual in the Control Room to prepare) the initial notification message (Part I of Attachments 2 and 3) as described in PEP-301.

Review the initial notification messages, make changes if necessary, and appr ove them for release by signing your name, the time, and the date.

)f7 ~ Give the approved initial notification messages to the Emergency Communicator and instruct him to notify the five off-site agencies within 1 5 minutes and the NRC and INPO within one hour after the declaration of an emergency.

NOTE: Refer him to PEP-217, PEP-301, PEP-302, and 'PEP-303.

8. After on shift personnel have reported in (physically or by telephone) notify the Emergency Security Team Leader.

9. If the on-shift personnel must be augmented to properly respond to the emergency, augment them as specified in PEP-321 by filling out Attachment 1 of PEP-321, "Emergency Organization Notification Form."

10. If personnel from Westinghouse, Ebasco, INFO, or other organizations are requir ed, indicate on the "Mobilization of Outside Organizations Form" (Attachment 1'to PEP-322).

+1'I . If personnel augmentation is required, give the completed and approved call-in lists (prepared in steps 9 and/or 10) to the Emergency Communicator (or other available'erson) and instr uct him to call in these .

personnel as quickly as possible and to r eport when everyone has been notified and when they have arrived.

"12. If the Emer gency Scour ity Team Leader has not called within 30 minutes of the declaration, contact him to determine if all personnel ar e accounted for in accordance with PEP-382 and, .if not, what actions are being taken. Also ascertain if the assembled personnel have provided any information on injuries, fires, or damage to equipment.

PEP-102 Rev. 0 Page 15 of 21

9.0 .PROCEDURE STEPS.

9.7 HABITABILITYOF ASSEMBLY AREA SHELTERS AND THE OPERATIONAL SUPPORT CENTER Instruct the Personnel Protection and Decontamination Team Leader to perform a radiological survey )(and/or toxic gas survey depending upon the type of emergency) of the assembly areas which are also being used to shelter personnel.

>2. If the Operational Support Center has been activated, also instr uct the Personnel Protection and Decontamination Team Leader to perform a radiological survey of the Operational Support Center after sur veying the Assembly Area Shelters, and inform you of the results when it is complete.

%3, If the radiological conditions reported in the Assembly Area Shelters or Operational Support Center will result in personnel exposure in excess of 5 mr em/hr or a pro)ected dose in excess of 100 mrem whole body, and/or airborne r adioactivity in excess of 1 MPC, or 40 MPC-hours/week, consider moving the Operational Support Center to a new location (such as the health physics area of the Naste Processing Building).

%4 If radiological conditions in the assembly areas exceed levels in step 3 or if toxic gas levels exceed threshold

~

level values non-essential personnel should be evacuated (as per PEP-381) or if this is not reasonable to do at the time, moved to a better shelter if one exists. If the emergency is classified as an unusual event or alert, and if all or most work areas have not been affected, consider instructing personnel to return to

%5 'fwork areas that have not been affected.

Oper you ar e considering moving the shelters or ational Support Center, instruct the Personnel Protection and Decontamination Team Leader to survey possible new locations (give suggestions) and r eport the results to you. 'I If surveys of alternate Oper ational Support Center locations have been r eported, evaluate the results, decide whether to move all, some, or none of the Operational Suppor t Center personnel and instruct the Personnel Protection and Decontamination Team Leader as to what further actions to take.

PEP-102 Rev. 0 Page 16 of 21

9.0 PROCEDURE STEPS 9.7 HABITABILITYOF ASSEMBLY AREA SHELTERS AND THE OPERATIONAL SUPPORT CENTER (Cont'd)

NOTE: Depending upon the radiological conditions at the current Operational Support Center, the radiological conditions at the proposed Operational Support Center(s), the wind direction and stability class, the distance from the area where personnel will be used, availability of communications equipment and other equipment, adequacy of the facility and overall adequacy of the r esponse fr om alternate locations, you may not want to transfer personnel. An alternative would be to transfer all personnel to an alternate Operational Support Center except those expected to be used shortly; as. people are needed, bring them to the old Operational Support Center to get dressed and obtain equipment.

7~ If an alternate Operational Support Center is activated, announce this decision (and whether the old Operational Support Center is closed) over the Public Address System.

8. Notify scour ity to instr uct incoming per sonnel to report to an alternate Operational Suppor t Center if an alternate is used.

9.8 DOSE PROJECTION If a General Emer gency has been declared, immediately determine a protective action recommendation based upon plant conditions and wind direction (as per PEP-104) and then have dose projections performed as per the steps. If an Unusual Event, Alert or Site

'ollowing Emergency has been declared, ther e should be no off-site effects by definition and therefore no immediate protective actions recommendations are required.

Procede with step 2.

Once the initial dose projection has been performed as indicated in PEP-341, PEP-342, or PEP-343 by the Dose Projection Team Leader, verify that the Radiological Control Director (if available) has checked the results arid agrees with them.

%3 ~ Verify that the Radiological Control 0 ir ector (if available) has sent out the Environmental Monitor ing Team, based upon the initial dose projection calculation, to confirm the initial projection as per PEP-351. Obtain the time the team was dispatched and the time they are expected to report.

PEP-102 Rev. 0 Page 17 of 21

9.0 PROCEDURE STEPS 9.8 DOSE PROJECTION (Cont'd)

NOTE: Not required for Unusual Event and Alert.

Obtain recommendations from the Radiological Control Director (if available or Dose Projection Team Leader) based upon the initial dose projection calculations and protective action guides as to what protective actions, if any, should be recommended to the off-site agencies. Compare with the results from PEP-100.

%5 'nce the Environmental Monitoring Team has reported their readings and the Radiological Control Director (if available or Dose Projection Team Leader) has evaluated the readings, discuss with him whether the results confirm the initial dose projection calculations and recommended protective actions or whether he recommends new protective actions based upon these results.

%6 ~ Based upon the Environmental Monitoring Team results, the recommendations of radiological control personnel, the evaluation by the Operations Leader of plant conditions and the protective action guides, decide what protective actions to recommend to the off-site agencies. See procedur e PEP-104 for details.

NOTE: The Site Emergency Coordinator cannot delegate this

. responsibility. By definition there should be no off-site effects and, therefor e no protective action recommendations requir ed for Unusual Event, Alert or Site Emer gency.

9. 9 FOLLOW"UP NOTIFICATIONS A

Once protective action recommendations have been decided upon, have Part II of the Emer gency Notification forms in PEP-301 completed (Par t I should already be complete) by the Radiological Control Dir ector (or Dose Projection Team Leader).

3f2 Review the follow-up notification messages (Par ts I 8c ~

II), add information or make changes if necessary, and approve them for release by signing your name,'he time,-

and the date.

%3 Give the approved follow-up notification messages to the Emergency Communicator and instruct him to notify the off-site agencies and the Nuclear Regulatory Commission.

PEP"102 Rev. 0 Page 18 of 21

9.0 PROCEDURE STEPS F 10 TEMPORARY PROCEDURES AND DEPARTURE FROM LICENSE CONDITIONS OR TECHNICAL'PECIFICATIONS The Site Emergency Coordinator is required to authorize reasonable action that departs from a license condition or a Technical Specification in an emergency when this action is immediately needed to protect the public health and safety and no action, consistent with license conditions and Technical Specifications, is immediately apparent that can provide adequate or equivalent protection.

All deviations from Technical Specifications or license condition (e.g., Quality Assurance Program, Control Room Staffing, Containment Leakage Rate, Security Plan, Safeguards Contingency Plan, State Local and SHNPP Emergency Plans, or unauthorized disclosur e of Safeguards information) shall be approved by the Site Emergency Coordinator-Control Room in accor dance with procedures AP-002 and OMM-001.

<<2. The Nuclear Regulatory Commission shall be notified via the Emergency Notification System (Red phone) of actions that deviate from license conditions or Technical Specifications. The Nuclear Regulator y Commission will be notified prior to performing the action, if time permits; otherwise, the notification shall be made as soon as possible thereafter.

<<3. All temporary changes to procedures shall be approved by the Site Emergency Coor dinator-Control Room in accordance with procedure AP-007. If prudence dictates immediate action, verbal approval will be given and documentation completed as time permits.

9.11 POSITION CHANGEOVER FOR SITE EMERGENCY COORDINATOR

<<1. When relinquishing the position of Site Emergency Coordinator - Control Room brief your successor on the emer gency and emergency actions status using Attachment 1.

<<2. If you are relieving a Site Fmergency Coor dinator-Control Boom, request and obtain fr om the current position holde. a briefing on the emer gency and emergency actions status.

<<3. Upon assuming the position of Site Fmergency Coor dinator -Control Room, notify all appropriate personnel of your name, the position you ar e assuming, and the name of the person you replace.

PEP-102 Rev. 0 Page 19 of 21

9.0 PROCEDURE STEPS 9.11 POSITION CHANGEOVER FOR SITE EMERGENCY COORDINATOR (Cont'd)

If activation of the Emergency Operations Facility by the Emergency Response Manager should occur prior to activation of the Technical Support Center, transfer the responsibility for off-site related activities to the Emergency Response Manager . This includes a briefing of the Emer gency Response Manager using Attachment 1 and transfer of the Emergency Communicator position to the Emergency Operations Facility.

<<5. Transfer of the position of Site Emer gency Coordinator from the Control Room to the Technical Support Center will occur after the person who is to assume the Site Emergency Coordinator - Technical Support Center position has arrived in the Technical Support Center.

The transfer may occur before the Technical Support Center is fully operational at the discretion of the Site Emergency Coordinator-Technical Support Center .

Upon transfer, PEP-103 will go into effect 'and will terminate. this'rocedure 10.0 DIAGRAMS/ATTACHMENTS

1. Site Emergency Coordinator Tur nover Check list.

PEP-102 Rev. 0 Page 20 of 21

ATTACERKNT 1 Site Emer enc Coordinator Turnover Checklist

1. Review status of major plant safety equipment and systems.

2. Review cause and history of the emergency condition.

a. Initiating events

b. Sequence of follow-up events

c. Other details

3. Review and determine emergency actions initiated.

a. Plant-specific

b. Off<<site

4. Review resources available on site and resources needed.

5. Review off-site notifications made.

a. Corporate

b. State

c. NRC

d. Westinghouse

e. Ebasco Services

f. Other: Duke, VEPCO, SCESG, INFO, ANI, FEMA

6. Determine what other notifications should be made.

7. Determine other resources needed.

8. Identify key personnel o'n duty.

a. Site Emergency Coordinator

b. Pla'nt Operations Director

c. Emergency Repair Director

d. Logistics Support Director

e. Radiological Control Director

f. SERT Representative PEP-102 Rev. 0 Page 21 of 21

CAROLINA POMER 5 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING HAiVUAl VOLUiME 2 PART 5 PROCEDURE TYPE: PLANT Ei4lERGENCY PROCEDURE {PEP)

NUMBER: PEP-103 TITLE: SITE EMERGENCY COORDINATOR TECHNICAL SUPPORT CENTER REVISION 0 APPROVED: g.~e(

Signature Date J. L 'PILLION, PLANT 8EHBAL INHALER PEP-103 Rev. 0 Page 1 of 12

TABLE OF CONTENTS Page Table of Contents...................,......... 2 List of E ffec t i ve Pages....'...,'....; ..;...'.'.

~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 3 1 ~ 0 PURPOSE ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 ~ 4 2.'0 REFERENCES................;.............. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ...4 2.1 Emergency Plan References........... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~

2.2 Referenced Plant Emergency Procedure s ~ ~ ~ ~ i o4 2.3 Other Referenced Plant Procedures. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 3.0 RESPONSIBILITIES......................... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~

3.1 Reporting Responsibilities.......... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 3.2 Assignment and Relief of Position... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5 3 .3 Dutieso ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ o 5 4 ~ 0 DEFINIT10NS ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~ a > ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ r ~ ~ ~ ~ 6 5 0

~ GENERAL ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 6.0 INITIATING CONDITIONS................,... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~ ~ 6 7.0 PRECAUTIONS AND LIMITATIONS.......;...... ~ ~ ~ ~ ~ ~ 6 8.0 SPECIAL TOOLS AND EQUIPMEiVT......;... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 ~ ..6 9.0 PROCEDURE STEPS..............,....,....., ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ > ~ ~ ~ ~ ~ 7 10.0 DIAGRAMS/ATTACHMENTS..................... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ..10

1. Site Emergency Coordinator Turnover Checklist. ..11 PEP-103 Rev. 0 Page 2 of 12

LiST OF EFFECTEVE PAGES Page Revt.sion 1 thru 12 0 PEP-103 Rev. 0 Page 3 of 12

1.0 PURPOSE This pr ocedur e implements Section 2.4.2 of the SHNPP Emergency Plan. It specifies actions to be taken by the Site Fmergency Coordinator - Technical Support Center.

2.0 REFERENCES

2.1 EHERGENCY PLAN REFEREiVCES Section 2.3, "Command and Control"

2. Section 2.4.2, "Site Fmergency Coordinator"

3. Section 4.0, "Emer gency Heasures and Ooerations" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-101, "Initial Emergency Actions"

2. PEP-104, "Protective Action Recommendations"

3. PEP-301, "Notification and Communications" PEP-302, "Communications Activities"

5. PEP-321, "Notification of Emergency Personnel"

6. PEP-322, "Mobilization of Outside Organizations"

7. PEP-323, "Set-up and Operation of Emer gency Facili.ties"

8. PEP-371, "Emergency Response in Radiological Areas"

9. PEP-381 "Evacuation"

10. PEP-405, "Pr eparation of Activity Logs"

11. PEP-500, "Recover y" 2.3 OTHER REFEREiVCED PLANT PROCEDURES

1. AP-002, "Plant Conduct of Operations" 3.0 RESPONSIBILITIES 3.1 REPORTING RESPONSIBILITIES The Site Emergency Coordinator - Technical Suppor " Center r eports to the Emergency Response Hanager after the Emergency Operations Facility is manned.

PEP-103 Rev. 0 Page 4 of 12

3. 0 RESPONSIBILITIES

3. 2 ASSIGNMENT AND RELIEF OF POSITION The Plant General Hanager, Hanager - Start-up, Manager-Operations, or Manager - Maintenance, in tnat order of succession, reports to the Control Room when notified of an Alert, Site Emergency, or General Emergency. After a briefing by tne Site Emergency Coor dinator-Control Room, and when ne has determined that the Technical Suppor t Center is sufficiently manned and activated to assume command responsibilities, he formally assumes the position of Site Emer gency Coordinator-Technical Suppor t Center.

3.3 DUTIES The Site Emergency Coordinator - Technical Support Center is responsible for:

Maintaining a record of his activities.

2~ Coordinating and directing the activities of all personnel on the plant site.

3. Designating an individual to be in char ge of the Control Room.

4. Classifying the emergency.

5. Ensuring that required notifications are made in a timely manner.

6. Ordering evacu'ations from on-site areas and/or on-site sheltering when necessary.

7. Activating the Emergency Operations Facility if the event escalates to a Site or General Emergency.

8. Performing the functions of the Emergency Response Hanager until that position is manned at the Emer gency Oper ations Facility, and informing the Emer gency Response Hanager of actions being planned and taken.

9. Ensuring that provisions are made for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> continuity of the on-site emergency response effort.

10. In the absence of the Plant General Hanag r and the Hanager Environmental and Rad1.ation Control, appr oving planned radiation exposures in excess of 3 Rem or entry into radiation fields greater than 100 R/hr .

PEP-103 Rev. 0 page 5 of 12

3.0 RESPONSIBILITIES 3.3 DUTIES (Cont'd)

11. Author izing distr ibuting of Potassium Iodide to on-site emer gency workers.

12. Ensuring tnat he is relieved only by an individual tr ained to perform the duties of Site Emer gency Coordinator-Technical Support Center.

JJ.O DEFINlTIONS None Applicable 5.0 GENERAL The Site Emergency Coordinator - Technical Support Center exercises overall command and control of on-site activities.

6.0 INITIATING CONDITIONS 6.1 The Shift Foreman has declared an Alert, Site Emergency, or General Emer gency, and has assumed the position of Site Emergency Coor dinator - Control Room.

6.2 The Plant Gener al Hanager has determined that activation of this position is warranted.

7.0 PRECAUTIONS AND LINITATIONS 7.1 The following actions shall not be delegated:

1. Classi,fication of an emer gency.

2. Deciding to notify authorities r esponsible for off-sit actions.

3. Deciding what protective actions to r ecommend to authorities r esponsible for off-site actions.

7.2 Planned radiation exposures in excess of regulatory limits are appropriate only for lifesaving activities, or to prevent additional damage to the plant and/or r adiological releases.

8.0 SPECIAL TOOLS AND EQUIPMENT None Applicable PEP-103 Rev. 0 Page 6 of 12

9*0 PROCEDURE STEPS 9.1 If you are relieving the Site Emergency Coordinator -Control Room, report your arrival to the Emergency Communicator-Control Room. Obtain a briefing from the Site Emergency Coordinator-Control Room on the status of the emergency. Mnen satisfied that the Technical Support Center is sufficiently manned and oper ational, inform the Site Emer gency Coordinator-Control Room that you are relieving him as Site Emergency Coordinator and direct him to assume the responsibilities of Operations Leader in the Control Room. Use tne public address system to notify all on-site personnel that the Technical Support Center has been activated and that you nave assumed the r esponsibilities of Site Emergency Coor dinator in the. Technical Suppor t Center.

9.2 If you are r elieving another Site Emergency Coor dinator-Technical Suppor t Center, obtain a br iefing on the status of the

.emergency and all actions taken and planned. Announce tnat you have r elieved the Site Emergency Coordinator-Technical Suoport Center to those individuals. who report to you.

9.3 Initiate and maintain a record of your activities in accordance with PEP-405 and ensure that your staff are also maintaining activity logs.

9.4 Conduct all communications activities in accordance with PEP-302 and PEP-303, and ensure that your staff ar e following proper communications'rocedures.

9.5 Ensure that tne Plant Operations Director is implementing Abnormal and/or Emergency Operation Procedures and Fire Pr otection Procedur es as dictated by the situation.

9.6 Ensur e that the Logistics Support Director has:

1. directed the implementation of access control in .

accordance with PEP-380, and security contingency procedures as appropriate to the situation.

2. directed the implementation of personnel accountability in accordance witn PEP-382.

3. provided for access control and set up of the Emergency Operations Facility (if the emergency classifi.cation is Site Emergency or higher, or if discretionar y activation of the Emergency Operations Facility has been di. ected.)

9.7 Ensure that the Emer gency Communicator is implementing the necessary procedures to notify:

1. CP&L response oersonnel in accordance with PEP-321.

PEP-103 Rev. 0 page 7 of 12

9.0 PROCEDURE STEPS

2. local fire departments and/or rescue squads, the Nuclear Regulator y Commission, State and local authorities and ENPO in accor dance with PEP-301.

e

~ ~

9.8 Ensure that the Radiological Control Director has:

dir ected that all occupied emergency facilities and assembly areas be surveyed for habitability.

2. directed that samples of the containment atmosphere and/or plant systems be taken as appropriate.

3. dir ected the continuous monitoring of Radiation Monitoring System Data, and is ensuring that other Directors and tneir team leaders are being kept aware of changing r adiological conditions.

directed the implementation of emer gency radiation exposure control and personnel protection procedur es.

9.9 Ensure that the Emergency Repair Director nas dispatcned damage control teams to investigate reports of out of service or malfunctioning equipment that is necessary to place the plant in a safe condition.

9.10 Ef a gaseous r elease of radioactive material is known or suspected to have occur ed or is imminent, ensur e that:

the Plant Operations Director has dir ected the isolation of the potable water system.

2. the Logistics Support Director has dir ected tne isolation of foodstuffs.

3. the Radiological Control Director has directed tne implementation of dose pr ojection and environmental monitoring procedures, and the analysis of potable water for radioactivity.

9.11 Based on data and recommendati.ons provided by the Plant Operations Director and Radiological Contr ol Director, continuously assess and reclassify tne accident as appropr iate in accordance with PEP-101.

9.12 Whenever the emergency is r eclassified, consult with the Radiological Control Dir ector to determine wnether protective actions ar e necessar y for personnel r esponding to the site, then direct the Emergency Communicator to notify additional CPhL response personnel as appropr ate in accor dance witn PEP-321.

Until relieved of this re ponsibility by the Emergency Response Manager, direct tne Log sties Suppor t Director to request PEP-103 Rev. 0 Page 8 of 12

9.0 PROCEDURE STEPS additional off-site assistance as needed in accordance with PEP-322, determine any change to r ecommended protective actions in accordance witn PEP-104, and direct the notification of off-site autnorities in accordance with PEP-301. If appropr iate, direct the 'Logistics Support Dir ector to activate the Emergency Operations Facility in accordance with PEP-323.

9.13 As soon as data on radiological releases, off-site dose projection and/or environmental monitoring become available, and until relieved of this responsibility by the emergency Response Manager, direct the Emergency Communicator to perform follow-up notifications to off-site author ities in accordance with PEP-301.

9.14 When personnel accountability is complete, ensure tnat the Plant Operations Director implements sear ch and rescue efforts as required. Based on recommendations from the Radiological Contr ol Director, direct protective actions for on-site personnel in the assembly areas as appropriate.

9.15 If necessary to save a life or prevent furtner plant damage and/or radiological releases, and in the absence of the Plant General Manager and the Manager Environmental and Radiation Control, authorize planned radiation exposures in excess of regulatory limits and/or entry into radiation fields in excess of 100R/hr in accordance with PEP-371.

9.16 Based on recommendations from the Radiological Control Director, authorize the di,stribution of Potassium Iodide to on-site emer gency wor kers in accordance with PEP-383

'esignated if war r anted.

9.17 After the on-site response organization is fully manned, ensur e that the Logistics Support Director is coordinating the prepar ation of shift schedules adequate to ensure 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> continuity of the emergency response effort, identifying the need for augmentation, and dismissing unnecessary personnel so that they will be adequately rested to relieve the initial responders.

9.18 Direct tne Logistics Suppor t Director to request assistance from the Emergency Operations Facility, Corporate Emergency Operations Center, and/or contractor s and agreement organizations in accordance with PEP-322 as necessar y to augment the shift schedules.

9.19 When damage reports are made, ensur e that the Emergency Repair Director, Plant Operations Director, and Radiological Control Director are developing,a course of corrective action, and

.tnat the Logistics Support Director is directing the issuance or pr ocurement of any required mater ials or supplies.

PEP-103 Rev. 0 Page 9 of 12

9.0 PROCEDURE STEPS 9.20 When the Emergency Response Manager and his staff are ready to be br iefed on the emer gency, you may designate a qualified alternate te relieve you in accordance with Step 9.2 of this procedure if one is available. Using Attachment 1 as a guide, brief the Emergency Response Manager and his staff on the status of the emergency and all actions taken or planned. If you were relieved by an alter nate, relieve your alternate in accordance with Step 9.2 of this procedure to reassume the position of Site Emergency Coordinator after the briefing is complete.

NOTE: If the Emergency Response Manager and his staff came to the Technical Support Center for a .ace-to-face br i,ef ing, the Emergency Response Manager will telephone the Site Emergency Coor dinator to be updated on any change in conditions or actions that have occurred since the br iefing after they ar rive at the Fmergency Operat,ions Facility. The Emergency Response Manager will then activate the Emergency Operations Facility and relieve the Site Emergency Coordinator -Technical Support Center of off-site responsibilities.

9.21 Periodically throughout the emer gency, inform the entire plant emergency organization of the status of the plant and actions taken by making announcements over tne public address system.

9.22 When the emergency is downgraded to a lowe." classification, request the emergency director s to recommend which positions, if any, are no longer needed to manage tne emergency. If the Emer gency Operations Facility is activated, obtain concurrence fr om the Emergency Response. Manager, tnen direct the dismissal of tnose plant emer gency personnel who are no longer required.

9.23 When the emer gency is terminated, direct the transit,ion to recover y in coordination with the Emer gency Response Manager and in accordance with PEP-500. Deliver your activity log and any otner documentation generated during the emer gency to the Senior Specialist-Emergency Preparedness.

1 0. 0 DIAGRAMS/ATTACHMENTS

1. Site Emergency Coordinator Turnover Checklist PEP-103 Rev. 0 Page 10 of 12

ATTACHMENT Site Emergency Coordinator Turnover Checklist ON-SITE SITUATION Review status of major plant safety equipment and systems, specificly including tne status of the fission product barriers.

2. Reviews cause and history of the emer gency condition.

a. Initiating events

b. Sequence of follow-up events

c. Other details (specificly revie~ any suspect instrumentation that could possibly be an indication that a r elease is occurring).

3. Review and determine emergency actions initiated.

a. Plant-specific

b. On-site protective actions

c. Exclusion Area Review resources available on site and resources needed.

5. Identify key personnel on duty.

a. Site Emergency Coordinator

b. Plant Oper ations Dir ector

c. Emergency Repair Director

d. Logistics Support Director

e. Radiological Contr ol Director

f. SERT Representative OFF-SITE SITUATION

1. Review off-site notifications made.

a. Corporate

b. State PEP-103 Rev. 0 Page 11 of 12

APR014

c. NRC

d. '4'est inghouse

e. Ebasco Services

f. Other: Duke, VEPCO, SCE&G, INPO, ANl, FERA

2. Determine what other notifications should be made.

3. Review Protective Action Recommendations made for the public.

4. Review current status of off-site (local/state government) activation, readiness, actions,etc.

5. Review current status of any off-site evacuations, sheltering, and reception/decontamination centers.

6. Review progress and location of any radiological plume.

7. Determine other resources needed

8. Review the time and content of the most recent media briefing.

PEP-103 Rev. 0 Page 12 of 12

APR015 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE NUMBER: PEP-104 TITLE: PROTECTIVE ACTION RECOMMENDATIONS REVISION 0 APPROVED:

Signature Da e TITLE:

PEP-104 Rev. 0 Page 1 of 15

APR015 TABLE OF CONTENTS

~Pa e 1.0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 2.2 Referenced Plant Emergency Procedures 4 2.3 Other References 3.0 RESPONSIBILITIES 4 3.1 Site'mergency Coordinator 4, 3.2 Emergency Response Manager 5 3.3 Radiological Control Director/ 5 Dose Projection Team Leader 3.4 Radiological Control Manager/

Dose Assessment Team Ieader 3.5 Plant Operations Director 5 4.0 DEFINITIONS 5 5.0 GENERAL 5 5.1 Protective Action Guidel'ines 5' 5.2 Description of Protective Action Options 5.3 Protective Action Guidelines Based Upon Plant Conditions 6 5.4 Protective Action Guidelines Based Upon Project ed Doses 7 5.5 Identification of Affected Area 7 6.0 INITIATING CONDITIONS 8 7.0 PRECAUTIONS AND LIMITATIONS 8 8.0 SPECIAL TOOLS AND EQUIPMENT 8 9.0 PROCEDURE STEPS 9 10 ' DIAGRAMS/ATTACHMENTS 11

1. Evacuation Times - SHNPP Plume Exposure Emergency Planning Zone 12

2. Protective Action Recommendations Decision Tree (Based on Plant Conditions) 13

3. Local Emergency Planning Zones Map 14

4. Determination. of Affected Subzones Based Upon Vind Direction and Speed 15 PEP-104 Rev. 0 Page 2 of 15

APR015 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 through 15 0 PEP-104 Rev. 0 Page 3 of 15

APR015 1.0 PURPOSE The purpose of this procedure is to implement section 4.5 of the SHNPP Emergency Plan, "Protective Actions for the Public."

This procedure provides guidelines for determining protective action recommendations to be made to the State, and Chatham, Harnett, Lee and Vake Counties, during a General Emergency.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 4.5, "Protective Actions for the Public"

2. Annex G, "Interfacing Information from Supporting Emergency Plans" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP.-101, "Initial Emergency Action"

2. PEP-102, "Site Emergency Coordinator - Control Room"

3. PEP-103, "Site Emergency Coordinator - Technical Support Center

4. PEP-204, "Radiological Control Director"

5. PEP"216, "Dose Projection Team Leader" 6." PEP-301, "Notification and Communications"

7. PEP-341, "Manual Dose Projection"

8. PEP-342, "Automation'f Dose Projection-ERFIS"

9. PEP-344, "Automation of Dose Projection-IBM PC" 2.3 OTHER REFERENCES

1. USEPA 520/1-75-001, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents"

2. Title 10, Code of Federal Regulations, Part 50 Appendix E.

3. NUREG"0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants."

4. NRC IE Information Notice No. 83-28, "Criteria for Protective Action Recommendations for General Emer-II gencies.

3.0 RESPONSIBILITIES

1. SITE EMERGENCY COORDINATOR The Site Emergency Coordinator recommends to off-site government authorities, protective actions which should be taken by the public until relieved of this responsibility by the Emergency Response Manager. After the Emergency Operations Facility is activated, the Site Emergency Coordinator is responsible for advising the Emergency

. Response Manager as to what fission product barrier conditions exist in order to determine that portion of the off-site protective action recommendation based on plant conditions.

PEP-104 Rev. 0 Page 4 of 15

APR015 3.0 RESPONSIBILITIESS

/

2. EMERGENCY RESPONSE MANAGER After the Emergency Operations Facility is activated, the Emergency Response Manager relieves the Site Emergency Coordinator of the responsibility to recommend to govern-ment authorities what protective actions should be taken by the public.

3. RADIOLOGICAL CONTROL DIRECTOR The Radiological Control Director is responsible for determining what recommendations for continuing protective action based upon plume conditions should be taken by the public and for advising the Site Emergency Coordinator concerning radiological conditions when the Technical Support Center is activated.

4. RADIOLOGICAL CONTROL MANAGER The Radiological Control Manager is responsible for determining what recommendations for continuing protective action based upon plume conditions should be taken by the public and for advising the Emergency Response Manager when the Emergency Operations Facility is activated.

5. PLANT OPERATIONS DIRECTOR The Plant Operations Director (or in his absence the Shift Technical Advisor) is'esponsible for informing the Site 1

Emergency Coordinator of the existing fission product barrier status to allow the Site Emergency Coordinator to make a determination of off-site protective action rec-ommendations when a General Emergency is first declared.

4.0 DEFINITIONS Fission Product Barrier - The fuel cladding, reactor coolant system boundary, or the containment .boundary. A "Fission Product Barrier Status Board" is used to determine Emergency Action Levels and to determine recommendations for protective actions offsite based on plant conditions.

Protective Actions - Actions taken to afford dose savings to a population at risk when the benefits derived from such action are sufficient to offset any undesirable features of the actions taken.

5.0 GENERAL 5.1 PROTECTIVE ACTION GUIDELINES The guidance below is based upon the provisions of NUREG-0654 and the North Carolina Emergency Response Plan in Support of the Shearon Harris Nuclear Power Plant.

PEP-104 Rev. 0 Page 5 of 15

APR015 5.0 GE HERSE The protective actions in this procedure are limited to minimizing the exposure of the public from external and internal radiation exposure from passage of, deposition from or inhalation of, an airborne radioactive plume.

Other protective actions for minimizing public exposure via the ingestion pathway (food and water consumption) are described in Table 4.5.2 of the SHNPP Emergency Plan.

5.2 DESCRIPTION

OF PROTECTIVE ACTION OPTIONS 5.2.1 Evacuation Timely evacuation of members of the population is the most

,effective protective action. .There are, however, disad-vantages and constraints that may make evacuation inappro-priate. An estimate of the time necessary to effect an evacuation of SHNPP emergency planning zones is shown in Attachment 1 of this procedure.

5.2.2 Sheltering Sheltering is a protective action which involves members of the general public taking cover in a building or home that can be made relatively airtight. The representative protection factors for surface deposited radionuclides and for a gamma cloud source are as follows:

Shelter PF Surface Contamination ~PF Cloud Wood Frame Home 2.5 (No Basement)

Masonry Home 1.7 (No Basement)

Sheltering is suitable as a protective action alone or may be used in lieu of evacuation for:

Severe incidents in which an evacuation cannot be implemented because of inadequate lead time due to the rapid passage of the plume ("puff" release).

When an evacuation is indicated, but local con-straints, such as inclement weather, road conditions, etc., dictate that directing the public to seek shelter is a more feasible and effective protection measure than evacuation.

PEP-104 Rev. 0 Page 6 of 15

APR015 5 .0 GENERAL 5.3 PROTECTIVE ACTION GUIDELINES BASED UPON PLANT CONDITIONS When a General Emergency is first. declared, protective action recommendations shall be made based upon the plant fission product barrier conditions stated in Appendix 1 to NUREG-0654 for General Emergency, pages 1-17 and 1-18.

A flow chart depicting protective action recommendations based on plant conditions is provided as Attachment 2.

5.4 PROTECTIVE ACTION GUIDELINES BASED UPON PROJECTED DOSES As radiological release information becomes available, increase the zones affected by the recommendations in accordance with wind speed and direction, and dose projec-tions, as compared against the following guidelines:

5.4.1 No additional protective actions should be recommended for members of the general public in incidents involving actual or potential radioac-tivity releases to additional zones which are projected to result in the following doses:

a. whole body: less than 1 Rem

b. thyroid doses: less than 5 Rem 5.4.2 Sheltering of members of the general public within additional affected zones should be recommended in incidents involving actual or potential radioactivity releases which are projected to result in the following doses:

a. Whole. Body: 1 to 5 Rem

b. Child Thyroid: 5 to 25 Rem 5.4.3 Recommend evacuation (or sheltering if evacuation is not possible or fast enough) in additional affected areas if projected offsite doses exceed the following doses:

~ Whole Body: 5 rem

~ Child Thyroid: 25 rem 5.5 'IDENTIFICATION OF AFFECTED AREA The designation of the area requiring protective actions will depend on several variables, each of which will have to be evaluated at the time of the incident. Major variables include the plant condition and existing meterological conditions.

PEP-104 Rev. 0 Page 7 of 15

APR015 5.0 GENERAL Generally, the affected area will consist of local emer-gency planning zones that are intersected by a keyhole consisting of a circle with a 90 (or larger) wedge shaped sector attached in the downwind direction.

As a result of uncertainty, three general evacuation bands are to be considered. The first is a two-mile radius circle surrounding the plant. If ~an offsite protective action is necessary, this initial two-mile band will be included in the recommended area in which protective actions are to be implemented. The second band is the area between two miles and five miles and may be zones intersected by as little as a 90 wedge, or up to a com-plete circle. The third band is the area between five miles and ten miles, and as before may range from 90 to a complete circle.

County and State authorities have been provided with maps having sector designations showing the emergency planning subzones.

For reference, affected local plume exposure pathway emergency planning-subzones can be grouped as follows:

2 Miles: Zone A.

5 Miles: Zones A, B, C, D, K and L 10 Miles: All zones These zones are shown on Attachment 3.

6.0 INITIATING CONDITIONS An emergency has been declared at SHNPP in accordance with the SHNPP Emergency Plan and implementing procedures PEP-102 or PEP-103, and the emergency has been classified as a General Emergency.

7.0 PRECAUTIONS AND LIMITATIONS Protective action recommendations could be influenced by factors not considered here, and consequently the actual protective actions taken by the State and Local Govern-ments may vary from those recommended here. Such factors may include inclement weather, existence of other emer-gencies, hazardous conditions, or timing.

2~ The Site Emergency Coordinator(or Emergency Response Manager when Emergency Operations Facility is activated),

must approve a protective action before the recommended action is communicated to offsite authorities.

PEP" 104 Rev. 0 Page. 8 of 15

APR015 7.0 PRECAUTIONS AND LIMITATIONS P

3. SHNPP should not generally recommend the downgrading of a protective action when an emergency classification is downgraded. The state should be informed when plant conditions are stabilized and have subsided and the State should decide when and to what level protective action will be downgraded.

4. The Site Emergency Coordinator may consult with the Emergency Response Manager, if available, (before the Emergency Operations Facility is activated), or the Emergency Response Manager may consult with the Site Emergency Coordinator (Emergency Operations Facility activated) prior to the decision for offsite protective action recommendations.

8.0 SPECIAL TOOLS AND E UIPMENT None Applicable 9.0 PROCEDURE STEPS Consult the Emergency Action Levels (Fission Product Barrier Status Trees) in PEP-101 to determine the status of the fuel, primary system, and containment barriers, if known.

2. Consult the Protective Action Recommendation Decision Tree (Attachment 2) to determine the offsite protective action recommendation for the public.

NOTE: The recommendations based upon plant conditions will result in an offsite protective action for either 2 miles radius and 5 miles downwind, or 5 mile radius and 10 miles downwind, plus sheltering..in other..zones. in most cases.

a. Determine the offsite protective action recommend-ations based upon plant conditions.

b. If an automated offsite dose pro]ection is available, determine if any protective action guidelines are exceeded (in accordance with Section 5.4 ) in any emergency planning subzones. Record affected zones here:

LIST ZONES No Action:

Shelter:

Evacuate:

PEP-104 Rev. 0 Page 9 of 15

APR015 9,0 PROCEDURE STEPS

3. Determine wind direction (from) and speed using one of the following methods, which are listed in order of preferred Use:

a. Access the meterological data on the Emergency Response Facility Information System to determine wind speed and direction.

b. Call Radiation Control and request the wind speed and wind direction from the Radiation Monitoring System report processor (RM-21).

c. Call the Corporate Meteorology Center and request the current wind speed and wind direction for the Harris plant.

d. Dete'rmine wind speed and wind direction from visual observations outdoors.

4. Using the information obtained from Steps 2a and 3 above, consult Attachment 4 to determine the affected emergency planning subzones based upon plant conditions. List them here:

No Action:

Shelter; Evacuate:

5. Compare subzones in Step-2b with subzones identified in Step 4. If a subzone has conflicting recommendations choose evacuation over sheltering and sheltering over no action. List the compared affected subzones here:

Shelter:

Evacuate:

6. Consult the evacuation time estimates (Attachment 1) and consider weather conditions to determine whether recom-mended evacuations will occur during plume passage. If evacuation cannot be accomplished before plume arrival in an affected zone, recommend sheltering for that zone unless the lume is a result of a continuous release of duration reater than the evacuation time for that sub-zone. If the preferred recommendation is sheltering versus evacuation, list the affected subzones to be evacuated after plume passage.

PEP-104 Rev. 0 Page 10 of 15

APR015.

9.0 PROCEDURE STEPS NOTE: Concentrate on evacuation of subzones near the plant. For example, there may be time to evacuate Subzone A (100-160 minutes) but not one or more subzones within five miles(minimum of 160 minutes).

7. List the affected emergency planning subzones with the appropriate recommendation in Section 10 of Part I of the "North Carolina Emergency Notification Form", Attachment 2 to PEP-301. Complete initial notifications per PEP-301.

NOTE: A dose projection can be used in Step 2b at this time.

8. Once the initial protective action recommendations have been communicated per procedure PEP-301, continue assess-ment by reviewing the fission product barriers status, dose projections and environmental monitoring results to determine (by performing Steps 2 through 5) if any protec-tive action recommendations should change. If any rec-ommendations are changed, issue a follow-up emergency notification per PEP-301 listing the affected subzones and the appropriate protective action recommendation.

9. Utilizing dose projections and field monitoring data, recommend, in a follow-up communication, evacuation of emergency planning subzones that are sheltering where plume passage has resulted in ground contamination.

10. 0 DIAGRAHS ATTACHMENTS Evacuation Times - SHNPP Plume Exposure Emergency Planning Zone

2. Protective Action Recommendations Decision Tree (Based. on Plant Conditions)

3. Local Emergency Planning Zones Map 4, Determination of Affected Subzones based upon wind direction and speed

'EP-104 Rev. 0 Page 11 of 15

APR015 ATTACHMENT 1 a

Evacuation Times - SHNPP Plume Exposure Emergency Planning Zone Local Planning Evacuation Time Resident b

Case Zones Evacuated Description (minutes) cpd Population 2-mile radius 100-160 A,B,C 5-mile 90 NE 160"200' 1,049 A,C,D 5-mile 90 SE 160-180 257 A,K 5-mile 90 SV 170 640 A,B,K,I 5-mile 90 NV 170-200 2,042 A,B,C,D,K,L 5-mile radius 170-200 2,299 A,B,C,D,E,F,G 10-mile 90 NE 172 236 14,576 A,C,D,G,H,K 10-mile 90 SE 172-190 7,540 A,K,J,I 10-mile 90 SV 170-180 1,740 10 A,B,K,L,M,N 10-mile 90 NV 172-200 3,635 All Entire EPZ 172-236 19,832 Notes

a. From: Evacuation Time Estimates for the Plume E osure Pathwa Emer enc Plannin Zone Shearon Harris Nuclear Power Plant, HMM Associates, Inc.,

Raleigh, NC (October 1983).

b. Attachment 3 shows the boundaries of each, local planning zone ce This range of evacuation times covers four conditions: Good Veather-summer weekday, summer weekend, and'summer evening; and Adverse Veather-late fall weekday.

d. Evacuation time includes public alerting and notification (15 min-utes),preparation for movement, and time to travel out of the local planning zone(s) being evacuated.

ee There are no permanent, residents in Local Planning Zone A. The evacuation time estimate applies to the transient population that may be present in recreation areas, and the working population.

PEP-104 Rev. 0 Page 12 of 15

RCS CONTAINMENT UPDATE CSF FUEL FPS BREACH FPB BREACH STATUS BOARD FPB BREACH 0 0 0 0 0 CSF-I CSF-2 CSF-'5 CSF-4 CSF-5 SUBCRITICALITY CORE CODLING HEAT SINK IN T EGR IT Y CONTAINMENT 0

0 0 0 0 0 0 0 0 0

0 0 0 0 0 CSF-I YES RED OR MAGENTA NO CSF-2 YES REO FUEL JEOPARDY NO FUEL FPB OK YES CSF 3 RED OR MAGENTA YES CSF 4 RED RCS JEOPARDY NO RCS FPB OK CSF-5 YES RED NO CSF-5 MAGENTA CONTAINMENT JEOPARDY MO CONTAINMENT FPS OK UPDATE FPB STATUS BOARD FUEL RCS CONTAINMENT FPB FPB FPO INTACT INTACT INTACT BREACHED/ BREACHED/ BREACHED/

JEOPARDY JEOPARDY JEOPARDY ANY ADDITIONAL FPBs BREACHED/

JEOPARDIZED EAL FLOWPATH REVIEWED HIGHEST LEVEL EMERGENCY AS DETERMINED BY EAL FU)WPATH SITE GENERAL ALERT EMERGENCY EMERGENCY GENERAL SITE 2 FPB's I FPB 3 FPB s ALERT NO NO NO NO EMERGENCY NO NO EMERGENCY BREACHED/ BREACHED/ (FROM FLOWFATH BREACHED/

%%M FLOWPATH (FROM FLDWPATH JEOPARDIZED JEOPARDIZED OR ATWS) JEOPARDIZED OR ATWS) OR ATWS)

NO YES YES YES YES YES ATWS EVALUATE AGAINST UNUSUAL EVENT MATRIX ANY UNUSUAL MANUAL EVENT NO REACTOR TRIP CONDITION SUCCESSFUL YES FUEL FPB YES BREACHED/

JEOPARDIZED NO ATWS ATWS ATWS ALERT SITE EMERGENCY GENERAL EMERGENCY DECLARE DECLARE DECLARE NO I DECLARE SITE ALERT UNUSUAL EMERGENCY GENERAL EMERGENCY EVENT DECLARATION EMERGENCY TIME TIME TIME TIME TIME GP TO PEP-IOI UNUSUAL EVENT MATRIX SECURITY THREAT NATURAL PHENOMENA AND SITE EMERGENCY OTHER EVENTS OR SPECIFIC PRIMARY SYSTEM TO LOSS OF PRIMAR'I SYSTEM LOSS OF SHUTDOWN REACTOR PROTECTION AND LOSS OF POWER OR FIRE GASEOUS OR LIQUID LOSS OF A FISSION LOSS OF SECONDARY OTHER PLANT HAZARDS COORDINATOR JUDGEMENTS LCOs EXCEEDEO COOLANT OR COOUNG SECONDARY SYSTEM COOLANT FUNCTIONS (DECAY HEATI REACTIVITY INCIDENTS CONTROL BOARD ALARM EFFWENT( ~ ) EXCEEDING PRODUCT BARRIER LEAKAGE OR ACCIDENT MITIGATION INDICATIONS TECHNICAL SPECIFICATIOHS FUNCTIONS FIRE LASTING MORE THAN A SECURITY ALERT HAS NATURAL PHENOMENON OR OTHER PLANT CONDITIOMS SAFETY INJECTION SYSTEM MAIN STEAM OR PRIMARY-TO-SECONDARY PRIMARY SYSTEN COOLANT LOSS OF CONTAINMENT UNCONTROLLED RCCA LOSS OF ALL OFFSITE DISCHARGES TO RCS.

LIQUID EFFLUENT FUEL DAMAGE INDICATION. POWER. 10 MINUTES WITHIN THE BEEN DECLARED, BUT MAN MADE EVENT HAVING EXISTING WHICH WARRANT FEEDWATER BREAK: LEAKAGE GREATER THAN LEAKAGE GREATER THAN INTEGRITY REQVIRINO WITHDRAWAL VNCONTROLLEO TRANSPORTATION OF CONCENTRATION TECHNICAL PRIMARY COOLANT SAMPLE POTENTIAL FOR DEGRADING INCREASED AWARENESS ON TECHNICAL SPECIFICATIONS. TECHNICAL SPECIFICATIONS. SHUTDOWN BY TECHNICAL RCCA SANK WITHDRAWAL, LOSS OF ALL ON-SITE AC CONTAINMENT, REACTOR THERE IS NOT AN CONTAMINATED, INJURED SPECIFICATION LIMITS ACTIVITY (LATER) . I) INSIDE CONTAINMENT, POWER (INCWDINO ESF AUXILIARY FUEL HANDLINGr IMMINENT THREAT TO VITAL PLANT SAFETY INCLUDINO: THE PART OF THE PLANT

2) OUTSIDE CONTAINMENT . FAILURE OF A PRESSURIZER SPECIFICATIONS IMPROPER STARTUP OF INDIVIDUAL TO HOSPITAL.

EXCEEDEO FOR 15 MINUTES. POWER I FOR GREATER WASTE PROCESSING, DIESEL, EQUIPMENT. THE SE(XIRITY a) ANY ALARM ON SEISMIC STAFF, CHATHAM, HARNETT.

FAILURE OF A STEAM SAFETY OR RELIEF VALVE LOSS OF ESF OR FIRE REACTOR COOLANT PUMP. INADVERTENT DISCHARGE OF GASEOUS EFFLUENT MALFUNCTION RESULTINO IN THAN 5 MINUTES OR TURBINE BUILDING THREAT MUST BE THE MONITOR AND CONFIR- LEE, AND WAKE COUNTIES, GENERATOR SAFETY OR TO RESEAT AFTEII OPERATION. PROTECTION FUNCTIOHS CONTAINMENT SPRAYS.

TECHNICAL SPECIFICATION WHICH MAY AFFECT SAFETY RESULT OF ANY ADVERSARY MATION OF AN EARTH- THE STATE OF NORTH RELIEF VALVE TO RESEAT REQUIRINS SHUTDOWN BY BORON DILUTIOH AHY INCIDENT INVOLVINO INSTANTANEOUS LIMITS RELATED EQUIPMENT. INITIATED INCIDENT OR QUAKE IN THE REGION, CAROLINA, AND THE NUCLEAR EXCEEDED FOR ONE HOUR. AFTER OPERATION. TECHNICAL SPECIFICATIONS. I) HOT STANDBY (MODE 3) REGULATORY COMMISSION . LICENSED NUCLEAR MUST HAVE THE POTENTIAL b) ANY TORNADO CROSSING STEAM GENERATOR GREATER THAN IT MATERIAL WHICH CAUSES A MINUTES, TO THREATEN VITAL THE SITE BOUNDARY BLOWOOWM LINE BREAK.

EQUIPMENT. (EXCLUSION AREA LOSS OF 24 HOURS OR

2) STARTUP (MODE 2) MORE OF PLANT OPERATION GREATER THAN IS BOUNDARY)(BY OBSERVATION OR OR O2000 IN PROPERTY MINUTES, DAMAGE.

EVIDENCE),

3) POWER OPERATION (MODE I) GREATER THAN 8 ANY ICE STORM CAUSING LOSS OF ONE OF THE 30 MINUTES AFTER REDUNDENT OFF SITE REACTOR TRIP. 16 POWER SOURCES,

8) ANY AIRCRAFT CRASH OR TRAIN DERAILMENT WITHIN THE SITE BOUNDARIES, a) ANY UNPLANNED EXPLOSION WITHIN THE SITE BOUNDARIES, l) ANY RELEASE OF TOXIC OR FLAMMABLE OAS THAT COULD ENDANGER SITE PERSONNEL ATTACHMENT 1 17 EMERGENCY ACTION LEVEL NETWORK PEP 1p1 RFV p PAGE 9 OF 15

ONE SAFETY SYSTEM NO TRAIN YES DEFEATED FIRE ONE YES SHUTDOWN NO REDUNDANT FUNCTION SAFETY SYSTEM NO DEFEATED NO TRAINS DEFEATED ONE SHUTDOWN YES REDUNDANT FUNCTION YES SHUTDOWN NO DEFEATED FUNCTIONS DEFEATED ALERT YES SITE EMERGENCY LOSS YES OF POWER LOSS LOSS OF ALL NO OF MOST/ALL ON SITE CONTROL NO NO POWER BOARD ALARMS/INDICATION LOSS YES OF ALL HO YES ON SITE ESF OC LOSS OF ALL YES OFF- SITE GREATER YES NO POWER THAN 5 MIN.

LOSS NO NO OF GREATER NO YES AFW THAN 15 MIN.

POWER YES YES GREATER LOSS GREATER NO THAN 5 MIN. YES ALERT THAN RCS 15 MIN.

LEVEL SITE LESS THAN TOP NO GREATER EMERGENCY ALERT NO THAN NO IRRADIATED YES FUEL 15 MIN.

SITE YES ALERT EMERGENCY YES GENERAL SITE EMERGENCY EMERGENCY EFFLUENT YES DOSE RELEASE RATE AT EAB (PROJECTED OR NO MEASURED) m 500 NR/HR NO FOR 2 MIH.

NO YES GREATER THAN 10s YES AT EAS TECH SPEC M)REM WHOLE OR INSTANTANEOUS 5 REM LIMITS GENERAL THYROID EMERGENCY YES YES ALERT SITE EMERGENCY FUNCTIONS REQUIRED FOR SHUTDOWN LOSS OF COLD S/D HOT S/D FUNCTION YES REQUIRED FOR 4FW PUMPS X SHUTDOWN BORIC ACID TRANSFER PUMPS X HOT 5/G PORVs X NO SHUTDOWN) RHR PUMPS X NO CCW SYSTEM X SERVICE WATER SYSTEM X COLD YES NO ON-SITE POWER SOPPY SYSTEM X SHUTDOWN)

D/8 FUEL OIL STORAGE AND TRASMFER SYSTEM SITE EMERGENCY HVAC SYSTEMS (IN REQUIRED LUIPMENT AREAS)

YES CONTROL ROOM PANEL AND 4UKILIARY CONTROL PANEL ALERT EMERGENCY LIGHTING SECURITY YES EMERGENCY SUCCESSFUL SABOTAGE NO OF VITAL EQUIP MEN T NO SUCCESSFUL YES PENETRATION NO OF VITAL AREAS ACTUAL OR IMMEDIATE IMISINENT POTENTIAL FOR YES YES OR ACTUAL THREAT NO OFF-SITE TO VITAL RADIATION AREAS RELEASE GENERAL EMERGENCY NO YES 5 IT E EMERGENCY ALERT FUEL HANDLING MULTIPLE ACCIDENT FUEL ASSEMBLIES INVOLVED RELEASE TO CONTAINMENT OR SITE FUEL EMERGENCY NO HANDLING NO ALERT NO EXPLOSION, NO NO AIRCRAFT CRASH, OR MISSILE OTHER TES YES EVENTS DAMAGED NO ADVERSE STRUCTURE( s) NO PERSONNEL 0) HO NO EARTHQUAKE WEATHER HOUSING SAFETY OPERABILITY OF SAFETY RELATED RELATED EQUIPMENT SYSTEMS YES YES YES YES GREATER CAUSING LOSS CAUSINQ LOSS CAUSING LOSS YES THAN OF TWO SAFETY YES OF TWO SAFETY OF TWO SAFETY 0.08 RELATED RELATED RELATED s TRAINS TRAINS TRAINS SITE EMERGENCY SITE NO SITE YES NO NO EMERGENCY EMERGENCY GREATER CAUSING (DSS CAUSING LDSS CAUSING LOSS NO OF ONE SAFETY OF ONE SAFETY NO OF ONE SAFETY THAN RELATED REL4TED RELATED 0.18 8 TRAIN TRAIH TRAIN YES ALERT YES YES YES SITE ALERT ALERT ALERT EMERGENCY CONTROL TURBINE OTHER MALFUNCTION NO NO ROOM DISK FAILURE CONDITION RESULTING EVACUATION RESULTING IN AIRBORNE WARRANTING RECOMMENDATION IN BORON YES REQUIRED/ CASING RADIATION LEVELS OF EVACUATION OR DILUTION ANTICIPATEO INDICATE SEVERE SHELTERING YES DEQRADATIDN TO SE TAKEN IN RADIOACTIVE GENERAL BY THE YES YES MATERIAL EMERGENCY PUBLIC CONTROL ALERT NO DURING REFUELING AUXILIARY NO YES YES SHUTDOWN GREATER THAN PANEL OR 4NY 47 MIN. OPERATIONAL PLANT SAFETY DEGRADING EVENT SITE CONCURRENT WITH/CAUSING EMERGENCY NO ANY LOSS/DEGRAOATK)N OF TWO SAFETY RELATED PLANT SAFETY TRAINS YES DEGRADIHG EVENT CONCURRENT WITH/CAUSING WHILE IN LOSS/DEGRADATION OF ONE GREATER COLD SHUTDOWN NO THAN SAFETY RELATED GREATER ALERT TRAIN NO 15 MIN.

THAN 2 MIN. ALERT NO SITE YES EMERGENCY YES OR SITE ALERT EMERGENCY OTHER CONDITION WARRANTING PRECAUTIONARY ACTI TATI 0 N OF THE TSC ATTACHMENT 2 EMERGENCY ACTION LEVEL FLOWPATH PEP-101 REV. 0 PAGE 10 OF 15 RETURN TO EAL NETWORK S kO'IIaO>eII Oa, D

FISSIOII FRCOUCT OEOIII 8ARRIER wrAcr PTCCARC ACCESSIUa.

4EUERAI. TRIIETRATIOJ VITAI.AREAS EMERORHcy f6OJRRAa. Tta OOJI 7ES F CACToa yES STATUS COHTAIIJMEtlr COOCAHT SysTCM OF FISS IOH YES I HTACT FEOOUCT SARRERS IHTACT KpXSJH COIJTIHUI PROT ECTIVE Ac IhUIPELItll5 EICRRDEO RECOMMEtJD COOLAIJT SVETEl4 RECOMMEHD 5 IIEcrERIH4 IHTAcr IIROTCCTIVEACTIOtl E'Mtca RADIUS HO 8ASED DH 5 EC TIOH 5'LES POIJJIJ WD O'8 CDHTI HUE CQHTIIJ4 C ASSESSMEHT A55C55MEHl IUCI IOSSICH PIIOOUCT COHTAIHMEHT SACIUCR IHTACT IHTACT COHTAIHMEur YES STATUS IHTACT OEH UCtl RECCMMCIJ P EMEROcucy CVACUATIou oF Oputl6 RAPED Z'MILE RADIUS 5 MlcES DOktatAHD Sttacraa wacac RECOMMEHD RECCMMRHP

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tJO yE5 IZEACTOR yES 5TATU5 COIJTAIIJ MEIJT OF FISSIONS CoOLAtJT SY5'TKJ4 I tJTACT MOPLICT BARR IER5 IIJ TACT ICNOLJtJ GCIIJTIIJLllhlCi PROT E'CTIVE ~TI0

@UI DELItJ 65 REAC TtOR K~EDED RECOMNIGIJD COOLAIJ T SYSTEM 5EESG IZECOMNIEIJD 5HELTEIZIIJA ltJrAcr 3 PROTECTI VE ACTIOIJ5 Z.-MILE RADIU5 5 MILES POWtJLJIIJD SA5ED OIJ 5'IOIJ 5'.3 COtJTI hlUE COIJTIIJLIE A55E55MEIJT A55E56MEhlr FUEL FISSIOIJ F ROPLICT COIJl A ltJMEIJT BARRIER ~'

3 tJrAGT IIJTA F(55IOIJ yE5 AZOPUCT &ARRIEJZ T'OhJTAItJMEJJT 5TATU5 HAIJ5EP INrACT NO 6EIJEIZAL IZECOMMEIJP EMERY EIJCY EVACUATIOIJ OF DOMtJSIZAPED

,XE 2-MILE RADIUS JlPE~]III 5. MILE5POLJKJWltJD Tug'QE) glkELTE'R LJHERE RECO MMES D JZE~KNP EVACUATIOtJ CAIJ IJOT EVACLJATIOIJ OF EVACUATIOtt OF SE COMPLETED SEFORE 2 Mll 6 IZADIU5 Z MILE RADIU5 PLUME ARRIVAL 5- MILE5 DDWIJhllI4t 5'ILE5 DOWtJW lhJP R'ECOMMEIJ Ct 5HELTERIIJCt FOR IZEMAltJ IIJ6 ZOIJE5 ATTACHMENT2 EVACUATE ZONEQ AFFECTED SY &ROUtJD PROTECTIVE ACTION RECOMMENDATIONS OIJlAMIIJATION FOL~ t INC PcUME PASSAGE PEP-104 Rev. 0 Page 13 of 15

0 VV g 41 1982 SHNPP PERMANENT RESIDENT POPULATION ESTIMATE&1 SUBZONE PEOPLE SU&ZONES

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APR015 ATTACHMENT 4 DETERMINATION OF AFFECTED SUBZONES BASED UPON WIND DIRECTION AND SPEED WIND AFFECTED DOWNWIND SUBZONES DIRECTION FROM A B C D K L E F G H I J M N 349-11 X X X X 0 X X 0 11-34 X 0 X X X X X 0 35 "56 X 0 X 0 0 X X .X 57-79 X X X X X, X 80 101 X 0 X X X X. X '

102" 124 X X X X 0 X X X 125 "146 X X X X 0 0 X X 147 169 X X X X X X X 170-191 X X 0 0 X X 0 X X 192 214 X X K X X X 0 0 X 215-236 X X X 0 X X X X X 237-259 X X X X 0 X X X

..260-281 . X,X X X X K X 0 282-304 X 0 X X 0 X X X X 305-326 X X X X 0 X X X 0 327-346 X X X X 0 X X X LEGEND:

X = UNDER ALL WIND CONDITIONS 0 = IF WIND SPEED IS LESS THAN 9 MILES PER HOUR PEP-104 Rev. 0 Page 15 of 15

APR015 CAROLINA POWER 6 LIGHT COMPANY

. SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP "201 TITLE: PLANT OPERATIONS DIRECTOR REVISION 0 "

APPROVED:

Signature Dat TITLE:

PEP-201 Rev. 0 Page 1 of 11

APR015

'TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4 2.3 Other Referenced Plant Procedures 3.0 RESPONSIBILITIES 4, 3.1 Reporting Responsibilities 4 3.2 Assignment and Relief of Position 4 3.3 Duties 5 4.0 DEFINITIONS 5 5.0 GENERAL 5 6.0 INITIATING CONDITIONS 6 7.0 PRECAUTIONS AND LIMITATIONS 6 8.0 SPECIAL TOOLS AND EQUIPMENT 6 9.0 PROCEDURE STEPS 6

9. 1 Initial Actions 6 9.2 Operations Leader 7 9.3 First Aid Team/Search and Rescue Team Leader 8 9.4 Fire Brigade Leader 9 9.5 Accident Assessment Team Leader 10 9 ' General 11 10.0 DIAGRAMS(ArrACHMENTS 11 PEP"201 Rev. 0 Page 2 of 11

APRO15 LEST OF EFFECTIVE PAGES

~Pa e Revision 1 through ll 0 PEP-201 Rev. 0 Page 3 of 11

APR015 1.0 PURPOSE The purpose of this procedure is to implement section 2.4.3 "Plant Operations Director" of the SHNPP Emergency Plan.

This proceduxe describes the actions of the Plant Operations Direc-tor when the Technical Support Center is activated.

2.0 REFERENCES

2.1 EMERGENCY'PLAN REFERENCES

1. Section 2.4.3, "Plant Operations Director" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-101, "Initial Emergency Actions"

2. PEP-104, "Protective Action Recommendations"

3. PEP-218, "Accident Assessment Team Leader"

4. PEP-301, "Notification and Communications"

5. PEP-302, "Communication Activities"

6. PEP-303, "Use of Communications Equipment"

7. PEP-321, "Notification of Emergency Personnel"

8. PEP-323, "Setup and Operations of Emergency Facilities"

9. PEP-382, "Personnel Accountability"

10. PEP-391, "First Aid and Medical Care"

11. PEP-394, "Search and Rescue"

12. PEP-401, "Record Keeping and Documentation"

13. "PEP-405, "Preparation of Activity Logs" 2.3 OTHER REFERENCED PLANT PROCEDURES

1. AP-002, "Plant Conduct of Operations"

2. AP-006, "Procedure Review and Approval"

3. AP-007, "Temporary Proceduze Revision Review/Approval" 4,. FPP-002, "Fire Emexgency" 3.0 RESPONSIBILITIES 3.1 REPORTING RESPONSIBILITIES

1. The Plant Operations Director reports to the Site Emergen-cy Coordinator-Technical Support Center

2. The Accident Assessment Team Leader, Fire Brigade Leader, Operations Leader (in Control Room), and First Aid Team Leader report to the Plant Operations Director.

3.2 ASSIGAiENT AND RELIEF OF POSITION The on-shift person who fills the position of Plant Operations PEP-201 Rev. 0 Page 4 of 11

APR015 3.0 RESPONSIBILITIES Director is the Site Emergency Coordinator (Shift Foreman) until relieved in the Technical Support Center by the Manager Operations, Operating Supervisor, or Principal Engineer-Operations.

3.3 DUTIES The Plant Operations Director is responsible to the Site Emergency Coordinator for providing direction to the Accident Assessment Team, the Control Room Staff, the Fi.re Brigade, and the First Aid Team.

Specifically, the Plant Operations Director:

1. Directs the Accident Assessment Team and Control Room personnel in determining the nature and extent of emergencies pertaining to equipment and plant facilities.

2. Ensures immediate corrective actions are carried out by Control Room personnel to minimize the consequences of the emergency.

3. Ensures adequate manning of the Control Room.

4. Coordinates recommendations to the Site Emergency Coordinator from the Accident Assessment Team.

5 ~ Designates a trained computer console operator for the Techn-ical Support Center. Ensures that data plotters are stationed at the status boards in the Technical Suppoxt Center.

6. Organizes and directs rescue operations of injured personnel.

7. Ensures Fixe .Brigade actions are in accordance with the Fire Plan and Fire Area Preplans.

8., Requests support from the Technical Analysis Manager, as necessary, after the Emergency Operations Facility is activat-ed.

9. He is also responsible for ensuring that he is relieved only by an alternate trained for duty as Plant Operations Director, and fox maintaining a record of his activities.

4.0 DEFINITIONS None Applicable

5. 0 GENERAL None Applicable PEP-201 Rev. 0 Page 5 of 11

APR015 6.0 INITIATING CONDITIONS The Site Emergency Coordinator has declared an emergency and act-ivated the Technical Support Center.

7.0 PRECAUTIONS AND LIMITATIONS 7.1 Immediately inform the Sit'e Emergency Coordinator if it is necessary to deviate from any existing plant procedure or to perform an action for which no procedure exists, but which would normally require a procedure in accordance with AP-002.

7.2 The Site Emergency Coordinator is responsible for overall control of the plant. No action shall be taken without his concur-rence that could affect the operability of a plant system.

8.0 SPECIAL TOOLS AND E UIPMENT None Applicable 9.0 PROCEDURE STEPS 9.1 INITIALACTIONS

1. If you are relieving anothez individual, review the activity log and obtain a briefing from your predecessor on the emergency and any actions that have been completed or are in progress; otherwise, obtain' briefing from the Site Emergency Coordinator.

2. Conduct all communications in accordance with PEP-302 and PEP-303.

3. Report your arrival in the Technical Support Center to the Emergency Communicator-Technical Support Center (Emergency Communicator-Control Room if the Emergency Communica-tor-Technical Support position is not yet manned) and inform the Site Emergency Coordinator that you are assum-ing (or relieving if appropriate) the position of Plant Operations Director.

4. Initiate and maintain a record of your activities in accordance with PEP-405.

5. Verify that the operations area is set up per PEP-323, Contact the Operations Leader to vezify that the Control Room is adequately manned. Designate available members of the operations staff to assist in the Control Room, if required.

PEP-201 Rev. 0 Page 6 of 11

APR015 9.0 PROCEDURE STEPS 9.1 INITIAL ACTIONS (Cont'd)

6. Verify that the Accident Assessment Team Leader, Fire Brigade Ieader; and the First Aid Team Leader are present and that their teams are adequately staffed, have been accounted fox according to PEP-382, and are standing by.

7. Designate an available member of the operations staff as a Phone Talker - Operations. Verify that a trained comput-er console operator is available to man the Emergency Response Facility Information System console in the Technical Support. Center Site Emergency Coordinator and Staff Room, and inform the Emergency Communicator-Technical Support Center.

8. Notify the Site Emergency Coordinator-Technical Support Center. that you and your staff are present and ready to support the Site Emergency Coordinator.

9. When directed to do so, notify the alternate for your position specified by the Site Emergency Coordinator to axrange for relief at the end of the present shift in accordance with Section 9.2 of PEP-321. Notification messages shall be given only to the specified individual, and not to their spouse, children, babysitter, etc. If the designated alternate cannot be contacted, notify the Logistics Support Director.

9.2 OPERATIONS LEADER 9.2.1 Check with the Operations Leader to determine the curxent status:

What is the current emergency classification and what is the basis for the classificationf

2. Is the reactor in a stable condition? If not, what actions are being taken to place it in a stable condition7 Are all systems necessary f'r a safe shutdown opera-tional'l If not, what actions are being

4. fisson product barriers (core, reactor taken'ave any coolant system, or containment) been breached or are any close to being breached2 (Notify Site Emergency Coordinator and Radiological Control Director as input to PEP-104 Protective .Action Recommendations)

5. Has anyone been reported injured or missing? If so, has the First Aid Team been notifiedV

6. Have any fires been reported'f so, has the Fire Brigade been notified'E Is the fire in an area containing safety related equipment7 PEP-201 Rev. 0 Page 7 of 11

APR015 9.0 PROCEDURE STEPS 9.2 OPERATIONS LEADER (Cont'd)

7. What emergency operating procedures (EOP'S), flow path procedures, and/or abnormal operating procedures are currently being used2 8 ~ Are there any critical tasks with which the Accident Assessment Team can assist you (such as reviewing blueprints to determine alternate'flow paths or performing calculations to ascertain if any limits have been exceeded)2 9.2. 2 ~ Based upon the report from the Operations Leader, provide assistance by performing the following actions as neces-sary:

If First Aid or Search and Rescue services are needed (or are in progress) go to section 9.3.

2. If fire fighting services are needed (or are in progress) go to section 9.4.

3. If Accident Assessment services are needed go to section 9.5.

4. If any additional operations personnel are needed contact the assembly area or Operational Support Center or have them called in.

5. If. maintenance assistance or radiation control assistance is needed, notify the Emergency Repair Director or Radiological Control Director, as-appro-priate, of the request.

9.2. 3. Provide technical and administrative direction to the Operations Leader as needed.

9.3 FIRST AID TEAM (SEARCH AND RESCUE TEAM) LEADER If personnel are injured or are missing, notify the First Aid Team Leader (if not previously notified) as per PEP-391 or 394 and brief him on the situation. (Attach-ment 1 to PEP-394 "Search and Rescue Briefing Form" may be used if appropriate.)

2~ Determine from the team leader what personnel are avail-able to compose the team. For Search and Rescue teams (or for First Aid Teams who must enter locked High Radiation areas), select personnel who best meet the requirements of Section 7.1 of PEP-394.

Check with the Radiological Control, Director to obtain available information on radiological conditions in the rescue area or area to be seazched, and recommend the best routes-to use to the First Aid Team Leader (Search and Rescue Leader).

PEP-201 Rev. 0 Page 8 of 11

APR015 9.0 PROCEDURE STEPS 9.3 FIRST AID TEAN LEADER(Cont'd)

4. Request that the Radiological Control Director provide a Personnel Protection and Decontamination Team member to assist the team if they will be entering radiologically controlled areas.

5. Notify all personnel where to assemble (normally the Operational Support Center).

6. Instruct the First Aid Team Leader to keep you posted.

7. If additional personnel or equipment are needed for rescue operations, request them from the appropriate Director or Assembly Area Leader and have them dispatched from the Operational Support Center.

8. If off-site medical personnel, rescue personnel or an ambulance are needed, notify the Site Emergency Coordina-tor and have him request the off-site assistance as per PEP-301.

9. If a contaminated injured person is to be taken to the hospital, notify the Site Emergency Coordinator because this constitutes an unusual event and must be reported to the NRC within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> as per PEP-301 unless a higher level emergency classification has already been reported.

10. Provide technical and administrative direction to the First Aid Team Leader, as needed.

When time permits, provide assistance to Regulatory Compliance in the description of events if a report to the Nuclear Regulatory Commission is required.

9.4 FIRE BRIGADE LEADER 9.4. 1. If a fire or explosion has occurred have the plant fire alarm sounded and the location announced.

9.4. 2. Contact the Fire Brigade Leader:

Brief him on the situation.

Instruct him to follow FPP-002 and the Fire Area Preplans.

3. Instruct him to brief you after he has evaluated the situation at the fire scene.

4 ~ Also direct him to notify you of the approach or exceeding of an Emergency Action level caused by the fire or fire fighting efforts.

9.4,3. If the fire lasts more than 10 minutes and may affect safety related equipment, notify the Site Emergency Coordinator that this may constitute an Unusual Event which he must report to the NRC within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> as per PEP-301 unless if a higher level of emergency classifica-tion has already been reported.

PEP-201 Rev. 0 Page 9 of 11

APR015 9.0 PROCEDURE STEPS 9.4 FIRE BRIGADE LEADER (Cont'd) 9.4 4. If additional personnel or equipment are needed at the fire scene, request them from the appropriate director and have them dispatched from the Operational Support Center.

9.4.5. If off-site fire personnel are needed, fillout the Immediate Response Organizations Notification Form (Att-achment 1 to PEP-301), have the Site Emergency Coordinator approve it and have the Emergency Communicator request the off-site assist as per PEP-301.

9.4.6. Provide additional technical and administrative directions to the Fire Brigade Leader, as needed.

9.5 ACCIDENT ASSESSMENT TEAM LEADER 9.5. 1. Direct the Accident Assessment Team Leader to have his team continuously .monitor plant parameters and system status indicators (via System Parameter Data and Status sheets and the Emergency Response Facilities Information System console) and assist the Control Room. personnel in determining the nature and extent of the emergency.

9.5.2. Direct the Accident Assessment Team Leader to monitor and evaluate vital plant parameters during the emergency to determine the overall conditions of safety related sys-tems, the core and fission product barriers.

9.5.3. Direct the Accident Assessment Team Leader to evaluate the parameters and indicators being monitored against Emerg-ency Action Levels in accordance with PEP-101 and recom-mend changes in the emergency classification when so indicated.

9.5.4.When accident assessment reports are received, develop a course of corrective or preventive actions as follows:

Determine whether or not any actions are actually necessary to place or maintain the plant in a safe shutdown condition, to prevent or reduce the release of radioactive material, to prevent or reduce further damage to the Plant, or to prevent personnel injuries and/or overexposure to radiation.

2. Evaluate available alternatives to determine which will have the least impact on eventual full recovery of the Plant, including potential requirements for rework, testing, and certification.

3. Determine the feasibility of the considered action(s) based on availability of resources.

PEP-201 Rev. 0 Page 10 of 11

APR015 9.0 PROCEDURE STEPS 9.5 ACCIDENT ASSESSMENT TEAM LEADER (Cont'd) 9.5 5. Determine whether or not procedures and/or instructions are required in accordance with AP-002. If required, existing plant procedures should be used to the maximum extent possible. If necessary, direct the Accident Assessment Team Leader to develop new procedures and/or changes to existing procedures as required in accordance with AP-006 and AP-007, respectively.

NOTE: In accordance with AP-002, authorize reasonable action that departs from license conditions, Technical Specifications, or the Plant Operating Manual in an emergency when this action is immediately needed to protect the public health and safety, and no action, consistent with license conditions, Technical Specifications, or the Plant Operating Manual is immediately apparent that can provide adequate or equivalent protection.

9.5.6, Provide technical and administrative direction to the Accident Assessment Team Leader as needed.

9.6 GENERAL Request any needed material or supplies not on the plant site from the Logistics Support Director.

2'. Periodically report to the Site Emergency Coordinator the status of plant systems and whether the plant is in a safe shutdown condition.

3. When the emergency has been terminated, deliver your activity log and copies of all records generated during the emergency to the Emergency Preparedness Specialist as per PEP-401.

10. 0 DIAGRAMS ATTACHMENTS None Applicable PEP-201 Rev. 0 Page 11 of 11

CAROLINA;POWER:,&,'-'LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2.,

PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-202 TITLE: EMERGENCY REPAIR DIRECTOR REV/SION 0 APPROVED:

Signature D e TITLE:

PEP-202 Rev, 0 Page 1 of 7

APR012 TABLE OF CONTENTS

~Pa e Table of Contents 1 2

List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

2.1 Emergency Plan References 2.2 Referenced Plant Emergency Procedures 4.

2.3 Other Referenced Plant Procedures 4 3.0 RESPONSIBILITIES 4 3.1 Reporting Responsibilities 4.

3' Assignment and Relief of Position 5 3.3 Duties 5 4.0 DEFINITIONS 5 5.0

'.0 GENERAL INITIATING CONDITIONS 5

5 7.0 PRECAUTIONS AND LIMITATIONS 5 8.0 SPECIAL TOOLS AND EQUIPMENT 6 9.0 PROCEDURE STEPS 6 10.0 DIAGRAMS/ATTACHMENTS 7 PEP-202 Rev. 0 Page 2 of 7

APR012 LIST"OF EFFECTIVE'PAGES

~Pa e Revision 1 thru 7 0 PEP-202 Rev. 0 Page 3 of 7

APR012 1.0 PURPOSE This procedure implements Section 2.4.4 of the SHNPP Emergency Plan.

It specifies actions to be performed by the Emergency Repair Director.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 2.4.4, "Emergency Repair Director" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-211, "Damage Control Team Coordinator"

2. PEP-212, "Operational Support Center Leader"

3. PEP-302, "Communications Activities"

4. PEP-303, "Use of Communication Equipment"

5. PEP-321, "Notification of Emergency Personnel"

6. PEP-323, "Setup and Operation of Emergency Facilities"

7. PEP-382, "Personnel Accountability"

8. PEP-405, "Preparation of Activity Logs" 2.3 OTHER REFERENCED PLANT PROCEDURES

1. AP-002, "Plant Conduct of Operations"

2. AP<<006, "Procedure Review and Approval"

3. AP-007, "Temporary Procedure Revision Review/Approval" MMM-001, "Maintenance Conduct of Operations"

5. MMM-002, "Corrective Maintenance" 3.0 RESPONSIBILITIES 3.1 REPORTING RESPONSIBILITIES

1. The Emergency Repair Director reports to" the Site Emergency Coordinator in the Technical Support Center.

2. The Operations Support Center Leader and Damage Control Team Coordinator report to the Emergency Repair Director.

PEP"202 Rev. 0 Page 4 of 7

APR012 3'.0 RESPONSIBILITIES P

3.2 ASSIGNMENT AND RELIEF OF POSITION Until relieved by the Manager-Maintenance, Mechanical Maintenance Supervisor, or Electrical Maintenance Supervisor, the Site Emergency /

Coordinator assumes the responsibilities of Emergency Repair Director.

3.3 DUTIES - The Emergency Repair Director is responsible for:

1. Directing the overall maintenance and equipment restora-tion effort.

2. Identifying and developing instructions and procedures for reducing the consequences of and recovering from an emergency.

3. Defining preferred and alternate ingress and egress routes in coordination with the Radiological Control Director.

4. Ensuring that equipment is maintained during an emergency.

5. Maintaining a record of his activities.

6. Ensuring that he is -relieved only by an individual trained for duty as. Emergency Repair Director.'.0 DEFINITIONS None Applicable 5.0 GENERAL During an emergency, unusual and expeditious actions to restore vital equipment to operability may be required. The Emergency Repair Director directs the implementation of necessary actions such that their impact on the subsequent full recovery of the plant is minimized.

6.0 INITIATING CONDITIONS The Site Emergency Coordinator has activated the site emergency organization, including the position of Emergency Repair Director.

7.Q PRECAUTIONS AND LIMITATIONS 7.1 Approval must be obtained from the Site Emergency Coordinator prior to deviating from any existing plant procedure or prior to performing an action for which no procedure exists, but which would normally require a procedure in accordance with MMM-002.

Site Emergency Coordinator is responsible for overall 7.2 The control of the plant. 'o action shall be taken'that could adversely affect the operability of a plant system without his concurrence.

PEP-202 Rev. 0 Page 5 of 7

APR012 8.0 SPECIAL TOOLS AND E UIPNENT None Applicable 9.0 PROCEDURE STEPS

1. If you are relieving another individual, review the activity log and obtain a briefing on the emergency and any actions that have been completed or are in progress.

2 ~ Conduct all communications in accordance with PEP-302 and PEP-303.

3. Report your arrival in the Technical Support Center to the Emergency Communicator-Technical Support Center (Emergency Communicator - Control Room if the Emergency Communicator-Technical Support Center position is not yet manned) and inform the Site Emergency Coordinator that you,are assuming (or relieving if appropriate) the position of Emergency Repair Director.

4. Initiate and maintain a record of your activities in accordance with PEP-405.

5. Ensure that the Operations Support Center Leader and Damage Control Team, Coordinator have implemented PEP-382, "Personnel, Accountability," and that the Operational Support Center Leader is setting'p the Operations .Support Center in accordance with PEP-323.

I

-6. Ensure that the Damage Control Team. Coordinator dispatches teams to investigate out of service or malfunctioning equipment which may be contributing to or could help mitigate the emergency.

7. When damage assessment reports are received, develop a

-course of corrective or preventive actions as follows:

In consultation with the Plant Operations Director and Radiological Control Director, determine whether or not any actions are actually necessary to place or maintain the plant in a safe shutdown condition, to prevent or reduce the'release of radioactive material, to prevent or reduce further damage to the plant, or to prevent personnel injuries and/or over exposure to radiation.

Evaluate available alternatives to determine which will have the least impact on eventual full recovery of the plant, including potential requirements for

'rework, testing, and certification.

Determine the feasibility of the considered action(s) based on availability of resources.

PEP-202 Rev. 0 Page 6 of 7

APR012 9.'0 PROCEDURE STEPS

8. Determine whether or not procedures and/or instructions are required in accordance with MMM-001. If required, existing plant procedures should be used to the maximum extent possible. Develop new procedures and/or changes to existing procedures as required in accordance with AP-006 and AP-007, respectively.

NOTE: In accordance with AP-002, the Site Emergency Coordinator may authorize reasonable action in an emergency that departs from license conditions, Technical Specifications, or the Plant Operating Manual when th'is action is immedi-ately needed to protect the public health and safety, and no action, consistent with license conditions, Technical Specifications, or the Plant Operating Manual is immedi-ately apparent that can provide adequate or equivalent protection.

9. Inform the Damage Control Team Coordinator or Operations Support Center Leader, as appropriate, of the instructions or procedures to be followed in accomplishing required actions, and direct him to implement them.

10. Request any needed material or supplies not on the plant site from the Logistics Support Director.

Report. to the- Site Emergency Coordinator the status of repair, damage assessment and restoration work being performed.

12. When directed to do so, contact the alternate specified by the Site Emergency Coordinator in accordance with Section 9.2 of PEP-321 to arrange for relief;,at the end of the present shift. Notification messages shall be given to the specified individual only, and not to the individual's spouse, children, babysitter, etc. If the specified alternate cannot be contacted, inform the Logistics Support Director.

13. When the emergency has been terminated, deliver your activity log and copies of all records generated during the emergency by the Operations Support Center Leader, Damage Control Team Coordinator and the Damage Control Teams to the Senior Specialist-Emergency Preparedness.

10.0 DIAGRAMS ATTACHMENTS None Applicable PEP-202 Rev. 0 Page 7 of 7

APR007 CAROLINA POWER &. LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-203 TITLE: LOGISTICS SUPPORT DIRECTOR REVISION 0 APPROVED:

S ature Date TITLE:

PEP-203 Rev. 0 Page 1 of 9

APRO07 Table of Contents

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 2.0 PURPOSE REFERENCES l 4 2.1 Emergency Plan References 4 2' Referenced Plant Emergency Procedures 4 2,3 Other References 4 3.0 RESPONSIBILITIES 4 3.1 Reporting Responsibilities 4 3' Assignment and Relief of Position 5 3.3 Duties 5

. 4' DEFINITIONS 6 5.0 GENERAL 6 6.0 INITIATING CONDITIONS 6 7.0 PRECAUTIONS AND LIMITATIONS 6 8.0 SPECIAL TOOLS AND EQUIPHENT 6 9.0 PROCEDURE STEPS 6 10.0 DIAGRAHS/ATI'ACHMENTS 9 PEP-203 Rev. 0 Page 2 of 9

APR007 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 through 9 0 PEP-203 Rev. 0 Page 3 of 9

APR007 1.0 PURPOSE This procedure implements Section 2.4.5, "Logistics Support Direc-tor," of the SHNPP Emergency Plan. It specifies actions to be taken by the Logistics Support Director.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES Section 2.4.5, "Logistics Support Director"

2. Section 4.2, "Notification"

3. Section 4.3, "Activation"

4. Section 4.6, "Protective Actions for On-Site Personnel"

2. 2 REFERENCED PLANT EMERGENCY PROCEDURES PEP-210, "Emergency Security Team Leader"

2. PEP-215, "Assembly Area Leader" 3 ~ PEP-302, "Communication Activities" PEP-303, "Use of Communications Equipment"

5. PEP-321, "Notification of Emergency Personnel"

6. PEP-322, "Mobilization of Outside Organizations"

7. PEP-323, "Setup and Operation of Emergency Facilities"

8. PEP-382, "Personnel Accountability"

9. PEP-384, "Access Control

10. "Search and Rescue"

'EP-394, PEP-405, "Preparation of Activity Logs" 2' OTHER REFERENCES SP"016, "Emergency Plan Support",

3.0 RESPONSIBILITIES 3.1. REPORTING RESPONSIBILITIES 3.1.1.The Logistics Support Director reports to the Site Emergency Coordinator.

PEP-203 Rev. 0 Page 4 of 9

APR007 3.0 RESPONSIBILITIES 3.1. REPORTING RESPONSIBILITIES (Cont'd) 3.1.2.The Site Communications Systems Coordinator, Support Services Coordinator, Emergency Security Team Leader, and Assembly Area Leaders report to the Logistics Support Director.

3.2 ASSIGNMENT AND RELIEF OF POSITION 3.2.1.Upon arrival in the Technical Support Center the Assistant to the Plant General Manager, Administrative Supervisor, or Office Services Supervisor assumes the responsibilities of Logistics Support Director.

3.2.2.When the Emergency Operations Facility is activated, the Administrative and Logistics Manager relieves the Logistics Support Director of the responsibility for contacting offsite agencies to,request assistance.

3.3 DUTIES The Logistics Support Director is responsible for:

3.1. Ensuring that the Technical Support Center and Emergency Operations Facility are set up and made operational if ac-tivation has been directed.

3.2. Directing the implementation of administrative functions during an emergency.

3.3. Assisting the Site Emergency Coordinator in arranging for shift reliefs and continuous manning of the plant emergency staff.

3.4. Arranging for food and sleeping facilities for on-site emergen-cy workers.

3.5. Coordinating requests for material, equipment, and supplies from members of the on-site emergency organization.

d 3.6. Arranging for additional services and providing new and/or modified contracts for services to be procured.

3.7. Ensuring that communications equipment is used to support the emergency, and that all non-emergency communications are terminated.

3.8. When the Emergency Operations Facility is activated, coordinat-ing plant logistical requests through the Administrative and Logistics Manager.

3.9. Ensuring that potentially contaminated on-site foodstuffs are not consumed.

PEP-203 Rev. 0 Page 5 of 9

APR007 3.0 RESPONSIBILITIES 3.3 Duties (Cont'd)

3. 10. Ensuring that he is relieved only by an alternate trained for duty as Logistics Suppoxt Director.

3. 11. Maintaining a record of his activities.

4.0 DEFINITIONS None Applicable 5.0 GENERAL The Logistics Support-Director provides personnel and material resource augmentation as necessary and as authorized by the Site Emergency Coordinator.

6.0 INITIATING CONDITIONS The Site Emergency Coordinator has activated the site emergency organization, including the position of Logis'ties Support Director.

7.0 PRECAUTIONS AND LIMITATIONS None Applicable 8.0 SPECIAL TOOLS AND E UIPMENT Institute for Nuclear Power Operations Emergency Response Manager's Resource. Manual.

9.0 PROCEDURE STEPS 9.1. If you are relieving another individual, review the activity log and obtain a briefing on the emergency and any actions that have been completed or are in progress.

9.2. Conduct all communications in accordance with PEP-302 and PEP-303.

9.3. Report your arrival in the Technical Support Center to the Emergency Communicator"Technical Support Center(or the Emerg" ency Communicator-Control Room if the Emergency Communica-tor-Technical Support Center position is not yet manned), and inform the Site Emergency Coordinator that, you are assuming (or relieving if appropriate) the position of Logistics Support Director.

9.4. Initiate and maintain a record of your activities in accordance with PEP-405.

PEP"203 Rev. 0 Page 6 of 9

APRO07 9.0 PROCEDURE STEPS 9.5, Verify that your staff positions have been manned.

9.6. Ensure that the Technical Support Center is set up in accor-dance with PEP-323.

9.7. Verify that the Emergency Security Team Leader is taking appro-priate action according to the SHNPP Industrial Security Plan, Safeguards Contingency Plan and security procedures.

9.8. Verify that the Emergency Security Team leader is implementing PEP-384 Access Control, SP-016, "Emergency Plan Support" and PEP-210, "Emergency Security Team Leader."

9.9. Verify tEat the Assembly Area Leader is implementing PEP-215, "Assembly Area Leader".

9.10.If activation of the Emergency Operations Facility has been directed, ensure that it is set up in accordance with PEP-323 and that the Emergency Security Team Leader provides access control in accordance with PEP-384.

9.11.Within 30 minutes after the emergency is declared, obtain a list of any unaccounted for personnel from the Emergency Security Team Leader as per PEP-382 and 384. Report the name(s) and suspected location(s) of missing personnel to the Site Emergency Coordinator and Plant Operations Director, who will direct the implementation of search and rescue efforts in accordance with PEP-394.

'Note: The 30 minute requirement to accomplish personnel accountability is satisfied when the Logistics Support Director is notified of the names of missing persons.

9.12.If necessary to man all emergency positions, direct the Assem-bly Area Leader(s) to dispatch available personnel to the appropriate emergency facilities.

9.13.When directed to do so, notify the alternate for your position specified by the Site Emergency Coordinator to arrange for relief at the end of the present shift in accordance with Section 9.2 of PEP-321. Notification messages shall be give only to the specified individual, and not to their spouse, children, babysitter, etc. If the designated alternate cannot be contacted, inform the Site Emergency Coordinator.

Coordinate the preparation of shift schedules for all other onsite emergency personnel.

9.14.If an evacuation is to be performed, notify the Emergency Security, Team Leader and Assembly Area Leaders, inform them where the Personnel Protection and Decontamination Teams will be setting up monitoring and decontamination areas (if this is PEP-203 Rev. 0 Page 7 of 9

APR007 9.0 PROCEDURE STEPS to be done), and instruct them to direct people to the approp-riate areas and control personnel there.

9.15.If additional pers'onnel resources are needed to support the on"site response, request assistance from outside agencies in accordance with PEP-322. Refer to the Institute for Nuclear Power Operations Emergency Response Manager's Resource Manual for general guidance on" resources available from other util-ities.

9.16.lf an atmospheric release has occurred, direct the Support Services Coordinator and Assembly Area Leaders to isolate potentially contaminated foodstuffs by disabling vending machines and prohibiting access to refrigerators until it can be verified that the food is not contaminated or is discarded.

9.17.Direct the Support Services coordinator to arrange for a supply of uncontaminated food and, if required, sleeping facilities for on-site emergency workers.

9.18.Ensure that the site Communications System Coordinator is responding to communications equipment problems, if any. If necessary to ensure that communications equipment is being properly used to support the emergency, direct him to dispatch personnel to the Administration Building telephone equipment room to modify software and/or hardware as required. Consult with the Radiological Control Director to determine personnel protection requirements prior to directing the dispatch of personnel. \

9.19.When the need for materials or supplies are identified, direct the Support Services Coordinator to identify whether or not they are available on site and to procure materials or supplies as required. Ensuring that the Support Services Coordinator has stores personnel available to issue parts and supplies from the Service Building Storeroom, Warehouse, and/or Receiving Building. Consult with the Radiological Control Director to determine personnel protection requirements prior to directing the Support Services Coordinator to dispatch personnel to those locations.

9.20.Keep the Site Emergency Coordinator informed of any non-routine security procedures and/or contingency conditions that are in effect or that require a response and of any activities being conducted by local law enforcement agencies in support of the emergency response'.

PEP-203 Rev. 0 Page 8 of 9

APR007 9.0 PROCEDURE STEPS 9.21.Ensure that the Emergency Security Team Leader is kept informed of radiological conditions and personnel protection require-ments in all site areas.

9.22.When the emergency is terminated, deliver your activity log and copies of all records generated during the emergency by the Site Communications System Coordinator, Support Services Coordinator, Emergency Security Team Leader, and Assembly Area Leaders to the Senior Specialist - Emergency Preparedness.

10.0 DIAGRAMS/ATTACHMENTS None Applicable PEP-203 Rev. 0 Page 9 of 9

APR015 CAROLINA POWER 6 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: - PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-204 TITLE: RADIOLOGICAL CONTROL DIRECTOR REVISION 0 APPROVED:

Signature PEP-204 Rev. 0 Page 1 of 13

APR015 TABLE OF CONTENTS

~Pa e 2'

Table of Contents List of Effective Pages 1.0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4 3.0 RESPONSIBILITIES 5 3.1 Reporting Responsibilities 5 3.2 Assignment and Relief of Position 5 3.3 Duties 5 4.0 DEFINITIONS 7 5.0 GENERAL 7 6.0 INITIATING CONDITIONS 7 7.0 PRECAUTIONS AND LIMITATIONS 7 8.0 SPECIAL TOOLS AND EQUIPMENT 7 9.0 PROCEDURE STEPS 7 9.1 Initial Actions 7 9.2 Personnel Protection 8 9.3 Plant Monitoring 10 9.4 Dose Projection 11 9.5 Emergency Environmental Monit'oiing 12 9.6 General 13

10. 0 DIAGRAMS/ATI'ACHMENTS 13 PEP-204 Rev. 0 Page 2 of 13

APR015 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 thxough 13 0 PEP"204 Rev. 0 Page 3 of 13

APR015 1.0 PURPOSE The purpose of this procedure is to implement Section 2.4.6, "Radiological Control Director" of the SHNPP Emergency Plan.

This procedure describes the actions of the Radiological Control Director during an emergency.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 2.4.6, "Radiological Control Director" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-101, "Emergency Classification"

2. PEP-103', "Site Emergency Coordinator - Technical Support Center"

3. PEP-I04, "Protective Action Recommendations"

4. PEP-206, "Environmental Monitoring Team Leader"

5. PEP-207, "Plant Monitoring Team Leader"

6. PEP-208, "Personnel Protection and Decontamination Team Leader"

7. PEP-216, "Dose Projection Team Leader" 8, PEP-301, "Notification and Communications"

9. PEP-302, "Communication Activities"

10. PEP-303, "Use of Communications Equipment" ll; PEP-321, "Notification of Emergency Personnel"

12. PEP-323, "Setup and Operation of Emergency Facilities"

13. PEP-331, "Emergency Plant Monitoring"

14. PEP-341, "Manual Dose Projection"

15. PEP-342, "Automation of Dose Projection - ERFIS"

16. PEP-343, "Automation of Dose Projection - EBM-PC" PEP-204 Rev. 0 Page 4 of 13

APR015

2.0 REFERENCES

2.2 REFERENCED PLANT EMERGENCY PROCEDURES (Cont'd)

17. PEP-351, "Emergency Environmental Monitoring"

18. PEP-371, "Emergency Response in Radiological Areas"

19. PEP-382, "Personnel Accountability"

20. PEP-383, "Administration of Potassium Iodide"

21. PEP-391, "First Aid and Medical Care"

22. PEP-394, "Search and Rescue"

23. PEP-401, "Record Keeping and Documentation"

24. PEP-405, "Activity Logs" 3.0 RESPONSIBILITIES 3.1 REPORTING RESPONSIBILITIES

1. The Radiological Control Director reports to the Site Emergency Coordinator in the Technical Support Center upon activation of the Technical Support Center.

2. The Dose Projection Team Leader, the Environmental Moni-toring Team Leader, the Personnel Protection and Decon-tamination Team Leader, and the Plant Monitoring Team Leader report to the Radiological Control Director.

.. 3.2 ASSIGNMENT AND RELIEF OF POSITION The primary person assigned to the position of Radiological Control Director is the Manager - Environ-mental and Radiation Contxol. If he is not available, the designated alternates in order of succession are:

1. Supervisor - Radiation Control

2. Supervisor - Environmental and Chemistry

3. Project Specialist - Radiation Control 3.3 DUTIES The Radiological Control Director performs the following duties:

t

1. Maintains a record of his activities.

PEP-204 Rev. 0 Page 5 of 13

APR015 3.0 RESPONSIBILITIES 3.3 DUTIES (Cont'd)

2. Provides technical and administrative direction to the Plant Monitoring Team, Personnel Protection and Decon-tamination Team, Environmental Monitoring Team, and Dose Projection Team .

3. Coordinates initial off-site environmental monitoring and dose assessment efforts until such activities can be directed by the Emergency Operations Facility.

4, Directs the Dose Projection Team and Plant Monitoring Team to accumulate, tabulate, and evaluate data on plant conditions such as meteorological and radiation monitor-ing readings, hazardous material surveys, and. other pertinent, data.

5. Ensures use of protective clothing, respiratory pro-tection, and access control within the plant as deemed appropriate to control personnel exposures.

6. Ensures that appropriate bioassay procedures have been implemented for on-site personnel when a radioactivity incident has occurred..

7. Ensures that personnel are decontaminated, if necessary.

8. Assists in the transfer of contaminated injured personnel and nonessential personnel.

9. Determines appropriate on-site personnel evacuation routes and alternate assembly areas when deemed necessary.

10. Coordinates and compares dose-assessment and monitoring results with the State (Department of Human Resources State Emergency Response Team) until the Emergency Op-erations Facility is activated.

Assists the counties by providing Thermoluminescent Dosimeters and providing a representative to assist in reading and analyzing dosage, when requested.

12. Assures planned exposures in excess of 3Rem or entry into radiation fields greater than 100R/hr are approved by the Plant General Manager, Manager - Environmental and Ra-diation Control or the Site Emergency Coordinator, in that order.

PEP-204 Rev. 0 Page 6 of 13

APR015 3.0 RESPONSIBILITIES 3.3 DUTIES (Cont'd)

13. Ensures that he is relieved only by an alternate trained for duty as Radiological Control Director.

4.0 DEFINITIONS None Applicable 5.0 GENERAL None Applicable 6.0 INITIATING CONDITIONS

1. An emergency has been declared and the Site Emergency Coordinator has activated the emergency organization including the Radiological Control Director position.

7.0 PRECAUTIONS AND LIMITATIONS None Applicable 8.0 SPECIAL TOOLS AND E UIPMENT None Applicable 9.0 PROCEDURE STEPS I

9.1 INITIAL ACTIONS

1. If you are relieving another individual, review the activity log and obtain a briefing from your predecessor on the emergency and any actions that have been completed or are in progress; otherwise, obtain a briefing from the Site Emergency Coordinator.

2. Conduct all communications in accordance with PEP-302 and PEP-303.

3. Report your arrival in the Technical Support Center to the Emergency Communicator - Technical Support Center (or to the Emergency Communicator - Co'atrol Room if the former position is not yet manned) and inform the Site Emergency Coordinator that you are assuming (or relieving, if appropriate) the position of Radiological Control Direc-tor.

4. Initiate and maintain a record of your activities in accordance with PEP-405.

PEP-204 Rev. 0 Page 7 of 13

APR015 9.0 PROCEDURE STEPS 9.1 INITIAL ACTIONS (Cont'd)

5. Verify that, the Plant Monitoring Team Leader, Personnel Protection and Decontamination Team Leader, Environmental Monitoring Team Leader, and Dose Projection Team Leadex are present, their teams are adequately staffed, have been accounted for according to PEP-382, and are standing by.

6. Verify that the radiological areas (Radiological Control Director position, Dose Projection Room, Environmental Monitoring Room, and Plant Monitoring Team Room) are set up per PEP-323.

7 0 Notify the Site Emergency Coordinator - Technical Support Center that you and your staff are present and ready to support him.

When directed to do so, notify the alternate for your position specified by the Site Emergency Coordinator to arrange for relief in accordance with Section 9.2 of PEP-321. Notification messages shall be given only to the specified individual, and not to their spouse, children, babysitter, etc. If the specified alternate cannot be contacted, inform the Logistics Support Director.

9.2 PERSONNEL PROTECTION Check with the Personnel Protection and Decontamination Team Leader that he has assigned personnel to perform habitability surveys in the Assembly Areas, Security Building, and Operational Support Center.

2. Based upon the type of emergency and the radiological conditions in the Radiologically Controlled Area or other area (as determined by readings from Area Radiation Monitors, Airborne Radiation Monitozs and Surveys, or known or suspected releases) advise the Site Emergency Coordinator and Emergency Security Team Leader whether to temporarily withdraw security personnel from a particular area.

After the Pexsonnel Protection Team Leader has evaluated the habitability surveys and made recommendations regard-ing any protective equipment requirements, evaluate his recommendations and concur or set alternate requirements.

Based upon the habitability surveys obtained from the Personnel Protection and Decontamination Team Leader, the meteorological conditions and dose projections obtained from Dose Projection Team Leader and the plant conditions PEP-204 Rev. 0 Page 8 of 13

APR015 9.0 PROCEDURE STEPS 9.2 PERSONNEL PROTECTION (Cont'd) obtained from the Plant Operations Director, recommend to the Site Emergency Coordinator whether to shelter on-site personnel in the assembly areas or to evacuate them. Also advise evacuation routes to be used, locations for moni-toring and decontamination areas, if needed, and/or assembly areas to be used.

5. Based upon the Site Emergency Coordinator's decision regarding the protective action'ecommendations in Step 4, provide the appropriate directions to the Personnel Protection and Decontamination Team Leader.

NOTE: If it is determined that cars will have to be decontam-inated with fire hoses, request the Plant Operations Director to supply Fire Brigade personnel to man the hoses.

6. If personnel are missing in the Radiologically Controlled Area, verify that the Personnel Protection and Decon-tamination Team Leader has assigned an individual to accompany the search and rescue team as per PEP-394.

7. If the Plant Operations Director or the Personnel Pro-tection and Decontamination Team Leader notifies you that a contaminated injured patient is to be sent to the hospital, verify that the hospital has been notified prior to transporting the patient and that a Personnel Pro-tection and Decontamination Team Member accompanies the injured to the hospital and/or is waiting at the hospital.

NOTE: If the injured's condition allows him to be decontaminated prior to transport or allows his treatment on-site by one of the agreement physicians, this should be done since transporting a contaminated injured person to an off-site medical facility constitutes an Unusual Event and must be reported to the NRC.

8. Verify with the Personnel Protection and Decontamination Team Leader that any contaminated personnel are being decontaminated.

9. If a radioactivity incident, has occurred where personnel on-site have or are likely to have internal contamination verify that appropriate bioassay procedures have been or will be implemented for the affected personnel.

PEP-204 Rev. 0 Page 9 of 13

APR015 9.0 PROCEDURE STEPS 9.2 PERSONNEL PROTECTlON (Cont'd)

10. Ensure that Radiation Vork Permits and Exposure Control are being properly implemented according to PEP-371, that appropriate emergency personnel monitoring and dosimetry issuance is being conducted, and that appropriate protec-tive equipment is being specified.

11. If personnel in the emergency organization are likely to receive a significant dose (25 rem) to the thyroid from radioiodine, and alternative protective actions are not feasible or would be ineffective, contact the agreement physician to obtain approval, obtain authorization from the Site Emergency Coordinator, and direct the Personnel Protection and Decontamination Team Leader to administer the potassium iodide as per PEP-383.

12. If personnel will incur planned exposures in excess of 3 rem or will enter into radiation fields greater than 100R/hr, ensure approval is obtained from the Plant General Manager, Manager - Environmental and Radiation Control or the Site Emergency Coordinator, in that order.

13. When requested by the Counties provide thermoluminescent dosimeters to emergency response personnel and arrange to have the dosimeters evaluated when they are returned.

9.3 PLANT MONITORING

1. Assist the Plant Monitoring Team Leader in selecting the proper monitoring and sample collection points, selecting the data required and assessing the radiological con-ditions at these sample points. (See PEP-207 and 331)

2. If the radiation and airborne activity levels for the Post Accident Sample System panel area, other sample areas and the access routes to these areas are not reasonably known, direct the Personnel Protection and Decontamination Team Leader to have a survey performed or send an individual with the plant monitoring team.

3. Verify that the Plant Monitoring Team Leader is continu-ously monitoring the plant Radiation Monitoring System data with the Emergency Response Facility Information System. Instruct him to notify his team, the Personnel Protection and Decontamination Team Leader, and you if any significant or unusual changes occur and maintain a record of these changes.

PEP-204 Rev. 0 Page 10 of 13

APRO}5 9.0 PROCEDURE STEPS 9.3 PLANT MONITORING (Cont'd)

4. Review the'lant monitoring data that is obtained and verify that appropriate data is being transmitted to the Dose Projection Team Leader and Accident Assessment Team Leader.

5. Direct that additional sampling be conducted to determine souxce terms, with the frequency based upon the need for calculation dose projections, performing accident assess'-

ment evaluations,and changing plant conditions which may effect personnel exposure.

9.4 DOSE PROJECTION NOTE: Off-site dose projections will be performed in the Emer-gency Operations Facility after it is fully activated and staffed. Dose projections may continue in the Technical Support Center to provide information on off-site con-ditions and input to the Emergency Action Levels.

Verify the Dose Projection Team Leader is performing dose projections via the best method currently available. (See PEP-341, 342, 343, and 216)

2. If informed by the Dose Projection Team Leader that Radiation Monitoring System data being used is suspect, direct that substitute values be entered in the Emergency Response Facility Information System data base.

3.: Evaluate the results and confer with the Dose Projection Team Leader on recommendations for environmental monitor.-

ing (to confirm the dose projections) and on recommenda-tions for protective actions. (See PEP-104)

4. If the projected dose 'is gxeater than 1 rem whole body or 5 rem thyroid at the site boundary (2500 feet) have the doses calculated at the Exclusion Area Boundary (1.3 miles) and beyond.

5.. Confer with the Site Emergency Coordinator and provide the dose projection results and a protective action recommen-dation. to him (as per PEP"104) to be transmitted to the counties, State, and NRC using the notification form in PEP-301.

NOTE: The initial notification must be performed within 15 minutes of the declaration of the emergency.

PEP-204 Rev. 0 Page 11 of 13

APR015 9.0 PROCEDURE STEPS 9.4 DOSE PROJECTION (Cont'd)

6. Verify the plume is being plotted and kept current on the map board in the Technical Support Center.

7. Determine how often the calculation should be repeated and instruct the Dose Projection Team Leader. (Once per hour or upon any significant change in release rate or meteorological conditions.)

8. Vhen the Emergency Operations Facility is manned, have the Dose Projection Team Leader brief the Dose Assessment Team Leader, brief the Radiological Control Manager, and notify the Site Emergency Coordinator that the dose projections function is being transferred to the Emergency Operations Facility Staff.

Notify the Site Emergency Coordinator of projected on-site doses and off-site doses, and how the results calculated at the Technical Support Center and at the Emergency Operations Facility (when available) compare.

9.5 EMERGENCY ENVIRONMENTAL MONITORING NOTE: Environmental monitoring will be controlled by the Emer-gency Operations Facility after it is fully activated and staffed. The Environmental Monitoring Team Leader in the Technical Support Center will remain to provide informa-tion and liaison to the Emergency Operations Faci,lity's environmental monitoring effoxts.

Verify the Environmental Monitoring Team Leader has consulted with the Dose Projections Team Leader and the Personnel Protection and Decontamination Team Leader to determine what sectors should be monitored initially and what personnel protection equipment should be used by the Environmental Monitoring Teams. (See PEP-206 and 351)

2. Veri.fy the Dose Projection Team Leader and Environmental Monitoring Team Leader are comparing the calculated values to the actual readings.

3. Confer with the Dose Projection Team'Leadex and Environ-mental Monitoring Team Leader and set priorities for obtaining more data.

4. Provide instructions as to which laboratory to deliver iodine collection cartridges and have the Environmental Monitoring Team Leader inform his teams.

PEP-204 Rev. 0 Page 12 of 13

APR015 9.0 PROCEDURE STEPS 9.5 EMERGENCY ENVIRONMENTAL MONITORING (Cont'd)

5. Based upon'the monitoring results have the Dose Projection Team Leader perform additional dose projections and notify the Site Emergency Coordinator of the results.

6. Coordinate and compare the initial dose assessment and environmental monitoring efforts with the State (Depart-ment of Human Resources - State Emergency Response Team) until the Emergency Operations Facility is activated.

7. Vhen requested by responsible State officials, arrange for an analyses of environmental samples by the Harris Energy and Environmental Center (or other laboratory).

8. When the Emergency Operations Facility is manned have the Environmental Monitoring Team Leader brief the Environ-mental Monitoring Supervisor who will then take control of the Environmental Monitoring Teams.

9.6 GENERAL Directors'.

1. Request any needed material or supplies not on the plant site from the Logistics Support Periodically report to the Site Emergency Coordinator the radiological status on-site and off-site and any protec-tive action recommendations.

3.'hen the emergency has been terminated, deliver your activity log and copies of all records generated by yourself and your subordinates during the emergency to the Senior Specialist>>Emergency Preparedness as per PEP-401.

10.0 DIAGRAMS ATTACHMENTS None Applicable PEP-204 Rev. 0 Page 13 of 13

APR015 CAROLINA,POWERS,:,.LIGHT'.COMPANY SHEARON HARRIS NUCLEAR POWER PLAifT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-205 TITLE: REPRESENTATIVE TO THE STATE EMERGENCY RESPONSE 7EQi REVISION 0

/

APPROVED:

Signature TITLE: u~r PEP-205 Rev. 0 Page 1 of 8

A?RO15 TABLE OF COKKNTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4 3.0 RESPONSIBILITIES

3. 1 Reporting Responsibilities 4 3.2 Assignment and Relief of Position 4.

3.3 Duties 4.

4.0 DEFINITIONS 5 5' GENERAL 5 6.0 INITIATING CONDITIONS 5 7.0 . PRECAUTIONS AND LIMITATIONS 5 8.0 SPECIAL TOOLS AND EQUIPMENT 6 9.0 PROCEDURE STEPS 6 10.0 DIAGRAMS/ATTACHMENTS 7

1. North Carolina Emergency Operations Center Space Assignments PEP-205 R'ev. 0 Page 2 of 8

APR015 I;IST- OF EFFECTIVE; PAGES

~Pa e Revision through 8 0 1

PEP-205 Rev. 0 Page 3 of 8

APR015 1.0 PURPOSE This procedure implements Section 2.4.9, "Representative 'to the State Emergency Response Team," of2. the SHNPP Emergency Plan. It specifies actions to be taken by the Representative to the State Emergency Response Team.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 2.4.9, "Representative to the State Emergency Response Team" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES 1 PEP 101~ iiEmergency Classification

2. PEP-104, "Protective Action Recommendations"

3. PEP-351, "Emergency Environmental Monitoring" 3.0 RESPONSIBILITIES 3.1 REPORTING RESPONSIBILITIES

1. The Representative to the State Emergency Response Team reports to the Site Emergency Coordinator until the Emergency Operations Facility is activated, after which time he reports to the Emergency Response Manager.

3.2 ASSIGNMENT AND RELIEF OF POSITION

1. The Manager - Technical Support is assigned to the posi-tion of Representative to the State Emergency Response Team ~

2. If the Manager - Technical Support is not available, the position is filled by one of the designated alternates who are the Manager - Start-Up and the Senior Specialist-Emergency Preparedness.

3.3 DUTIES The Representative to the State Emergency Response Team (SERT),

located at the State Emergency Response Team Headquarters in Raleigh, shall:

1. Maintain a record of his activities.

2. Report to the State Emergency Response Team Headquar'ters after a briefing by the Site Emergency Coordinator.

PEP-205 Rev. 0 Page 4 of 8

APR015 3..0, RESPONSIBILITIES 3.3 DUTIES (Cont'd)

3. Inform government agency repxesentatives of plant cond-itions and provide technical guidance on xecommendations of the Emergency Response Manager for protective actions for the t public.

Confirm that copies of emergency procedures for environ-mental monitoring and analysis are available for in-spection and review in the State Emergency Response Team Headquarters.

5. When requested, coordinate axrangements for analysis of replicate samples.

6. Ensure that he is relieved only by a alternate train'ed for duty as Representative to the State Emergency Response Teamt 4;0 DEFINITIONS None Applicable.

5 t0 GENERAL The Representative to the St~e Emergency Response Team Headquarters acts as Carolina Power and Light Company's technical liaison for the North Carolina Emergency Response Teem. He interprets emergency action levels and protective action recommendations made by the Emergency Response Manager and informs the Emergency Response Manager of actions taken by the State Emergency Response Team.

The Representative to the State Emergency Response Team position is activated when the Emergency Opexations Facility is activated, and staxts with a briefing by the Site Emergency Coordinator in the Technical Support Center. After the briefing, the Representative to the State Emergency Response Team. travels to the State Emergency Response Team Headquarters, located in the State Administrative Building basement, 116 West Jones Street, Raleigh.

6. 0 INITIATING CONDITIONS

1. The Emergency Operations Facility has been activated, which activates this position.

7.0 PRECAUTIONS AND LIMITATIONS

1. The Representative to the State Emergency Response Team is a communications liaison for the company and can not commit company resources or make decisions in the absence of, or in lieu of, the Emergency Response Manager.

PEP-205 Rev. 0 Page 5 of 8

APR015 8.0 SPECIAL TOOLS AND E UIPMENT

1. Personal or company vehicle.

~

9.0 PROCEDURE STEPS 9.1 Upon arriving on site report to the Technical Support Center and inform the Emergency Communicator that you have arrived.

9.2 Participate in the briefing provided to the Emer'gency Response Manager by the Site Emergency Coordinator.

9.3 Obtain extra copies from the Technical Support Center library of the following Plant Emergency Procedures to take to the State Emergency Response Team Headquarters.

l. PEP-101, "Emergency Classification" 2~ PEP-104, "Protective Action Recommendations"

3. PEP-351, "Emergency Environmental Monitoring" Activity Log Sheet(Attactment 1 to PEP-405, "Prepara-tion of Activity Logs" )

9.4 Proceed to the State Emergency Response Team Headquarters, located in the basement of the North Carolina Adminis-tration Building, 116 Vest Jones Street, Raleigh: A diagram is shown in Attachment 1.

9.5 Report to the State. Emergency Response'Team Manager, in the Operations Room, Room B-24. Sign the access roster.

9.6 Initiate an activity log in accordance with PEP-405.

9.7 Verify that the following,emergency communications links from the State Emergency Response Team Headquarters to the Technical Support Center and the Emergency Operations Facility are operational:

1. Automatic ring down telephone from the State Emerg-ency Response Team Manager (Room B-9) to the Emerg-ency Operations Facility.

2. Automatic ring down telephone from the State Emerg-ency Response. Team Radiological Control Room B-26 to the Emergency Operations Facility.

3. Off premises extension84148 on the Emergency Opera-tions Facility telephone system in room (later).

4. VHF radio communications to the Emergency Operations Facility and Technical Support Center.

PEP-205 Rev. 0 Page 6 of 8

APR015 9.0 PROCEDURE,,STEPS 9.8 Contact the System Communications Systems Coordinator in the Emergency Operations Facility if any communications problems with the site arise.

9,9 Assist the State Emergency Response Team Headquarters in interpretation of plant emergency action levels, protec-tive action recommendations and environmental monitoring results 9.10 Determine any needs for additional equipment, supplies, and manpower, (especially technical and health physics expertise)and request them from the Adminstrative and Logistics Manager in the Emergency Operations Facility.

l 9.11 tIthen directed to do so, notify the alternate for your position specified by the Emergency Response Manager to arrange for relief, at the end of the present shift.

Notification messages shall be given only to the specified individual, and not to their spouse, children, babysitter, etc. If the specified alternate cannot be contacted, inform the Administrative and Logistics Manager.

9.12 Inform the Emergency Response Manager of any key decisions m'ade or protective action decisions made, and update the Emergency Response Qanager on the status of evacuation and reception centers. Ensure that the Emergency Operations Facility Status Board. Plotter receives the same informa-tion.

9.13 When relinquishing this position, brief your successor on the emergency and emergencyr actions status.

9.14 If requested, coordinate arrangements for replicate analyses of environmental samples collected by GPSS'ersonnel.

10. DIAGRAMS AT1'ACHMENTS

1. Attachment 1 - "North Carolina Emergency Operations Center r

Space Assignments" ~

PEP-205 Rev. 0 Page 7 of 8

szao15 Attachment 1 NC rOC SPACI'. ASSIGtltfEHTS BASIC PI.AH

{AUG 1983)

Sec. DOT State DCCPS DCCPS ,NRCD HRCD SHP Telephone Fed.-H>vy Equinment 0-13 0-14 0-16 0-17 8-18 State EBS Telephone 0-22 l DEtl DOT ADHIN Governor 0-9 ItlSURAt~CE 0-15 8-19 8-23 Gov. lllillll PIO Staff Gov. DF.N PU0. ED.

Staff 0-7 .

8-5 8-6 CORRECTInH 0-25 37 'Pl ( t'UISt<

RESOURCES 8-26 COMMUNICATION

'%I P IO/PR OPERATIONS IIUMAtl NTE NANCE RESOURCES 8-36 8-35 8-27 SEC. OF STATE 8-24 lIUHAN Com~n. OFFICE UD ITOR 0 33 RESOURCES AHD REVENUE 8-28 tlESSAGE R CENTER 0-36 USDA COtltIUf<I CATION H.C.

CULTURAL EQUIPMENT MILITARY CAP cotlt~rRcr. AGRIcULTURE RCSOURCES ARC HCHG LnonR SALVATION AR 4(

0-32 9-31 8-30 8-29 PEP;205 Rev. 0 Pacre 8 of 8

APR002 CAROLINA POWER 6 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP}

NUMBER: PEP"206 t

TITLE: ENVIRONMENTAL MONITORING TEAM LEADER REVISION 0 APPROVED:

S ignatuxe Da e TITLE:

PEP-206 Rev. 0 Page 1 of 9

APR002 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 4.

2.2 Referenced Plant Emergency Procedures 4 3.0 RESPONSIBILITIES 4 3.1 Reporting Responsibilities 3.2 Assignment and Relief of Position 4 3.3 Duties 5 4.0 DEFINITIONS 5 5.0 GENERAL 6 6.0 INITIATING CONDITIONS 6 7.0 PRECAUTIONS/LIMITATIONS 6 8.0 SPECIAL TOOLS AND EQUIPMENT 6 9.0 PROCEDURE STEPS 6 10.0 DIAGRAMS/ATTACHMENTS 8 PEP-206 Rev. 0 Page 2 of 9

APR002 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 through 9 0 PEP-206 Rev. 0 Page 3 of 9

APR002 1.0 PURPOSE This procedure implements Section 2 '.6.3, "Environmental Monitoring Team Leader," of the SHNPP Emergency Plan. It specifies actions to be taken by the Environmental Monitoring Team Leader.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 2.4.6.3, "Environmental Monitoring Team Leader

2. Section 4.4.4, "Environmental Monitoring" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-302, "Communications Activities"

2. PEP-303,. "Use of Communications Equipment"

3. PEP-321, "Notification of Emergency Personnel"

4. PEP-351, "Emergency Plant Environmental Monitoring"

5. PEP-382, "Personnel Accountability"

6. PEP-405, "Preparation of Activity Logs" 3.0 RESPONSIBILITIES 3.1 REPORTING RESPONSIBILITIES

1. The Environmental Monitoring Team Leader reports to the Radiological Control Director.

2. The Environmental Monitoring Teams report to the Environmental Monitoring Team Leader until the Emergency Operations Facility is activated, after which time they report to the Environmental Supervisor.

3.2 ASSIGNMENT AND RELIEF OF POSITION

1. The Supervisor - Environmental and Chemistry assumes the responsibilities of Environmental Monitoring Team Leader upon arrival at the Technical Support Center.

2. After activation of the Emergency Operations Facility, the Environmental Supervisor will relieve the Environmental Monitoring Team Leader of responsibilities related to control and .coordination of environmental monitoring.

PEP-206 Rev. 0 Page 4 of 9

APR002 3.0 REPONSIBILITIES 3.3 DUTIES 3.3.1. Until relieved by the Environmental Supervisor, the Environmental Monitoring Team Leader is responsible for:

1. Maintaining a record of all Environmental Monitoring Team Activities.

2. Directing the activities of the Environmental Monitoring Teams, positioning them such that representative samples and surveys of the plume, if any, can be made.

3. Consulting with the Personnel Protection and Decontamination Team Leader to determine protective requirements for the Environmental Monitoring Teams, and advising .the teams of those requirements.

4. Collecting and evaluating Environmental Monitoring Team sample and survey data.

5. Assisting in the orderly transfer of the environmental monitoring function to the Emergency Operations Facility.

6. Coordinating the use of the mobile laboratory.

7. Maintaining a list of personnel assigned to the Environmental Monitoring Teams and of team locations.

3.3.2. Both before and after being relieved by the Environmental Supervisor, the Environmental Monitoring Team Leader is responsible for:

1. providing the results of environmental samples and surveys to the Radiological Control Director and the Dose Projection Team Leader.

2. Maintaining a record of his activities.

3. Ensuring that he is relieved only by an alternate trained for duty, as Envizonmental Monitoring Team Leader.

4:0 DEFINITIONS None Applicable PEP-206 Rev. 0 Page 5 of 9

APR002 5.0 ~ GENERAL The Environmental Monitoring Team Leader will direct those activities necessary to verify whether or not an atmospheric release has occurred, and to determine its order of magnitude.

6.0 INITIATING CONDITIONS The Site Emergency Coordinator has declared an emergency and directed the activation of the Technical Support Center.

7.0 PRECAUTIONS LIMITATIONS

1. Notify Environmental Monitoring Team personnel of projected radiation and airborne activity levels in areas they will enter and advise them of pxotection requirements established by the Personnel Protection and Decontamination Team Leader.

2. The roads to the designated initial survey locations for all southerly sectors are particularly hazardous in inclement weather. During heavy rains, a four-wheel drive vehicle may be required (available at the SHEEC or from Security) on those roads. If roads are snow-packed, chains may be needed even fo'r four-wheel drive vehicles.

Do not direct the Environmental Monitoring Teams to survey in areas that would be hazardous for the type of vehicle that they have available.

8.0 SPECIAL TOOLS AND E UIPMENT None Applicable 9.0 PROCEDURE STEPS 9.1. If you are relieving another individual, review the activity log and obtain a briefing on the emergency and actions that have been completed or are in progress.

9.2. Conduct all communications activities in accordance with PEP-302 and PEP-303.

9.3. Report youx arrival in the Technical Support Center to the Emergency Communicator - Technical Support Center (or Emergency Communicator - Control Room if. the Emergency Communicator-Technical Support Center position is not yet manned), and inform the Radiological Control Director that you are assuming (or relieving, if appropriate) the position of Environmental Monitoring Team Leader.

9.4. Initiate and maintain a record of your activities and the activities of the. Environmental Monitoring Teams in accordance with PEP-405.

PEP-206 Rev. 0 Page 6 of 9

APR002 9.0 PROCEDURE STEPS 9.5. When a gaseous release of radioactive material is known or suspected to have occurred, consult with the Dose Projection Team Leader and using Attachment 1 and the guidance below, determine which downwind major compass sectors should be initially surveyed:

1. If the wind speed is greater than nine miles per hour, select the downwind major compass sector and one sector to each side (67.5 degrees wide).

2. If the wind speed is less than nine miles per hour, select the downwind major compass sector and two sectors to each side (112.5 degrees wide).

9.6. Consult with the Dose Projection Team Leader and Personnel Protection and Decontamination Team Leader to determine personnel protection requirements for the Environmental Monitoring Team(s).

9.7. Inform the Environmental Monitoring Team(s) of personnel protection requirements, then direct them to proceed to the predetermined locations for the selected downwind compass sectors and perform surveys in accordance with PEP-351.

9.8. Inform the Radiological Control Director and Dose Projection Team Leader of survey results as they become available. If the team(s) report radiation levels that, are greater than five mr/hr and are also more than double the expected levels, inform the Dose Projection Team Leader, and request the Personnel Protection and Decontamination Team Leader to determine whether any additional protective actions or equipment are required for the Environmental Monitoring Team (s).

9.9. Deploy the Environmental Monitoring Team(s) to additional locations to perform surveys as requested by the Radiological Control Director or Dose Projection Team Leader.

9. 10 Obtain

~ directions from the Radiological Control Director as to which laboratory to deliver Iodine collection cartridges and direct the Environmental Monitoring Team(s) to deliver the cartridges to that location.

9.11. NOTE:The frequency of this radio is publicly known.

If, contacted by state or local environmental monitoring, personnel on the'state VHF radio channel, answer the transmission but do not provide any information without first informing the Radiological'ontrol Director. Inform the state or local environmental monitoring personnel where the plant Environmental Monitoring Team(s) are PEP-206 Rev. 0 Page 7 of 9

APR002 9.0 PROCEDURE STEPS deployed, and suggest where they might deploy their teams to avoid duplication of effort. No information on the status of the emergency itself is to be transmitted on this radio channel. However, it is permissible to obtain a copy of a previously approved 'notification form from the Emergency Communicator and relay the meteorolo ical information ~onl from Part II, Item 4 of the North Carolina Emergency Notification Form to state or local environmental monitoring personnel.

9.12.Maintain continuous accountability of Environmental Monitoring Team personnel in accordance with PEP-382.

9.13.Inform the Radiological Control Director of additional supplies or equipment necessary to perform assigned functions.

9.14.When directed to do so, notify the alternate for your position specified by the Radiological Control Director to arrange for relief at, the end of the present shift in accordance with Section 9.2 of PEP-321. Notification messages shall be given only to the specified individual, and not to their spouses, children, babysitter, etc. If the specified alternate cannot be contacted, inform the Logistics Support Director.

9.15.When notified by the Environmental Supervisor at the Emergency Operations Facility that. he is ready to relieve you of responsibility for conducting and coordinating off-site monitoring, brief him on the status of the emergency and the environmental monitoring effort, and inform him of any contacts made with state or local environmental monitoring personnel.

Inform the Radiological Control Director and the Environmental Monitoring Team(s) that you have been relieved.

9.16.Continue to monitor communications between environmental monitoring personnel, and keep the Radiological Control Director and Dose Projection Team Leader informed of survey results.

9.17.When the emergency is terminated, collect all records generated by you and the Environmental Monitoring Team(s), and deliver them and your activity log to the Radiological Control Director.

10.0 DIAGRAMS ATTACHMENTS

1. Wind Directions PEP-206 Rev. 0 Page 8 of 9

APR002 ATTACHMENT 1 VIND DIRECTIONS Vind From De reees From North Wind Toward N 349-11 S NNE 12-33 SSW NE 34"56 SW ENE 57-78 WSW E 79-101 V ESE 102-123 WNW SE 124-146 NW SSE 147 <<168 NNW S 169-191 N SSW 192-213 NNE SW 214-236 NE WSW 237-258 ENE W 259-281 E WNW 282"303 ESE NW '304"326 SE NNV 327-348 SSE PEP-206 Rev. 0 Page 9 of 9

APR013 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

AMBER: PEP-207 TITLE: PLANT MONITORING TEAM LEADER REVlSION 0 APPROVED:

Signature Date TITLE:

PEP-207 Rev. 0 Page 1 of 7

APR013 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 2.2 Referenced Plant Emergency Procedures 3.0 RESPONSIBlLITIES 4 3.1 Reporting Responsibilities 4 3.2 Assignment and Relief of Position 3.3 Duties 4 4.0 DEFINITIONS 5 5.0 GENERAL 5 6.0 INITIATING CONDITIONS 5 7.0 PRECAUTION/LIMITATIONS 5 8.0 SPECIAL TOOLS AND EQUIPMENT 6 9.0 PROCEDURE STEPS 6 10.0 DIAGRAMS/ATTACHMENTS 7 PEP-207 Rev. 0 Page 2 of 7

APR013 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 through 7 0 PEP-207 Rev. 0 Page 3 of 7

APR013 1.0 PURPOSE This procedure implements section 2.4.6.5 of the SHNPP Emergency Plan. It specifies the actions to be performed by the Plant Monitoring Team Leader.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 2.4.6.5, "Plant Monitoring Team Leader"

2. Section 4.4, "Assessment Actions" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-204, "Radiological Control Director"

2. PEP-302, "Communications Activities"

3. PEP-303, "Use of Communications Equipment" PEP-321, "Notification of Emergency Personnel"

5. PEP-331, "Emergency Plant Monitoring>" Rev.0

6. PEP-382, "Personnel Accountability"

7. PEP-405, "Preparation of Activity Logs" 3.0 RESPONSIBILITIES 3.1 REPORTING RESPONSIBILITIES The Plant Monitoring Team Leader reports to the Radiological Control Director, or, prior I activation of that position, the Site to Emergency Coordinator.

3.2 ASSIGNMENT AND RELIEF OF POSITION An on-shift Radiation Control Technician assumes the responsibil-ities of Plant Monitoring Team Leader until relieved by a Project Specialist-Environmental and Chemistry, Specialist-Chemistry, or Specialist-ALARA.

3.3 DUTIES The Plant Monitoring Team Leader is responsible for:

1. Maintaining a record of all Plant Monitoring Team activities.

2. Providing personnel to conduct, 'in-plant radiological surveys for accident assessment purposes.

PEP-207 Rev. 0 Page 4 of 7

APR013 3.0 RESPONSIBILITIES 3.3 DUTIES (Cont'd)

3. Assigning personnel to operate the Post Accident Sampling System and to obtain and analyze other samples for accident. assessment purposes as directed by the Radiological Control Director.

Monitoring Radiation Monitor System data on the Emergency Response Facility Information System and maintaining a record of significant and unusual area radiation levels.

5. Assisting the Dose Projection Team by developing the radiological source term from Radiation Monitoring System data, in-plant surveys, and samples.

6. Maintaining personnel accountability of the Plant Monitoring Team.

7. Identifying any additional supplies or equipment needed to perform assigned functions.

8. Ensuring that he is relieved only by an alternate trained for duty as a Plant Monitoring Team Leader.

4.0 DEFINITIONS None Applicable 5.0 GENERAL Assessment of plant conditions in emergency situations requires. data that may not be available from permanently installed plant instru-mentation. The primary function of the Plant Monitoring Team Leader is to provide data on plant conditions for use by those individuals in the emergency organization performing assessment functions.

6.0 INITIATING CONDITIONS The Site Emergency Coordinator has activated the site emergency organization, including the Plant Monitoring Team Leader position.

7.0 PRECAUTIONS LIMITATIONS

1. Notify Plant Monitoring Team personnel of expected radiati'on levels and airborne activity levels in areas they will enter, based upon Emergency Response'Facility Information System readings, prior to entry.

2. Verify team members have appropriate protective gear (cover-alls, gloves, respirators, etc.) and an appropriate survey meter for the areas they will enter to obtain samples.

PEP-207 Rev. 0 Page 5 of 7

APR013 8.0 SPECIAL TOOLS AND E UIPMENT None Applicable

'.0 PROCEDURE STEPS If you are relieving another individual, review the activity log and obtain a briefing on the emergency and actions that have been completed or are in progress.

Conduct all communications activities in accordance with PEP-302 and PEP-303.

3. Report your arrival in the Technical Support Center to the Emergency Communicator, and inform the Radiological Control Director that you are assuming (or relieving, if appropriate) the position of Plant Monitoring Team Leader.

4. Initiate and maintain a record of your activities and the activities of the Plant Monitoring Team(s) in accordance with PEP-40S.

5. Determine the radiation and airborne activity levels for the Post Accident Sample System panel area, other sample areas and access routes to these areas by checking the Emergency Response Facility Informat'.ion System and by requesting information from the Personnel Protection and Decontamination Team Leader.

NOTE: The Personnel Protection and Decontamination Team Leader may have surveys in progress or may send an individual with the Plant Monitoring Team to obtain the required information.

6. Request the Operational Support Center Leader to dispatch a'eam to the Post: Accident Sampling System Panel to obtain a reactor coolant sample, containment sample and/or other samples deemed necessary depending upon current emergency conditions, in accordance with PEP-331.

Continuously monitor Radiation Monitoring System data with the Emergency Response Facility Information System.

Notify Plant Monitoring Team personnel, the Radiological Control Director, and Personnel Protection and Decon-tamination Team Leader of any significant changes or unusual area radiation levels and maintain a record of such levels.

When requested by the Site Emergency Coordinator or Radiological Control Director, request the Operational Support Center Leader to dispatch additional personnel from the'Plant Monitoring Team to perform other radiological assessment surveys in accordance with PEP-331. If additional personnel are not available, PEP-207 Rev. 0 Page 6 of 7

APR013 9.0 PROCEDURE STEPS instruct personnel who are presently performing surveys to perform the additional surveys after they finish their current assignment, or to divert to the new assignment if it has a higher priority and complete the original surveys afterward.

9. When requested by the Site Emergency Coordinator or Control Director, request the Operational

'adiological Support Center Leader to dispatch personnel from the Plant Monitoring Team to obtain and analyze additional plant samples in accordance with PEP-331.

10. If requested

source by the Dose Projection Team Leader, provide terms from in-plant survey and/or sample data.

11. 'Maintain continuous aCcountability of Plant Monitoring Team personnel in accordance with PEP-382 whenever they are not in the Operational Support Center.

12. Inform the Radiological Control Director of additional supplies or equipment necessary to perform assigned functions.

13. When directed to do so, notify the alternate for your position specified by the Radiological Control Director to arrange for relief at the end of the present shift in, accordance with Section 9.2 of PEP-321. Notification messages shall be given only to the specified individual, and not to their spouse, children, babysitter, etc., If the specified alternate cannot be contacted, inform the Logistics Support Director.

14. When the emergency has been terminated, collect all records generated by the Plant Monitoring Team, and deliver them and your activity log to the Radiological control Director.

10.0 DIAGRAMS ATI'ACHMENTS None Applicable PEP-207 Rev. 0 Page 7 of 7

APR013 CAROLINA POViER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLAiVI'LANT OPERATIiNG MANUAL VOLUiiE 2 PART 5 PROCEDURE TYPE: PLAiVZ EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-208 TITLE: PERSONNEL PROTECTION & DECONTAMINATION TEAM LEADER REVISION 0 APPROVED:

Signature Date TITLE:

PEP-208 Rev. 0 Page 1 of 9

APR013 TABLE OF CONTEiXTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

4 2,1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4 2.3 Other referenced Plant Procedures 3.0 RESPONSIBILITIES 5 3.1 Reporting Responsibilities 5 3.2 Assignment, and Relief of Position 5 3.3 Duties 5 4.0 DEFINITIONS 6 5.0 GENERAI 6 6.0 INITIATING CONDITIONS 6 7.0 PRECAUTIONS/LIMITATIONS 6 8.0 SPECIAL TOOLS AND EQUIPMENT 7 9.0 PROCEDURE STEPS 7 10.0 DIAGRAMS/ATTACHMENTS 9 PEP-208 Rev. 0 Page 2 of 9

APR013 LIST OF EFFECTIVE PAGES LEP

~Pa e Revision 1 thru 9 0 PEP-208 Rev. 0 Page 3 of 9

APR013 1.0 PURPOSE This procedure implements Section 2.4.6.7 of the SHNPP Emergency Plan. It specifies the actions to be performed by the Personnel Protection and Decontamination Team Leader.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 2.4.6.7, "Personnel Protection and Decontamination Team Leader"

2. Section 4.6, "Protective Actions for On-site Personnel"

3. Annex A, "Agreements" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-204, "Radiological Control Director"

2. PEP-302, "Communications Activities"

3. PEP-303, "Use of Communications Equipment"

4. PEP-321,"Notification of Emergency Personnel"

5. PEP-331, "Emergency Plant Monitoring"

6. PEP-371, "Emergency Response in Radiological Areas"

7. PEP-381, "Evacuation"

8. PEP-382, "Personnel Accountability"

9. PEP-383, "Administration of Potassium Iodide"

10. PEP-391, "First Aid and Medical Care" ll. PEP-394, "Search and Rescue"

12. PEP-405, "Preparation of Activity Logs" 2.3 OTHER REFERENCED PLANT PROCEDURES

1. HPP-075, "Vehicle Surveys"

2. HPP-251, "Personnel Decontaminations"

3. HPP-252, "Tool and Personnel Belongings'econtamination"

4. HPP-253, "Area Decontamination PEP-208 Rev. 0 Page 4 of 9

APR013 3.0 RESPONSIBILITIES

3. 1 REPORTING RESPONSIBILITIES The Personnel Protection and Decontamination Team Leader reports to the Radiological Control Director or, prior to activation of that position, the Site Emergency Coordinator.

3.2 ASSIGN>iENT AND RELIEF OF POSITION The senior on-shift Radiation Control Technician assumes the responsibilities of Personnel Protection and Decontamination Team Leader until'elieved by the Supervisor-Radiation Control or a designated Foreman-Radiation Control.

3.3. DUTIES The Personnel Protection and Decontamination Team Leader is respon-sible for:

1. Initiating and maintaining a record of Personnel Protection and Decontamination Team activities.

2. Assigning personnel to accompany other teams as required to provide health physics coverage.

3. Ensuring that radiological and chemical habitability conditions in the Operational Support Center, Security Building, and assembly areas are monitored.

4. If background radiation levels permit, ensuring that evacuated personnel and vehicles are monitored for contamination and decontaminated as required prior to leaving the site.

5. Administering Potassium Iodide to on-site personnel under the direction of the Radiological Control Directoz.

6. Establishing temporary radiological access control points, monitoring p'oints, decontamination areas, and dosimetry issue areas as required.

7. Establishing protective clothing and respiratory protection requirements foz all on-site emergency personnel.

Assisting the First Aid Team in evaluating the management of contaminated injured personnel, and notifying the Radiological Control Director when transportation of a contaminated injured person is required.

9. Maintaining accountability of Personnel Protection and Decontamination Team members when they are outside the Operational Support Center.

PEP-208 Rev. 0 Page 5 of 9

APR013 3.0 RESPONSIBILITIES 3.3. DUTIES (Cont'd)

10. Identifying any additional'upplies or equipment necessary to perform assigned functions.

11. Assigning members, of the Personnel Protection and Decontam-ination Team to direct the decontamination of 'on-site personnel and areas as required.

12. Ensuring that he is relieved only by an alternate trained to perform the duties of Personnel Protection and Decontam-ination Team Leader.

4.0 DEFINITIONS None Applicable 5.0 GENERAL During emergencies, habitability conditions on-site may change rapidly, and must. be continuously evaluated. The primaxy function of the Personnel Protection and Decontamination Team Leader. is to ensure that on-site radiological and chemical habitability conditions are properly monitored and that adequate protective actions are implemented as may be required to permi the on-site emergency response organization to carry out necessary activities.

To the extent that conditions permit, normal plant procedures will be utilized to fulfillthis function. The plant Radiation Monitoring System and other permanently installed instrumentation will be utilized to the maximum extent possible to preclude unnecessary exposures to personnel performing surveys'.0 INITIATING CONDITIONS The Site Emergency Coordinator has activated the site emergency organization, including the Personnel Protection and Decontamination Team Leader position.

7.0 PRECAUTIONS LIMITATIONS

1. Prior approval must be obtained from the Plant General Manager (who normally assumes the emergency position of Site Emergency. Coordinator-Technical Support Center) to permit planned radiation exposures in excess of regulatory limits.'n the absence of the Plant General Manager, the Environmental and Radiation Control Manager (who normally assumes the emergency position of Radiological Control Director) may authorize such exposures. The Site Emerg-ency Coordinator is authorized to approve such exposures in the absence of the above individuals.

PEP-208 Rev. 0 Page 6 of 9

APR013 7.0 PRECAUTIONS LIHITATIONS

2. Prior approval must be obtained from the Radiological Control Director or Site Emergency Coordinator before administering Potassium Iodide

3. After transportation of a contaminated injured person to a hospital, concurrence must be obtained from the Radio-logical Control Director or Site Emergency Coordinator prior to release of the hospital Radiological Emergency Room or ambulance for uncontrolled access and use.

8.0 SPECIAL TOOLS AND E UIP?KNT None Applicable 9.0 PROCEDURE STEPS If you are relieving another individual, review the activity log and obtain a briefing on the emergency and actions that have been completed or are in progress.

2. Conduct all communications in accordance with PEP-302 and PEP"303.

3. Report your arrival in the Technical Support Center to the Emergency Communicator-Technical Support Center (Emergency Communicator Control Room if the position of Emergency Communicator-Technical Support Center is not, yet, manned),

and inform the Radiological Control Director that you are assuming (or relieving, if appropriate) the position of Personnel Protection and Decontamination Team Leader.

4. Initiate and maintain a record of your activities and the activities of the Personnel Protection and Decontamination Team in accordance with PEP-405.

5. If an Alert, Site Emergency, or General Emergency has been declared, evaluate radiological and chemical habitability conditions in the Operational Support Center, Security Building, and Assembly Areas by directing the Operational Support Center Leader to dispatch the Personnel Protection and Decontamination Team to perform surveys in accordance with the methods referenced in PEP-331. Direct them to issue a group Thermoluminescent Dosimeter to each Assembly Area Leader while they are conducting the surveys to record exposure to personnel in the Assembly Areas.

Based on survey data foz the Operational Support Center and Security Building, establish requirements for dos-imetry, protective clothing, and respirators in these areas in accordance with PEP-371. Notify the Radiological PEP-208 Rev. 0 Page 7 of 9

APR013 9.0 PROCEDURE STEPS Control Director, the Operational Support Center Leader, and other team leaders in the Technical Support Center of these requirements.

Vhen notified by other team leaders or the Radiological Control Director that teams are to be dispatched, obtain Radiation Monitoring System data for the team's transit and destination areas, if available, from the Plant Monitoring Team Leader.

Establish protection requirements for these teams in accordance with PEP-371. If needed, assign a member of the Personnel Protection and Decontamination Team to accompany the team. Also notify the Radiological Control Director, Operational Support Center Leader and Personnel Protection and Decontamination Team of these requirements.

9. If an evacuation is ordered, direct the Operational Support Center Leader to dispatch the Personnel Protection and Decontamination Team to monitor evacuating personnel and/or vehicles for contamination in accordance with HPP<<251 and HPP-075 at the Security Building and/or other remote location(s) specified by the Radiological Control Director, and to decontaminate personnel, vehicles, and belongings in accordance with HPP-251 and HPP-252 if necessary.

10. If the Radiological Control Director directs the admini-stration of Potassium Iodide, administer the drug to selected personnel in the Technical Support Center and request the Operational Support Center Leader to direct the Personnel Protection and Decontamination Team to administer the drug to selected personnel in the Operat-ional Support Centez in accordance with PEP-383.

If requested by the First Aid Team or Search and Rescue Team, request the Operational Support Center Leader to assign personnel from the Personnel Pzotection and Decontamination Team to perform radiation surveys in accordance with the methods referenced in PEP-331, monitor injured personnel for contamination, and/or assist in decontamination in accordance with HPP-251. If the First Aid Team Leader decides to transport a contaminated injured person to a Radiological Emergency Room, notify the Radiological Control Director and request the Operational Support Center Leader to assign a Personnel Protection and Decontamination Team member to accompany the individual in accordance with PEP-391.

PEP"208 Rev. 0 Page 8 of 9

APR013 9.0 PROCEDURE STEPS

12. If requested by the Radiological Control Director, request the Operational Support Center Leader to dispatch personnel from the Personnel Protection and Decontam-ination Team to decontaminate on-site personnel and/or areas in accordance with HPP-251 and/or HPP"253.

13. Maintain continuous accountability of Personnel Protection and Decontamination Team members when they are out of the Operational Support Center in accordance with PEP-382.

14. Notify the Radiological Control Director of additional supplies or equipment necessary to perform assigned functions.

15. When directed to do so, notify the alternate for your position specified by the Radiological Control Director to arrange for relief at the end of the present shift in accordance with Section 9.2 of PEP-321. Notification messages shall be given only to the specified individual, and not to their spouse, children, babysitter, etc. If the specified alternate cannot be contacted, inform the Radiological Control Director.

16. When the emergency has been terminated, collect all records generated during the emergency by the Personnel Protection and Decontamination Team and deliver them and your activity log to the Radiological Control Director.

10.0 DIAGRAMS ATTACEKNTS None Applicable PEP-208 Rev. 0 Page 9 of 9

0 APR014 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP"210 TITLE: EMERGENCY SECURITY TEAM LEADER REVISION 0 APPROVED:

Signature o< ~g Date gg TITLE:

PEP-210 Rev. 0 Page 1 of 10

APR014 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1,0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan Refences 4 2.2 Referenced Plant Emergency Procedures 4 2' Other References 4 3,0 RESPONSIBILITIES 4 3.1 Reporting Responsibilities 4 3.2 Assignment and Relief of Position 5 3.3 Duties 5 4.0 DEFINITIONS 6 5.0 GENERAL 6 6.0 INITIATING CONDITIONS 6 7.0 PRECAUTIONS/LIMITATIONS 6 8.0 SPECIAL TOOLS AND EQUIPMENT 6 9.0 PROCEDURE STEPS 6 10.0 DIAGRAMS/AT1'ACHMENTS 10 PEP"210 Rev. 0 Page 2 of 10

APR014 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 thxough 10 0 PEP-210 Rev. 0 Page- 3 of 10

APR014 1.0 PURPOSE The purpose of this procedure is to implement Section 2.4.5.3, "Emergency Security Team Leader" of the SHNPP Emergency Plan, This procedure provides guidance for the Emergency Security Team Leader.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

l. 2.4.5.3, "Emergency Security Team Leader"

2. 4.8, "Security Measures" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-301, "Notification and Communications"

2. PEP-302, "Communications Activities"

3. PEP-303, "Use of Communications Equipment"

4. PEP-321, "Notification of Emergency Personnel"

5. PEP-371, "Emergency Response in Radiological, Areas"

6. PEP-381, "Evacuation"

7. PEP-382, "Perso'nnel Accountability"

8. PEP-383, "Administration of Potassium Iodide"

9. PEP-384, "Access Control"

10. PEP-394, "Search and Rescue"

11. PEP-405, "Preparation of Activity Logs" 2..3 OTHER REFERENCES

1. SP-016, "Emergency Plan Support" 3.0 RESPONSIBILITIES 4

3.1 REPORTING RESPONSIBILITIES The Emergency Security Team Leader reports to the Logistics Support Director, or prior to the activation of these positions, the Site Emergency Coordinator.

PEP-210 Rev. 0 Page 4 of 10

APR014 3.0 RESPONSIBILITIES 3.2 ASSIGi%EENT AND RELIEF OF POSITION 3.2.1 The position of Emergency Security Team Leader is normally filled by the Senior Specialist-Security except as noted in 3.2.2 and 3.2.3 below.

3.2.2 If the Senior Specialist-Security is unavailable, the position is filled by a supervisory level member of the security organization except as noted in 3.2.3 below.

3.2.3 Should the Technical Support Center be activated as a result of an incident(s) of the type addressed in the SHNPP Safeguards Contingency Plan, the position of Emer-gency Security Team Leader may be assumed at a location other than the Technical Support Center. In this case, a member of the Security Organization, with communications with the Security 'Force, will be assigned to the Technical Support Center to relay information and maintain a record of events.

3.3 DUTIES The Emergency Security Team Leader, located in the Technical Support Center, reports to the Logistics Support Director and is responsible for the following:

Maintain plant security in accordance with the provisions of the SHNPP Security Plan and Safeguards Contingency Plan.

2. Identify to the Logistics Support Director any non-routine security procedures and/or contingency conditions that are in effect or that require a response.

Pxovide personnel, as available, for search teams for missing personnel. Identify areas and routes for search-ing in coordination with the Radiological Control Direc-tor.

Ensure that necessary coordination with local law enforce-ment agencies is maintained.

5. Provide necessary members of the security force to main-tain security at the Emergency Operations Facility when activated.

6. Ensure that the locations of security personnel are verified frequently by Security Force supervision.

PEP-210 Rev. 0 Page S of 10

APR014 3.0 RESPONSIBILITIES 3.3 DUTIES (Cont'd)

7. Generate periodic listings of personnel within the Pro-tected Area via the Security Computer.

8. Provide escorts for emergency vehicles that may be required to enter the Protected Area.

4.0 DEFINITIONS None Applicable 5 .0 GENERAL None Applicable 6.0 INITIATING CONDITIONS

1. An emergency has been declared and the Site Emergency Coordinator has activated the Emergency Security Team Leader position.

7.0 PRECAUTIONS LIMITATIONS

1. Determine via the Radiological Control Director and/or the Personnel Protection and Decontamination Team Leader whether security personnel are at risk in the area where they are located (i.e. areas in the Radiologically Con-trolled Area of the plant where they are assigned to a fixed post or patrol).

8.0 SPECIAL TOOLS AND E UIPMENT

1. Handheld Radio.

9.0 PROCEDURE STEPS 9.1 Report your arrival at the Technical Support Center to the Emergency Communicator-Technical Support Center (or Emergency Communicator-Control Room if the first position is not manned yet) and inform the Logistics Support Director that your are assuming (or relieving, if appropriate) the position of Emer-gency Security Team Leader.

9.2. Conduct all communications activities with other emergency organization groups in accordance with PEP-302 and PEP-303.

PEP-210 Rev. 0 Page 6 of 10

APR014 9.0 . PROCEDURE STEPS 9.3 If you are relieving another individual, review the activity log and obtain a briefing on the emergency and actions that have been completed, are in progress, or are scheduled for a later time.

9.4 Maintain a record of your activities in accordance with PEP-405.

9.5 If the emergency was caused by a safeguards contingency event, ensure appropriate contingency actions are being taken and that pertinent actions are recorded.

9.6 Determine if all security personnel are accounted foz.

9.7 If an Alert or highez classification of emergency is announced (thereby requiring an assembly of. personnel for accountability purposes), instruct the. senior member of the Security Force to implement appropriate elements of PEP-384, "Access Control".

If the security access control system shows that personnel are still present in the Radiologically Controlled Area, notify the Logistics Support Director.

9.8 Check with the Radiological Control Director,,Personnel Pro-tection and Decontamination Team Ieader and/or the Site Emer-gency Coordinator ta determine if the type of emergency has affected the radiological conditions in the Radiologically Controlled Area and whether they recommend temporarily evacuating the security force from this area.

9.9 If a decision is made to temporarily evacuate the Radiological-ly Controlled Area procede as follows:

1. Notify the Central Alarm Station.

2. Direct the senior member of the Secuzity Force to deter-mine if the area has been cleared except for security personnel'via computer, security sweep or other means as per SP-016). In the event other personnel are indicated as present inside the Radiologically Controlled Area, notify the Logistics Support Directoz.

3. Direct security personnel to withdraw from the Radio-logically Controlled Area to the main radiological access control point (261 ft. elev. in the Radwaste Processing Building) and the Operations and Security access control point (289 ft.elev.in the Reactor Auxiliary Building).

PEP-210 Rev. 0 Page 7 of 10

APR014 9.0 PROCEDURE STEPS

4. Direct security personnel to secure the Radiologically Controlled Area from these two entry points.

S. Take other actions as necessary to secure the area and advise the Logistics Support Director when such actions are completed.

9.10 If the Radiologically Controlled Area is cleared of all person-nel, notify the Logistic Support Director when this is complet-ed. I 9.11 Identify any other non-routine security procedures that are being implemented or contingency plans that are in effect.

NOTE: The following notification must, be performed within 30 minutes of the initial declaration of the emergency.

9.12 Assist in the accounting of personnel per PEP-382, "Personnel Accountability" by notifying the Logistics Support Director of the names of personnel considered to be missing and their last known location as reported by the Assembly Area Leader(s).

9.13 Provide assistance, as appropriate according to PEP-394, "Search and Rescue" to locate any missing personnel.

9.14 If the Emergency Operations Facility is to be activated, instruct the senior member of the security force to provide security as per PEP-384.

9.15 If off-site response personnel/agencies are being requested by the Site Emergency Coordinator, notify the senior member of the security force to expedite access.

9.16 If the emergency classification is upgraded to General Emergency and the Sheriff's Department Deputies have not arrived yet to man the patrol boat, direct security to man the boat and perform the warning of the general public on Harris Reservoir within the Exclusion Area until the deputies arrive.

9.17 If an evacuation of the Site is ordered, as per PEP-381, notify the senior member of the Security Foxce, inform him where personnel are being directed to go , and provide him with instructions for access and traffic control..

NOTE: The member(s) of the security force on the reentry team must also comply with the requirements of the Radiation Work Permit (See PEP-371).

PEP-210 Rev. 0 Page 8 of 10

APR014 9.0 PROCEDURE STEPS 9.18 When notified by the Radiological Control Director that a team is being formed to reenter the Radiologically Controlled Area, direct the Senior Member of the Security Force to assign a properly equipped and clothed member of the security force to the team (if security has been temporarily evacuated).Dixect the senior member of the security force to notify the Emergency Security Team Leader, the individual and the central a'larm station of the assignment and the time and place of anticipated entry to the Radiologically Controlled Area.

9. 19 After the radiological conditions have been determined in the Radiologically Controlled Area, confer with the Radio-logical Control Director as to whether security personnel can be reposted within the area (and under what conditions) or whether it is more prudent to continue to send security person-nel with each team that enters.

9.20 Direct the senior member of the security force to provide and periodically maintain a list of personnel on duty with the security force and their locations (or patrol routes), to maintain accountability of security personnel.

9.21 Direct the Senior Member of the Security Force to provide listings of personnel within the Protected Area when requested by the Logistics Support Director.

9.22 Act as a point of contact and provide coordination, as necessary, with local law enforcement agencies and other agen-cies which may be providing traffic control, providing Safe-guards contingency support and/or performing warning functions on Harris Reservoir and in the surrounding forest area.

Agencies involved may include, but are not limited to the following:

1. Wake County Sheriff's Department (patrol cars and boat for warning, traffic control points and safeguards contingency support) - Lead Agency

2. North Carolina Wildlife Resources Commission, Enforcement Division (fixed wing plane for warning)

3. Division of Forest Resources, Department of Natural Resources and Community Development (helicopter with sirens and public address system, and 4-wheel drive vehicles for warning)

4. North Carolina National Guard, Office of the Adjutant General (helicopter with public address system and 4-wheel drive vehicles for warning)

PEP-210 Rev. 0 Page 9 of 10

APR014 9.0 PROCEDURE STEPS

5. North Carolina Highway Patrol (patrol cars for traffic control points and safeguards contingency support).

9.23 Perform other security related duties as necessary.

9.24 Notify the Logistics Support Director of additional supplies, equipment, or personnel needed to perform assigned functions.

9.25 Vhen the emergency has been terminated, collect emergency related security records generated during the emergency and deliver them (a copy) and your activity log to the Senior Specialist-Emergency Planning.

10.0 DIAGRAMS ATTACHMENTS None Applicable PEP-210 Rev. 0 Page 10 of 10

APR013 CAROLINA POVER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: . PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-211 TITLE: DAMAGE CONTROL TEAM COORDINATOR REVISION 0 APPROVED:

Signature TITLE:

PEP-211 Re@. 0 Page 1 of 7

APR013 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 4.

1.0 PURPOSE

2.0 REFERENCES

4 2.1 Emergency Plan References 2.2 Referenced Plant Emergency Procedures 4 2.3 Other Referenced Plant Procedures 4 3.0 RESPONSIBILITIES 4 3.1 Reporting Responsibilities ~

4 3.2 Assignment and Relief 'of Position 4 3.3 Duties 5 4,0 DEFINITIONS 5 5.0 GENERAL 5 6.0 INITIATING CONDITIONS 5 7.0 PRECAUTIONS/LIHITATIONS 5 8.0 SPECIAL TOOLS AND EQUIP>iENT 6 9.0 PROCEDURE STEPS 6 10.0 DIAGRAHS/ATTAC191ENTS 7 PEP-211 Rev. 0 Page 2 of 7

APR013 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 thru 7 0 PEP-211 Rev. 0 Page 3 of 7

APR013 1.0 PURPOSE This procedure implements Section 2.4.4.1 of the SHNPP Emergency Plan. It specifies actions to be taken by the Damage Control Team Coordinator.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 2.4.4.1, "Damage Control Team Coordinator"

2. Section 2.4.4.2, "Damage Control Team Leader"

3. Section 2.4.4.3, "Damage Control Team" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-302,. "Communications Activities"

2. PEP-303, "Use of Communications Equipment"

3. PEP-321, "Noti,fication of Emergency Personnel"

4. PEP-371, "Emergency Response, in Radiological Areas"

5. PEP-382, "Personnel Accountability"

6. PEP-405, "Preparation of Activity Logs" 2.3 . OTHER REFERENCED PLANT PROCEDURES

1. AP-020, "Clearance Procedure"

2. MMM-012, "Maintenance Pork Control Procedure" 3.0 RESPONSIBILITIES 3.1 REPORTING RESPONSIBILITIES

1. The Damage Control Team Coordinator reports to the Emergency Repair Director in the Technical Support Center or, prior td activation of that. position, the Site Emergency Coordinator.

2. The Damage Control Team(s) report to the .Damage Control Team Coordinator via the Damage Control Team Leader(s).

3.2 ASSIGNMENT AND RELIEF OF POSITION Upon arrival at the Technical Support Center, a Maintenance Supervisor, Project Specialist - Maintenance, or Project Engineer-Maintenance assumes the responsibilities of Damage Control Team, Coordinator.

PEP-211 Rev. 0 Page 4 of 7

APR013 3.3 DUTIES The Damage Control Team Coordinator is responsible for:

1. Maintaining a record of all Damage Control Team activities.

2. Determining the extent of damage to equipment and recom-mending corrective action(s) to the Emergency Repair Director.

3. Briefing Damage Control Teams on missions to be performed.

4. Dispatching, directing, and monitoring the activities of Damage Control Teams.

5. Maintaining accountability of Damage Control Team Personnel.

6. Keeping the Emergency Repair Director informed of the status of emergency repairs.

7. Identifying any additional supplies or equipment needed to perform assigned functions.

8. Ensuring that he is relieved only by an alternate trained to perform the duties of Damage Control Team Coordinator.

4.0 DEFINITIONS None Applicable 5.0 GENERAL Many of the initiating events that result in.declaration of an emergency involve damage to or malfunction of safety related equipment. The primary function of the Damage Control Team Coordinator is to direct the restoration of equipment that is necessary to establish or maintain safe shutdown of the plant.

6.0 INITIATING CONDITIONS The Site Emergency Coordinator has activated the site emergency organization, including the Damage Control Team Coordinator position.

7.0 PRECAUTIONS LIMITATIONS

1. The Site Emergency Coordinator has overall responsibility for control of the plant.'o action shall be taken that could affect the operability of a plant system without his concurrence.

PEP-211 Rev. 0 Page 5 of 7

APR013 7.0 PERCAUTIONS LIMITATIONS

2. The Personnel Protection and Decontamination Team Leader is responsible for establishing radiological protection requirements for all on-site personnel, and shall be consulted prior to dispatching any team(s).

8.0 SPECIAL TOOLS AND E UIPMENT None Applicable 9.0 PROCEDURE STEPS If you are relieving another individual, review the activity log and obtain a briefing on the emergency and actions that have been completed or are in progress.

2. Conduct all communications in accordance with PEP-302 and PEP-303..

Report your arrival in the Technical Support Center to the Emergency Communicator in the Technical Support Center (in the Control Room if the Technical'upport Center is not yet manned) and inform the Emexgency Repair Director that you are assuming (or relieving, if appropriate) the position of Damage Control Team Coordinator.

4, Initiate and maintain a record of your activities and the activities of the Damage Control Team(s) in accordance with PEP-405.

5, Maintain accountability of Damage Control Team personnel in accordance with PEP-382.

6. When reports of malfunctioning or oux, of service equipment are received, consult with the Personnel Pxotection and Decontamination Team Leader to determine personnel protection requirements, obtain an Emergency Radiation Work Permit in accordance with PEP-371, if required, and the cause of dispatch a Damage Control Team to determine the problem.

7. Based on the Damage Control Team's assessment, recommend actions necessary to restore equipment to service to the Emergency Repair Director. Advise the Emexgency Repair Director of any additional tools, supplies, or equipment that will be required if they are not readily available, and whether the work is within the scope of existing plant procedures.

PEP-211 Rev. 0 Page 6 of 7

APRQ13 9.0 PROCEDURE STEPS

8. When directed to do so by the Emergency Repair Director, brief the Damage Control Team Leader on the tasks to be performed, obtain clearance(s) as necessary in accordance with AP-020, then dispatch and direct the activities of the Damage Control Team(s) as necessary to accomplish repairs or maintenance in accordance with procedures or methods specified by the Emergency Repair Directory.

9. Inform the Emergency Repair Director immediately if unanticipated problems are encountered or additional materials or supplies are needed, and periodically provide updated information as work progresses.

10. Document repair actions as appropriate in accordance with MMM"012.

11. When directed to do so, notify the alternate for your position specified by the Emergency Repair Director to arrange for relief at the end of the present shift in accordance with Section 9.2 of PEP-321. Notification messages shall be given only to the specified individual, and not to their spouse, children, babysitter, etc. If the specified alternate cannot be contacted, inform the Logistics Support Director.

12. When the emergency has been terminated, collect all records generated by yourself and the Damage Control Teams and deliver them to the Emergency Repair Director.

10.0 DIAGRAMS ATTACHMENTS None Applicable PEP-211 Rev. 0 Page 7 of 7

APR011 CAROLINA POWER &, LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLTE 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-212 TITLE: OPERATIONAZ SUPPORT CENTER LEADER REVISION 0 APPROVED:

Signature ate TITLE".

PEP-212 Rev. 0 Page 1 of 9

APR011 TABLE OF CONTENTS (OPERATIONAL SUPPORT CENTER LEADER)

Section ~Pa e Table of Contents 2 List of Effective Pages 3

1. 0 PURPOSE

2.0 REFERENCES

4 2.1 Emergency Plan Refexences 2.2 Referenced Plant Emergency Procedures 4 2.3 Other References

3. 0 RESPONSIBILITIES 4

3. 1 Reporting Responsibilities 4 3.2 Assignment and'elief of Position' 4 3.3 Duties 5 4.0 DEFINITIONS 5 5.0 GENERAL 5 6.0 INITIATING CONDITIONS 6 7.0 PRECAUTIONS AND LIMITATIONS 6 8.0 SPECIAL TOOLS AND EQUIPMENT 6 9.0 PROCEDURE STEPS 7 9.1 Initial Actions 7 .

9.2 Recurring Actions 8 10.0 DIAGRAMS/ATTAC1BKNTS 9 PEP-212 Rev. 0 Page 2 of 9

APR011 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 through 9 0 PEP-212 Rev. 0 Page 3 of 9

~ ~

APR011 1.0 PURPOSE The purpose of this procedure is to implement Section 2.4.4.4, "Operational Support Center Leader," of the SHNPP Emergency Plan.

The position of Operational Support Center Leader may be activated during an Unusual Event if the Site Emergency Coordinator desires it, but is normally activated during an Alert, Site Emergency, or General Emergency. This procedure describes the actions of the Operations Support Center Leader.

2.0 REFERENCES

2,1 EMERGENCY PLAN REFERENCES

1. Section 2.4.4.4, "Operational Support Center Leader" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-302, "Communications Activities" 2~ PEP-303, "Use of Communications Equipment" 3~ PEP-321, "Notification of Emergency Personnel"

4. PEP"323, "Setup and Operation of Emergency Facilities"

5. PEP-382, "Personnel Accountability"

6. PEP-402, Maintaining Readiness of Emergency Facilities and Equipment"

7. PEP-405, "Preparation of Activity Logs" 2 3

~ OTHER REFERENCES

1. SP-016, "Emergency Plan Support"

3. 0 RESPONSIBILITIES 3.1 REPORTING RESPONSIBILITIES The Operational Support Center Leader reports to the Emergency Repair Director, or prior to activation of this position, the Site Emergency Coordinator.

3.2 ASSIGRKNT AND RELIEF OF POSITION The primary person assigned to the position of Operational Support Center Leader during normal working hours is a Maintenance Supervisor.

2. If a Maintenance Supervisor is unavailable (or needs help), the position is filled by a Maintenance Project Specialist or a Maintenance Project Engineer.'.

The on-shift person who has the interim responsibility PEP-212 Rev. 0 Page 4 of 9

APR011 3.0 RESPONSIBILITIES 3.2 ASSIGi%EENT AND RELIEF OF POSITION (Cont'd) is one of the maintenance personnel.

3.3 DUTIES The Operational Support Center Leader, located in the Operations Support Center; is responsible for the following:

Provide personnel accountability for the Operational Support Center by maintaining personnel logs and informing appropriate Technical Support Center personnel of emergency team assign-ments.

2. Compose, equip, and/or dispatch emezgency teams in response to requests via the Emergency Repair Director from the Radiological Control Director, Emergency Repair Director, or Plant Operations Director.

3. Dispatch additional personnel and/or equipment as requested by the Plant Monitoring Team Leader, Personnel Protection 6 Decontamination Team Leader and Damage Control Team Leaders.

4. Monitor communications between Plant Monitoring Teams, Person-nel Protection and Decontamination Teams, and Damage Control Teams and the Technical Support Center.

5. Be formally relieved by as alteznate trained for duty as Operational Support Center Leader.

6. Maintain a record of activities.

4.0 DEFINITIONS

1. Protected Area - The area within the security fence around Unit 1 buildings necessary for the operation of Unit 1.

2. Emergency Team - Plant Monitozing Team, Personnel Protec-tion and Decontamination Team, Damage Control Team, Environmental Monitoring Team, First Aid Team, and Fire Brigade.

5.0 GENERAL The Operational Support Center Leader is in charge of the Operation-al Support Center. The Operational Support Center is the assembly location for the Damage Control Team (s), Plant Monitoring Team (s),

Personnel Protection and Decontamination Team, Environmental Moni-toring Team (s), First Aid Team, and Seazch and Rescue Team (s). An Emergency Response Organization Personnel Roster will be avaiiable in the Operational Support Center. Selected teams, special equip-ment, and augmentation personnel are dispatched, as needed, at the request of emergency directors or team leaders. The Operational Support Center is PEP-212 Rev. 0 Page 5 of 9

APR011 5.0 GENERAL (Cont'd) normally located in the lunchroom of the Service Building, which is

~ ~~

I inside the Protected Area, and has reliable voice communications

+ with the Control Room, Technical Support Center, and Emergency Operations Facility. If environmental conditions warrant it (such as radiation levels greater than SmR/hr, airborne activity levels greater than 25% of maximum permissible concentration (MPC), exces-sive smoke or toxic fumes), the Operational Support Center leader may recommend to the Emergency. Repair Director and/or the Site Emergency Coordinator may decide to move the location of the Opera-tional Support Center.

6.0 INITIATING CONDITIONS

1. The Site Emergency Coordinator has activated the site emergency organization (per PEP-321) including the Opera-tional Support Center Leader position (which is normally activated for Alert, Site Emergency, and General Emergen-cy) 7.0 PRECAUTIONS LIMITATIONS As soon as possible, verify habitability of the Operation-al Support Center by having a radiation, airborne activi-ty, and contamination survey of the Operational Support Center performed to check on its radiological conditions.

If the emergency is have a result of a toxic chemical release a check performed to determine (such as chlorine),

the concentration of toxic fumes in the Operational Support Center.

5 ~

2. Initial accountability of personnel in the Operational Support Center must be performed and the Emergency Securi-ty Team Leader notified within 30 minutes after declara-tion of an Alert, Site Emergency, or General Emergency (as per PEP-382). Therefore, information on unaccounted for personnel should be given to the Emergency Security Team Leader (or member of the security organization present at Operational Support Center) within 20 minutes of the announcement or, if possible, sooner.

3. Perform continuous accountability by notifying Security whenever a team is dispatched or returns to the Operation-al Support Center.

8.0 SPECIAL TOOLS AND EQUIPMENT

1. Emergency response organization personnel rosters.

2. Personnel Accountability forms.

3. Telephone/Public Address system, and security/operations portable radios. (Use of this equipment is discussed in PEP-302 and PEP-303.)

PEP-212 Rev. 0 Page 6 of 9

t APROll 8,0 SPECIAL TOOLS AND E UIPMENT

4. Emergency lights.

5. Manning Board.

6. Camera

7. Megaphone

8. Portable Lanterns 9.0 PROCEDURE STEPS 9.1 INITIAL ACTIONS 9.1.1. Upon activation of the position by announcement over the Public Address system, the Operational Support Center PP Leader reports to the Operational Support Center, calls the Control Room (Emergency Commu'nicator or Site Emergency Coordinator) and reports:

1. His name 2~ Position he is assuming

3. Time of arrival (or estimated time of arrival if not at the Operational Support Center) 9.1.2. The Operational Support Center Leader then:

l. Obtains the stored equipment for the Operational Support Center Leader (from the storage room and the tool room next door),

2. Initiates the Operational Support Center log 3, Establishes radio communication with the Contzol Room and Technical Support Center (if activated)

4. Sets up the Operational Support Center per PEP-323 9.1.3. If the emergency is classified as an Unusual Event and emergency teams have not been activated, the Operational T

P Support Center Leader reports to the Control Room that the P

Operational Support Center is activated and stands by for further instructions. Otherwise, go to Step 9.1.4.

NOTE: For an Unusual Event, this terminates use of this procedure until the teams are activated at which time continue with Step 9 1.4.

~

9. 1.4. Vhen the emergency teams are activated, the Operational Support Center Leader, a Member of the Security Organiza-tion or an assistant appointed by the Operational Support Center Leader checks off names on an Emergency Personnel Roster as personnel arrive.

9.1.5. lilhen the personnel from the Personnel Protection &

Decontamination Team arrive, the Operational Support Center Leader requests that a habitability suzvey be initiated for the Operational. Support Center and the Operational Support Center Leader informed immediately of the results.

PEP-212 Rev. 0 Page 7 of 9 P'

APROll 9.0 PROCEDURE STEPS 9.1 INITIAL ACTIONS (Cont'd) 9.1.6. The Operational Support Center Leader instructs the personnel to:

1. Assemble and/or check out emergency equipment

2. Review applicable emergency procedures

3. Report to the Operational Support Center Leader when their team is ready 9.1.7. When the Operational Support Center is activated (personnel and equipment are present and ready so that a minimum of one emergency team of each type (see 4.2) that has been activated can be dispatched), the Operational Support Center Leader notifies the Technical Support Center (normally the Emergency Repair Director) or, Technical Support Center is not yet activated, he notifies if the the Control Room (Emergency Communicator or Site Emergency Coordinator) of the time of activation.

9.1.8. As habitability results become available, the Operational Suppo'it Center Leader informs the Technical Support Center (Emergency Repair Director or Radiological Control Direc-tor) or the Control Room,

'is not yet activated.

if the Technical Support Center 9.1.9. Within 20 minutes after declaration of the emergency, the Operational Support Center Leader notifies the Emergency Security Team Leader of the names of anybody considered to be missing and identifies the individuals of the emergency response organization who are present in the Operational Support Center.

9. 2 RECURRING ACTIONS 9.2. 1. After the initial activation and accountability efforts have been accomplished, the Operational Support Center Leader supervises the personnel in the Operational Support Center (except Damage Control Teams) and reports to the Emergency Repair Director. Some of the recurring items that he (or an assistant) may perform while doing this are:

1. Have habitability of Operational Support Center surveyed and evaluated (normally once per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

'hift or, whenever 'there is an escalation in the s'eyerity of accident classification or when an airborne release occurs) to determine continued Operational Support Center habitability.

2. Supervise the composition, equipping, and dispatch. of emergency teams (except Damage Control Teams) in response to requests from emergency directors.

PEP-212 Rev. 0 Page 8 of 9

APR011 9.0 PROCEDURE STEPS 9.2 RECURRING ACTIONS (Cont'd)

3. Dispatch additional personnel and/or equipment as requested by the Plant Monitoring Team Leader, Personnel Protection & Decontamination Team Leader, Damage Control Team Leader and Damage Control Team Coordinator.

4. Monitor communications between emergency teams and the Technical Support Center (both for accountability and to be forewarned as to what requests may be made for additional personnel or equipment).

5. Maintain accountability of all personnel who reported to the Operational Support Center.

6. Maintain an activity log in accordance with PEP-405.

9.2.2. The Operational Support Center Leader reports the status of the, Operational Support Center to the Emergency Repair Director approximately every two hours (or as requested by the Emergency Repair Director). Significant events or changes in Operational Support Center habitability should be reported as they occur or as soon afterwards as possi-ble.

9.2.3. When the Operational Support Center Leader turns over his position to a successor, he:

1. Reviews the events that have happened

2. Briefs the new Operational Support Center Leader on ongoing activities and what to expect

3. Signs out in the Operational Support Center log, noting name, date and time.

9.2.4. When the emergency is terminated, the Operational Support Center Leader collects all records generated by personnel in the Operational Support Center, and delivers them and his activity log to the Emergency Repair Director.

10.0 DIAGRAMS ATTACHMENTS None Applicable PEP-212 Rev. 0 Page 9 of 9

APR010 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOL%K 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP "215 TITLE: ASSEMBLY AREA LEADER REVISION 0 APPROVED:

Signature Dat TITLE:

PEP-215 Rev. 0 Page 1 of 9

APR010 TABLE OF CONTENTS

~Pa e Table of Contents List, of Effective Pages 1.0 PURPOSE 4 2,0 REFERENCES 4 2.1 Emergency Plan References 4 2.2. Referenced Plant Emergency Procedures 4 2.3 Other References 4 3.0 RESPONSIBILITIES 4 4.0 DEFINITIONS 5 5.0 GENERAL 5 6.0 INITIATING CONDITIONS 5 7.0 PRECAUTIONS/LIMITATIONS 6 8.0 SPECIAL TOOLS AND EQUIPMENT 6 9.0 PROCEDURE STEPS 6 10.0 DIAGRAMS/ATTACFMNTS 7 PEP-215 Rev. 0 Page 2 of 9

APR010 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 through 9 0 PEP-215 Rev. 0 Page 3 of 9

APR010 1.0 PURPOSE The purpose of this procedure is to implement section 2.4.5.4, "Assembly Area Leaders" and section 4.6.2, "Evacuation and Personnel Accountability" of the SHNPP Emergency Plan.

The position of Assembly Area Leader is activated during an Alert, a Site Emergency or a General Emergency. This procedure describes the actions of the Assembly Area Leader.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 2.4.5.4, "Assembly Area Leaders"

2. Section 4.6.2, "Evacuation and Personnel Accountability" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-321, "Notification of Emergency Personnel"

2. PEP-381, "Evacuation"

3. PEP-382, "Personnel Accountability" 2.3 OTHER REFERENCES

1. SP-016, "Emergency Plan Supp'ort" 3.0 RESPONSIBILITIES 3,1 REPORTING RESPONSIBILITIES The Assembly Area Leader reports to the Logistics Support Director or, prior to activation of this position, the Site Emergency Coordinator.

3.2. ASSIGNMENT AND RELIEF OF POSITION 3.2. 1. During normal working hours, the Assembly Area Leaders are:

l. At the Construction Warehouse, the Project General Manager is the primary designee, and the Assistant Project General Manager/Senior Resident Engineer and the Manager - Construction Start-up are the alternates.

2. At the Units 3 & 4 Fuel Handling Building Lunchroom and Auditorium, a Start-up Supervisor is the Assembly Area Leader.

PEP"215 Rev. 0 Page 4 of 9

APR010 3.0 RESPONSIBILITIES 3.2 ASSIGNMENT AND RELIEF OF POSITION (Cont'd) 3.2.2. Outside of normal working hours, the on-shift Site Superin'tendent is the Assembly Area Leader.

3.3 DUTlES The Assembly Area Leader(s), located in the designated assembly area(s), are responsible for the following actions when an Alert, Site Emergency, or General Emergency is declared:

1. Maintain a record of activities in the assembly area.

2. Coordinate the activities in the assembly area.

3. Request that supervisors account for all of their personnel and submit the names of unaccounted individuals and their suspected locations.

4. Instruct assembled personnel as to needed evacuation, evacuation routes, frisking-monitoring requirements, and accountability.

5. Provide a list of unaccounted individuals and their location to security within 20 minutes of the emergency declaration.

4.0 DEFINITIONS None Applicable 5.0 GENERAL.

The primaxy method of accounting for on-site personnel is by means of Assembly Area Leaders checking people against organization rosters. On back shifts, when few nonshift personnel may be present,. all personnel may be instructed to assemble at the Security Building (or other single location), rather then in separate assembly areas, to facilitate accountability.

During an assembly, Assembly Area Leaders check with those pexsonnel present to determine if personnel are missing, and provide this information to Security.

PEP-215 Rev. 0 Page 5 of 9

APR010 6.0 INITIATING CONDITIONS

1. The Site Emergency Coordinator has activated the site emergency organization (per PEP-321) including the Assembly Area Leader position.

2. 'An Alert, Site Emergency, or General Emergency has been declared.

7.0 PRECAUTIONS LIMITATIONS Initial accountability must be performed within 30 minutes of the declaration of an emergency. Therefore, information on unaccounted for personnel should be given to the Emergency Security Team Leader within 20 minutes or, if possible, sooner.

8.0 SPECIAL TOOLS AND E UIPMENT

1. Emergency Organization rosters

2. Public Address system, telephone system, bullhorns, and security/operations portable radios.

9.0 PROCEDURE STEPS Upon declaration of an Alert, Site Emergency, or General Emergency, report to your assigned Assembly Area and obtain a copy of the roster (which is maintained in the Assembly Area) which identifies which organizational groups report to that Assembly Area.

2. Announce to the assembling personnel that, you are assuming the position of Assembly Area Leader, and give them direction to perform accountability as per PEP-382.

3. After performing accountability, report the names and possible locations of missing personnel, if any, to the Emergency Security Team Leader.

NOTE: This report should be made within 20 minutes of the declaration of an emergency.

If any personnel were missing from your assembly area, request a volunteer, preferably a co-worker who, knows the missing individual, to serve on the Search and Rescue Team. Notify the'ogistic Support Director of the name of the volunteer, and direct the volunteer to report to the First Aid Team Leader in the Operational Support Center.

5. Maintain order in the assembly area, enlisting the assistance of any managers, supervisors, and/or foremen that are present as necessary.

PEP-215 Rev. 0 ~

Page 6 of 9

APR010 9.0 PROCEDURE STEPS

6. If directed to do so by the Logistics Support Director, restrict access to any foodstuffs in the assembly areas by appointing individuals to disable vending machines and/or guard refrigerators.

7. If an evacuation is ordered, relay instructions to the assembled personnel on what routes to follow and, if applicable, where monitoring and decontamination areas will be set up. Refer to Attachment 1 for routes to the CPSL Cape Fear plant and Cary District office if reassembly at remote areas has been directed. Direct the managers, supervisors and foremen to maintain control of the evacuating personnel. When all personnel have left your assembly area, report this fact to the Logistics Support Director, then evacuate yourself.

8. If reassembly at a remote area for radiological monitoring was directed subsequent to an evacuation, proceed to the remote area and assist in maintaining order and directing the flow of traffic and or personnel.

9. When the emergency is terminated, deliver the completed personnel accountability checklists to the Senior Specialist-Emergency Preparedness.

10. 0 DIAGELQiS ATTACRKNTS

1. Hap of Evacuation Routes to Remote Assembly Areas PEP"21S Rev. 0 Page 7 of 9

APRO10 MAPS OF EVACUATION BCVZES TO REMOTE ASSEMBLY AREAS

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APR009 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP"216 TITLE: DOSE PROJECTION TEAM LEADER REVISION 0 APPROVED:

Signature Da e TITLE:

PEP-216 Rev. 0 Page 1 of 7

APR009 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE

2.0 REFERENCES

4.

2.1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4 2.3 Other References 4 3.0 RESPONSIBILITIES 3.1 Reporting Responsibilities 4 3.2 Assignment and Relief of Position 4 3.3 Duties 4.0 DEFINITIONS 5 5.0 GENERAL 5 6.0 INITIATING CONDITIONS 5 7..0 PRECAUTIONS AND LIMITATIONS 5 8.0 SPECIAL TOOLS'ND EQUIPMENT 5 9.0 PROCEDURE STEPS 6 10.0 DIAGRAMS/ATTACHMENTS 7 PEP-216 Rev. 0 Page 2 of 7

APR009 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 thru 7 0 PEP-216 Rev. 0 Page 3 of 7

APR009 1.0 PURPOSE This procedure implements section 2.4.6.1 "Dose Projection Team Leader" and section 4.4.3 "Dose Projection" of the SHNPP Emergency Plan. It specifies actions to be performed by the Dose Projection Team Leader.

'I

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES 1 ~ Section 2.4.6.1, "Dose Projection Team Leader"

2. Section 4.4.3, "Dose Projection" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-302, "Communications Activities"

2. PEP-303, "Use of Communications Equipment"

3. PEP-321, "Notification of Emergency Personnel"

4. PEP-341, "Manual Dose Calculations"

5. PEP-342, "Automation of Dose Projection Procedures--ERFIS"

6. PEP-343, "Automation of Dose Projection Procedures--IBM II PC

7. PEP-405> "Preparation of Activity Logs" 2.3 OTHER REFERENCES

1. Plant Special Order, "Emergency Phone List" 3;0 RESPONSIBILITIES 3.1 REPORTING RESPONSIBILITIES The Dose Projection Team Leader reports to the Radiological Control Director in the Technical Support Center. He directs the activities of the Dose Projection Team.-

3.2 ASSIGiVEENT AND RELIEF OF POSITION An available on-shift Control Operator designated by the Site Emergency'oordinator initially assumes the responsibilities of Dose Projection Team Leader. He will be relieved by a Project Specialist

-Radiation Control, Specialist-Radiation Control, or Special-ist-ALM when one reports to the Technical Support Center.

3.3 DUTIES The Dose Projection Team Leader is responsible for:

1. Initiating and maintaining a record of Dose Projection Team activities.

2. Assigning personnel to perform source term and off-site dose projection calculations.

PEP-216 Rev. 0 Page 4 of 7

APR009 3.0 RESPONSIBILITIES 3.3 DUTIES (Cont'd)

3. Contacting the Corporate Meteorology Center or National Veather Service to obtain meteorological forecasts.

4. Monitoring source term and meteorology data used by the Emergency Response Facility Information System for reason-ableness and identifying any suspect parameters to the Radiological Control Director.

5. Ensuring the orderly transfer of the off-site dose projec-tion function to the Emergency Operations Facility upon its activation.

6. Performing radiological evaluations of available protec-tive actions for personnel, without emergency assignments in the on-site assembly areas.

7. Being formally relieved by an alternate trained for duty as a Dose Projection Team Leader.

8. Maintaining a record of activities.

4.0 DEFINITIONS None Applicable 5.0 GENERAL None Applicable 6.0 INITIATING CONDITIONS

1. The Shift Foreman has implemented PEP"101 and requires off-site dose projections to classify the emergency, or

2. The Shift Foreman has declared an Alert, Site Emergency, or General. /

7.0 PRECAUTIONS AND LIMITATIONS

l. All of the available methods for performing off-site dose projections provide for use of worst case default values for the radioiodine source term. Use of these default values will probably result in gross overestimation of the thyroid dose commitment, which could result in recommend-ing protective actions for the public that would later prove to be unnecessary.

2. Consistent with providing timely information to the Shift Foreman or Site Emergency Coordinator, dose projections should be based on isotopic analysis of a grab sample.

PEP-216 Rev. 0 Page 5 of T

APR009 8.0 SPECIAL TOOLS AND E UIPMENT None Applicable 9.0 PROCEDURE STEPS If relieving another .individual, review the activity log and obtain a briefing on the emergency and any previously performed dose projections.

2. Conduct all communications in accordance with PEP-302 and PEP-303.

3. Report arrival in the Technical Support Center to the Emergency Communicator-Technical Support Center (Emergency Communicator-Control Room if the Emergency Communicator

-Technical Support Center position is not yet manned), and inform the'Radiological Control Director (Site Emergency Coordinator if the Radiological Control Director position if is not yet manned) of the assumption of (or relieving, appropriate) responsibilities of the Dose Projection Team Leader.

Initiate and/or maintain a record of activities in accor-dance with PEP-405.

5. Assign Dose Projection Team- members to .perform off-site dose projections in. accordance with PEP-342, "Automation of Dose Projection - ERFIS", PEP-343, "Automation of Dose Projection - IBM PC", or PEP-341, "Manual Dose Calcu-lations" as- requested by the Radiological Control Direc-tor.

6. Obtain meteorological data from the corporate meteorology center or National Weather Service if the plant meteoro-logical system is inoperative. Consult the Plant Special Order, "Emergency Phone List", for phone numbers.

7'. Periodically monitor the raw data being used by the Emergency Response Facility Information System to calcu-late projected doses. If any parameters are suspect, enter substitute values and inform the Radiological Control Director.

8. Assist the Radiological Control Director in deciding what protective actions to recommend for on-site personnel by assigning, Dose Projection Team personnel'o calculate projected doses in shelters, emergency facilities, and plant areas, both with and without each combination of available protective actions.

9. Assign Dose Projection Team personnel to plot the plume on the map board in the Technical Support Center.

PEP<<216 Rev. 0 Page 6 of 7'

k

~ ~ APR009

' 9.0 PROCEDURE STEPS

10. When the Dose Assessment Team Leader in the Emergency Operations Facility reports that he is ready, brief him on the most current off-site dose projection status and the status of plant instrumentation that provides data used for dose projections. Inform the Radiological Control Director that the Emergency Operations Facility has assumed responsibility for off-site dose projections.

11. Continue to direct the Dose Projection Team in projecting off-site doses and compare these results with projections performed by the Dose Assessment Team. Keep the Radio-logical Control Director informed of the results of these projections and comparisons.

12. Continue to project dose rates and exposures in on-site shelters, emergency facilities, and plant areas, and keep the Radiological Control Director and Personnel Protection and Decontamination Team Leader informed of the results.

13. When the emergency is terminated, collect all records generated by the Dose Projection Team including activity log and deliver them to the Radiological Control Director.

14. When directed to do so., notify the alternate for your position specified by the radiological Control Director to arrange for relief at the end of the present shift in accordance with Section 9.2 of PEP-321. Notification messages shall be given only to the specified individual, and not to their spouse, children, babysitter, etc. If the specified alternate cannot be contacted, notify the Logistics Support Director.

10. 0 DIAGRAMS AT1'ACHMENTS None Applicable PEP-216 Rev. 0 Page 7 of 7

APR007 CAROLINA POWER 6 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE NUMBER: PEP-217 PROCEDURE TITLE: EMERGENCY COMMUNICATOR REVISION 0 APPROVED BY:

Signature Title PEP-217 Rev. 0 Page 1 of 18

APR007 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

2.1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4 3.0 RESPONSIBILITIES 3.1 Reporting Responsibilities 4 3.2 Assignment and Relief of Position 5 3.3 Duties 6 4.0 DEFl'NITIONS 7 5.0 GENERAL 8 6.0 INITIATING CONDITIONS 9 7.0 PRECAUTIONS AND LIMITATIONS 9 8.0 SPECIAL TOOLS AND EQUIPMENT 10 8.1 Control Room 10 8.2 Auxiliary Control Room (When Used) 10 8.3 Technical Support Center 10 8.4 Emergency Operations Facility 11 9.0 PROCEDURE STEPS 11 9.1 General 11 9.2 Emergency Communicator-Control Room 12 9.3 Emergency Communication Staff in the Technical Support Center 9.4 Emergency Communica'tion Staff in the Emergency Operations Facility 16 9.5 Emergency Response Facility Information System Console Operators 18 9.6 Logkeepers 18

10. 0 DIAGRAMS/ATTACHMENTS 18 PEP"217 Rev. 0 Page 2 of 18

APR007 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 thru 18 0 PEP-217 Rev. 0 Page 3 of 18

APR007 1.0 PURPOSE The purpose of this procedure is to implement Section 2.4.7, "Emergency Communicator" and Section 4.2 "Notification" of the SHNPP Emergency Plan.

This procedure describes the actions of the Emergency Communicator and his staff during an Unusual Event, Alert, Site Emergency or General Emergency.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 2,4.7, "Emergency Communicator"

2. Section 4.2, "Notification" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-102, "Site Emergency Coordinator - Control Room"

2. PEP-103, "Site Emergency Coordinator - Technical Support Center"

3. PEP-301, "Notification and Communications"

.4. PEP-302, "Communication Activities"

5. PEP-303, "Use of Communications Equipment"

6. PEP-321, "Notification of Emergency Personnel"

7. PEP-322, "Mobilization of Outside Organizations"

8. PEP"323, "Setup and Operation of Emergency Facilities"

9. PEP-403, "Performance of Training"

.10, PEP-405, "Preparation of Activity Logs" 3.0 RESPONSIBILITIES 3.1 REPORTING RESPONSIBILITIES 3.1.1 Emer enc Communicator - Control Room The Emergency Communicator in the Control Room reports to the Site Emergency Coordinator in the Control Room. When the Technical Support Center is activated, the Emergency Communicator

- Control Room still reports to the same individual who has now reverted to Operations Leader.

PEP-217 Rev. 0 Page 4 of 18

APR007 3.0 RESPONSIBILITIES 3.1 REPORTING RESPONSIBILITIES (Cont'd) 3.1.2 Emer enc Communication Staff in the Technical Su ort Center The Emergency Communicator in the Technical Support Center reports to the Site Emergency Coordinator in the Technical Support Center.

The phone talkers, plotter, and Emergency Response Facility Information System console operators in the Technical Support Center report to the Emergency Communicator - Technical Support Center.

3.1.3 Emer enc Communicator Staff in the Emer enc 0 erations pacilic The Emergency Communicator in the Emergency Operations Facility reports to the Emergency Response Manager in the Emergency Operations Facility. The phone talkers, plotter and Emergency Response Facility Information System console operator in the Emergency Operations Facility report to the Emergency Communicator-Emergency Operations Facility.

3.2 ASSIGi%EENT AND RELIEF OF POSITION 3.2.1 Emer enc Communicator - Control Room The on shift person who is assigned to this position by the Site Emergency Coordinator - Control Room is normally an available auxiliary operator, but it could be any person trained according to PEP-403 who is immediately available to perform this position.

3.2.2 Emer enc Communications Staff in the Technical Su ozt Center 3.2.2.1. The primary person "assigned to the position of Emergency Communicator is the Director - Regulatory Compliance 3.2.2.2. If the Dir'ector - Regulatory Compliance is unavailable, the position is filled by one of the designated alternates who are:

1. Regulatory Compliance - Senior Specialist a

'2. Regulatory Compliance - Specialist 3.2.2.3. The positions of Phone Talker - Operations is filled by an available member of the operations staff designated by the Plant Operations Director.

PEP-217 Rev. 0 Page 5 of 18

APR007

3. 0 RESPONSIBILITIES 3.2 ASSIGNMENT AND RELIEF OF POSITION (Cont'd) 3.2.2 Emer enc Communications Staff in the Technical Su ort 3.2'.2,4, The positions of Phone Talker Off-Site, Status Board Plotter, Emergency Response Facility Information System Console Operator, and Logkeepers are filled by predesignated personnel who have been trained in accordance with PEP-403.

3.2.3 Emer enc Communications Staff in the Emer enc Operations

~Fati1 it 3.2.3.1. The primary person assigned to the position of Emergency Communicator - Emergency Operations Facility is the Director - Nuclear Safety Review.

3.2.3,2. If the primary person assigned to the position is unavailable, the position is filled by one of the designated alternates who are:

1. Manager - Planning and Scheduling

2. Principal Mechanical Engineer 3.2.3.3. The positions of Phone Talker Off-Site, Status Board Plotter, Emergency Response Facility Information System Console Operator, and Logkeepers are filled by predesignated personnel who have been trained in accordance with PEP-403.

3.3 DUTIES 3.3.1 Emer enc Communicator - Control Room The Emergency Communicator in the Control Room acts as the liaison between the on-site emergency response organization and off-site emergency personnel and agencies. He is responsible for performing the initial notifications of local and state authorities and the Nuclear Regulatory Commission. He also requests assistance from local emergency response organizations and may call on emergency personnel if the emergency occurs during off hours. When the Technical Support Center is activated and the Emergency Communicator

- Technical Support Center is briefed, the functions of the Emergency Communicator - Control Room changes to providing communications (up-to-date data and event logs) to the Phone Talker

- Operations in the Technical Support Center.

PEP-217 Rev. 0 Page 6 of 18

APR007 3.0 RESPONSIBILITIES 3,3 DUTIES (Cont'd) 3.3.2 Emer enc Communication Staff in the Technical Su ort Center and the Emer enc 0 erations Facilit

1. The Emergency Communicator - Technical Support Center supervises the communications staff in the Technical Support Center,and acts as liason for the Site Emergency Coordinator between the Technical Support Center and the Control Room and the off-site authorities (county, state and Nuclear Regulatory Commission) ~ When the Emergency Operations Facility is activated, the Emergency Communicator - Emergency Operations Facility has the responsibility for communicating with the off-site authorities and acts as liaison for the Emergency Response Manager between the'echnical'upport Center, off-site agencies, and the Corporate Emergency Operating Center.

2. The Status Board Plotters keep current plant status information posted on status boards.

3. The Phone Talker - Operations records plant status information received from the Emergency Communicator

- Control Room and gives this information to the Status Board Plotter for posting. He also obtains answers from the Emergency Communicator - Control Room to questions he has asked for the emergency directors.

4. The Phone Talkers - Off-Site perform notifications for the Site Emergency Coordinator. (or Emergency Response Manager when the Emergency Operations Facility is activated) to off-site authorities and the Nuclear Regulatory Commission. The Phone Talkers

- Off-Site also record requests by off-site authorities and the Nuclear Regulatory Commission for information (which are given to the Emergency Communicator) and relay the responses (from the facility staff) to the originator.

5, Emergency Communicators are formally relieved by alternates trained for duty as Emergency Communicators.

6. Emergency Communicators maintain a record of activities.

4.0 DEFINITIONS None Applicable PEP-217 Rev. 0 Page 7 of 18

APR007 5.0 GENERAL

5. 1. Control Room Initially an on-shift individual is appointed by the Site Emergency Coordinator Control Room (Shift Foreman) as the Emergency Communicator in the Control Room. He communicates with the off site authorities (county, state, and Nuclear Regulatory Commission) to perform initial notifications of the emergency, with the plant emergency response organization (during off-hours),to call them in, and with local immediate response organizations (fire, rescue, hospital, etc.) if their assistance is needed.

Once the Technical Support Center is activated, the Emergency Communicator - Control Room no longer communicates with off-site authorities (as liaison for the Site Emergency Coordinator) since the function of Site Emergency Coordinator switches to the Technical Support Center at this time. The main function of the Emergency Communicator - Control Room at this time is to maintain verbal communications with the Phone Talker " Operations located in the Technical Support Center. The Emergency Communicator - Control Room assures plant data flow to the Technical Support Center either through computer systems or, as a back-up, by telephone.

5.2. Technical Su ort Center After activation of the Technical Support Center and a briefing by the Emergency Communicator - Control Room, the Emergency Communicator in the Technical Support Center assumes responsibility for communication with off-site authorities as the liaison for the Site Emergency Coordinator - Technical Support Center. The Emergency Communicator - Technical Support Center supervises a communications staff composed of:

1. One Phone Talker - Operations

2. One Status Board Plotter

3. Two or more Phone Talkers - Off-Site

4. One Emergency Response Facility Information System Console Operator The Status Board Plotter in the Technical Support Center receives System Parameter and Data Status sheets filled out by the Phone Talker - Operations (who is in communica-tions with the Control Room) or information from the Emergency Response Facility Information System Console Operator. As he posts this information on the Status Boards, he relays the information via a Telephone headset to the Emergency Operations Facility and Corporate Emergency Operations Center plotters (if these facilities are activated) so that all three sets of status boards are current.

PEP-217 Rev. 0 Page 8 of 18

APR007 5.0 GENERAL 5.2. Technical Su ort Center (Cont'd)

The two Phone Talkers - Off-Site who have Automatic Ringdown phones to the Nuclear Regulatory Commissien, State and counties, perform follow up notifications to the off-site authorities using prepared and approved messages.

This function terminates shortly after the activation of the Emergency Operations Facility, and the briefing of the Phone Talkers and the Emergency Communicator in the Emergency Operations Facility.

5.9. Emer enc 0 erations Facilit After activation of the Emergency Operations Facility and a briefing by the Emergency Communicator - Technical Support Center, the Emergency Communicator in the Emergency Operations Facility assumes responsibility for communication with off-site authorities as liaison for the Emergency Response Manager. The Emergency Communicator-Emergency Operations Facility supervises a communications staff composed of:

l. One Status Board Plotter

2. Two (or more) Phone Talkers - Off-Site

3. One (or more) Emergency Response Facility Information System Console Operator The Status Board Plotter in the Emergency Operations Facility receives -Emergency Response Facility Information System information via the console operator and/or System Parameter and Data Status Sheet information via his headphones from the Status Board Plotter in the Technical Support Center. He posts this information on the status board.

The two Phone Talkers - Off-Site, who have Automatic Ringdown phones to the Nuclear Regulatory Commission, State and counties, perform follow up notifications to the off-site authorities using prepared messages approved by the Emergency Response Manager.

6. 0 INITIATING CONDITIONS The Site Emergency Coordinator declares an .emergency and appoints an Emergency Communicator as per PEP-102.

7.0 PRECAUTIONS AND LIMITATIONS From the time the emergence was declared the Emergency Communicator must notify the five off-site agencies (county and State warning points) within 15 minutes and the Nuclear Regulatory Commission within one hour.

PEP"217 Rev. 0 Page 9 of 18

APR007 7.0 PRECAUTIONS AND LIMITATIONS

2. Whenever the emergency classification is changed, the Emergency Communicator must notify the off-site agencies and the Nuclear Regulatory Commission within 15 minutes.

8.0 SPECIAL TOOLS AND E UIPMENT 8.1 CONTROL ROOM 8.1.1. Automatic Ringdown phones for:

1 ~ Nuclear Regulatory Commission Emergency Notification System Nuclear Regulatory Commission Health Physics Network County and State warning points Technical Support Center (to the Plant Operations Director) 8.1.2. Three 10 button phones on control boards 8.1.3. Two 20 button desk phones in control room area 8.1.4. One 20 button desk phone in Shift Foreman's office 8.1.5. One radio remote for environmental monitoring radios 8 . 1 . 6.. One radio master console for site radio systems F

8.1.7. Sound powered communications system 8.2 AUXILIARY CONTROL ROOM (WHEN USED) 8.2.1 Automat ic Ringdown phones for:

Nuclear Regulatory Commission Emergency Notification System

2. County and State Warning Points

3. Technical Support Center to the Plant Operations Director 8.2.2 Two multibutton wall phones 8.3 TECHNICAL SUPPORT CENTER 8.3.1.Automatic Ringdown phones for:

Nuclear Regulatory Commission Emergency Notification System

2. Nuclear Regulatory Commission Health Physics network

3. County and State warning points

4. Control Room to the Plant Opertions Leader

5. Emergency Operations Facility to the Emergency PEP-217 Rev. 0 Page 10 of 18

APR007 8.0 SPECIAL TOOLS AND E UIPMENT 8.3 TECHNICAL SUPPORT CENTER (Cont'd)

Communicator

6. Site Emergency Coordinator to Emergency Response Manager 8.3.2 Three 10 button desk phones for phone talkers 8,3.3 One 20 button desk phone for Emergency Communicator NOTE: Radio systems are available elsewhere in the Technical Support Center.

8.4 EMERGENCY OPERATIONS FACILITY 8.4.1 Automatic Ringdown phones for:

r

1. Nuclear Regulatory Commission Emergency Notification System

. 2. Nuclear Regulatory Commission Health Physics Network

3. County and State warning points

4. Technical Support Center Emergency Communicator

5. Plant, Media Center(Emergency Response Manager to Site Public Information Coordinator)

6. Emergency Response Manager to Site Emergency Coordinator

7. Emergency Response Manager to State Emergency Response Team 8.4.2 Three 10 button desk phones for phone talkers 8.4.3 One 20 button desk phone for Emergency Communicator NOTE: Radio systems are available elsewhere in the Emergency Operations Facility.

9.0 PROCEDURE STEPS 9.1 GENERAL

l. Initiate an Emergency Communicators Log. Maintain this log per PEP-405 until the emergency is terminated or you are relieved.

2. Report your readiness to the Site Coordinator (or Emergency Response Manager if Emergency located in the Emergency Operations Facility).

3. Maintain copies of all forms used,, and messages received and sent.

PEP-217 Rev. 0 Page 11 of 18

APR007 9.0 PROCEDURE STEPS

9. 1 GENERAL

4. Ensure proper use of communications equipment per PEP-303.

5. When relinquishing the role of Emergency Communicator brief your successor on the status of the emergency and communication activities. When directed to do so, notify the alternate for your position specified by the Site Emergency Coordinator (Technical Support Center) or Emergency Response Manager (Emergency Operating Facility) to arrange for relief at the end of the present shift in accordance with Section 9.2 of PEP-321. Notification messages shall be given only to the specified individual, and not to their spouse, children, babysitter, etc. If the specified alternate cannot be contacted, inform the Logistics Support Director.

9.2 EMERGENCY CORHJNICATOR - CONTROL ROOM The following steps may be performed out of order if necessary.

Selected steps may be omitted if previously performed or if not pertinent, or performed by an assistant at the discretion of the Site Emergency Coordinator or Emergency Communicator.

1. Notify the necessary members of the On-Site Emergency

Response Organisation designated by the Site Emergency Coordinator according to PEP-321. (Normally, Attachment 1 to PEP-321 is filled out and approved. by the Site Emergency Coordinator).

2. Contact any immediate. response organizations requested by the Site Emergency Coordinator as per PEP-301. (Normally, Attachment 1 to PEP-301 is filled out by the Emergency Communicator at the the direction of the Site Emergency Coordinator, and approved by the Site Emergency Coordinator.)

3. Obtain an approved copy of Part I of the North Carolina Emergency Notification Form (Attachment 2 to PEP-301) from the Site Emergency Coordinator and contact the five primary off-site emergency response agencies warning points as per PEP-301.

NOTE: This contact must be initiated within 15 minutes of the declaration of the emergency.

4. Notify Nuclear Regulatory Commission headquarters (Headquarters Operations Office) as per PEP-301.

PEP-217 Rev. 0 Page 12 of 18

APR007 9.0 PROCEDURE STEPS 9.2 EMERGENCY COMMUNICATOR - CONTROI ROOM (Cont'd)

NOTE: Contact of the Nuclear Regulatory Commission Headquarters must be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the declaration of the emergency. 1 Obtain an approved copy of Part II of the North Carolina Emergency Notification Form (Attachment 2 to PEP 301) from the Site Emergency Coordinator. After the Emergency Operating Center for the counties and State are manned, transmit the infoxmation in Part II to the Emergency Operating Centers.

6. Obtain an approved copy of Part II of the Nuclear Regulatory Commission Incident Notification Form (Attachment 3 to PEP-301) from the Site Emergency Coordinator and notify the Nuclear Regulatory Commission Headquarters Operations Offices as per PEP-301.

7. Record on a message form (see PEP-302) any detailed questions or questions that cannot be answered immediately. Obtain the answer from the appropriate person and notify the questioner of the response as time permits.

8. If the Emergency Communicator-Technical Support Center comes to the Control Room, brief him as to the present status of the emergency and message traffic. When he arrives at the Technical Support Center, brief him on any pertinent events that have occuxred while he was in transit, or, if he did not come to the Control Room for a full face-to-face briefing, give him a briefing, after which the Emergency Communicator - Technical Support Center will assume responsibility for off-site communication.

9. After activation of the Technical Support Center, the Emergency Communicator - Control Room establishes commu-nication with the Phone Talker - Operations in the Technical Support Center.

10. If the Emergency Response Facility Information System is not'operational, the Emergency Communicator - Control Room transmits information to the Phone Talker - Operations in the Technical Support Center on a regulax basis (using System Parameter and Data Status sheets) and on as needed basis in response to questions (using message forms if needed).

PEP-217 Rev. 0 Page 13 of 18

APR007 9.0 PROCEDURE STEPS 9.2 EMERGENCY COMMUNICATOR - CONTROL ROOM (Cont'd)

The Emergency Communicator - Control Room briefs the person assuming his position when he is relieved and logs out in the Emergency Communicator - Control Room Logbook.

9.3 EMERGENCY COMMUNICATION STAFF IN THE TECHNICAL SUPPORT CE~i R 9.3.1 The Emergency Communicator - Technical Support Center, may go to the Control Room and obtain a briefing from the Emergency Communicator - Control Room, or may go directly to the Technical Support Center and be briefed by telephone.

9.3.2 The Emergency Communicator - Technical Support Center verifies that his staff is present:

1. One Phone Talker - Operations 2, One Status Board Plotter

3. Two (or more) Phone Talkers - Off-Site

4. One (or more) Emergency Response Facility Information System Console Operators

5. Two Logkeepers (one each for Site Emergency Coordinator and Radiological Control Director) 9.3.3 The Emergency Communicator - Technical Support Center accounts for all personnel in the Technical Support Center and provides a list of missing persons to the Emergency Security Team Leader within 25 minutes of the declaration of an Alert, Site Emergency, or General Emergency.

9.3.4 The Emergency Communicator - Technical Support Center has his staff set up their equipment and areas and perform a communications check to verify they are ready. He then calls the Emergency Communicator - Control Room to be briefed on events that have occurred since his face-to-face briefing, if one occured, or obtains a complete briefing.

9.3.5 The Emergency Communicator - Technical Support Center briefs the remainder of his staff as necessary and notifies the Site Emergency Coordinator - Technical Support Center that he is, ready to take .over communica-tions, 9.3.6 The Emergency Communicator - Technical Support Center.

instructs the Phone Talker - Operations to notify the Emergency Communicator - Control Room that the Technical Support Center"is taking over communications with off-site authorities.

PEP-217 Rev. 0 Page 14 of 18

APR007 9,0 PROCEDURE STEPS 9.3 EMERGENCY COEIUNICATION STAFF IN THE TECHNICAL SUPPORT CENTER (Cont'd) 1 9.3.7 The Emergency Communicator - Technical Support, Center obtains approved messages from the Site Emergency Coordinator and transmittal.

provides them to the Phone Talkers Of f-s ite for 9.3.8 Questions received by the Phone Talkers - Off-Site are recorded on message forms (PEP-302) which the Emergency Communicator - Technical Support Center picks up and delivers to the appxopriate person for response.

9.3.9 The Emergency Communicator - Technical Support Center obtains the message response, has it approved by the Site Emergency Coordinator - Technical Support Center and gives it to the Phone Talker - Off-Site for transmittal to the originator.

9.3.10 When information from the Control Room is requested by a director, the Emergency Communicator - Technical Support Center gives the request (verbally or in writing) to the Phone Talker - Operations and instructs him to request the information fxom the Emergency Communicator - Control Room. Vhen the response is obtained by the Phone Talker "

Operations, the Emergency Communicator - Technical Support Center gives the information to the director.

9.3. 11 'heassures Emergency Communicator - Technical Support Center also that information from the Emergency Response Facility Information System Console Operator is provided to the Status Board Plotter.

9.3. 12 The Emergency Communicator - Technical Support Center arranges for relief of his personnel as needed.

9 ~ 3. 13 If the Emergency Communicatox - Emergency Operations Facility arrives at the Technical Support Center, the Emergency Communicator - Technical Support Center briefs the Emergency Communicator - Emergency Operations Facility as to the present status of the emexgency, and message traffic.

NOTE: When the Site Emergency Coordinator - Technical Support Center announces that the Emeigency Operations Facility is activated, the Emergency Communicator - Emergency Operations Facility assumes responsibility for off-site communication.

PEP-217 Rev. 0 , Page 1S of 18

APR007

~ ~

9.0 PROCEDURE STEPS 9.3 EMERGENCY COMMUNICATION STAFF IN THE TECHNICAI SUPPORT CENTER (Cont'd)

The Emergency Communicator - Technical Support Center

,'i 9.3.14 briefs the person assuming his position when he is relieved and logs out in the Emergency Communicator-Technical Support Center Logbook.

9.4 EMERGENCY COMMUNICATION STAFF IN THE EMERGENCY OPERATIONS FACILITY 9.4. 1. The Emergency Communicator - Emergency Operations Facility may report to the Technical Support Center to obtain a face-to-face briefing from the Emergency Communicator - Technical Support Center. He then goes to the Emergency Operations Facility.

9.4.2. The Emergency Communicator - Emergency Operations Facility verifies that his staff is present:

1. One Status Board Plotter

2. Two (or gore) Phone Talkers - Off-Site

3. One (or more) Emergency Response Facility Information System Console Operators Three Logkeepers (one for Emergency Response Manager, Technical Analysis Manager, Radiological Control Manager) 9.4.3. The Emergency Communicator - Emergency Operations Facility has his staff set up their equipment and areas and perform a communications check to verify they aze ready.

9.4.4. The Emergency Communicator - Emergency Operations Facility instructs the Status Board Plotter to obtain the most current information from the Status Board Plottez-Technical Support Center and post it on the Status Board.

9.4.5. The Emergency Communicator - Emergency Operations Facility, with the Phone Talkers -- Off-Site on extensions, calls the Emergency Communicator Technical Support Center and receives an update on events that have occurred since the face-to-face briefing, if one occured, or obtains a complete briefing.

9.4.6. The Emergency Communicator - Emergency Operations Facility briefs the remainder of his staff.

PEP-217 Rev. 0 Page 16 of 18

APR007 A ~

9.0 PROCEDURE STEPS

. 9.4 EMERGENCY COISSNICATION STAFF IN THE EMERGENCY OPERATIONS FACILITY (Cont'd) 9.4.7. After the briefing and posting has been completed, the Emergency Communicator - Emergency Operations Facility notifies the Emergency Response Manager that he is ready to take over off-site Communications.

9.4.8. When the Emergency Response Manager announces the Emergency Operations Facility is activated, the Emergency Communicator - Emergency Operations Facility instructs the Status Board Plotter to notify the Emergency Communicator

- Technical Support Center that the Emergency Operations Facility is activated and that the Emergency Operations Facility is taking'ver communications with the off-site authorities.

9.4.9. The Emergency Communicator - Emergency Operations Facility obtains approved messages from the Emergency Response Manager and provides them to the Phone Talkers Off-Site for transmittal.

9.4.10. Questions received by the Phone Talkers - Off-Site are recorded on message forms (PEP-302) which the Emergency Communicator - Emergency Operations Facility picks up and delivers to the appropriate person for response.

9.4.11. The Emergency Communicator - Emergency Operations Facility'btains the message response, has it approved by the Emergency Response Manager and gives it to the Phone Talker - Off-Site for transmittal.

9. 4. 12'. When information from the Control Room or Technical Support Center is requested by a Manager, the Emergency Communicator - Emezgency Operations Facility gives the request (verbally or in writing) to the Status Board Plotter or one of the Phone Talkers and instructs him to request the information from the Emergency Communicator-Technical Support Center. When the response is obtained, the Emergency Communicator - Emergency Operations Facility gives the information to the Manager.

9.4.13. , The Emergency Communicator - Emergency also obtains information from the Emergency Operations'acilit'y Response Facility Information System Console Operator and provides it to the Status Board Plotter.

PEP"217 Rev. 0 Page 17 of 18

APRO07 9.0 PROCEDURE STEPS 9.4 EMERGENCY COMMUNICATION 'STAFF IN THE EMERGENCY OPERATIONS FACILITY (Cont'd) 9.4.14. The Emergency Communicator - Emergency Operations Facility'arranges for relief of his personnel as needed.

9.4.15. The Emergency Communicator - Emergency Operations Facility briefs the person assuming his position when he is relieved and logs out in the Emergency Communicator-Emergency Operations Facility Logbook.

9.5 EMERGENCY RESPONSE FACILITY INFORfATION SYSTEM CONSOLE OPERATORS

1. Emergency Response Facility Information System Console Operators operate the console to provide information requested by the Site Emergency Coordinator or Emergency Response Manager (depending on the facility.)

2. The console screen is displayed also on the overhead display monitor.

9.6 LOGKEEPERS

1. Logkeepers respond to directions from the individual (director or manager) for whom they are keeping the log (Site Emergency Coordinator, Radiological Control Director, Emergency Response Manager, Radiological Control Manager or Technical- Analysis Manager).

2. They record important items or events in the logbook as per PEP-405 They assist the director or manager in preparation of messages and/or response to questions.

10.0 DIAGRAMS ATTACHMENTS None applicable PEP-217 Rev. 0 Page 18 of 18

APR011 CAROLINA POMiR e LIGHT COMPANY SHEARON HARRIS NUCLEAR POMER PLANT PLANT OPERATING ~AL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

'UMBER:

PEP-218 TITLE: ACCIDENT ASSESSMiÃT TM LMER REVISION 0

'i '

S jgnacure Dace TITLE:

PEP-218 Rev. 0 Page 1 o5 6

APR011 OF CONI NTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4 2.0 ~~sZENCES 4

2. 1 Emergency Plan Ref erences 4 2.2 Referenced Plant Emergency Procedures 4 2.3 Other Referenced Plant Procedures 4 3.0 RESPONSIBILITIES 4

3. 1 Repommg Responsibilities 4 3!2 Assignment and Relief of Position 4 P

~ ~

3.3 Duties 5 4.0 DEFINITIONS 5 5.0 GENERAL 5 6.0 INITIATING CONDITIONS 5 7.0 PRECAUTIONS AND LIMITATIONS 5 8.0 SPECIAL TOOLS AND EQUIPMENT 5 9.0 PROCEDURE STEPS 6

10. 0 DIAGRAMS/ATTACHMENTS 6 PEP-218 Rev. 0 Page 2 of 6

APR011 LEST OF EFFECTIVE PAGES

~Pa e Revision 1 through 6 Q$

~

'7

~

'EP-218 Rev. 0 Page 3 of 6

APR011 1.0 PU)PQ)E The purpose of this procedure is to implement Section 2.4.3.1, "Accident Assessment Team Leader," of the SHNPP Emergency Plan. It specifies ac ions to be taken by the Accident Assessment Team Leader.

2.0 REFERENCES

2. 1 EKRGENCY PLAN REFERENCES Section 2.4.3.1) "Accident Assessment Team Leader II

2. Section 4.4.1, "Evaluation of Plant Conditions" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-101) "Emergency Classi ication" 2~ PEP-302) "Communicitions Activities" 3~ PEP-303) "Use of Communications Equipment"

4. PEP-321, "Notification of Emergency Personnel"

5. PEP-362, "Intezpretation of Liquid and Gas Samples"

6. PEP-405) "Preparation of Activizy Logs" 2.3 OX'EFERENCED PLANT PROCEDURES

1. AP-005, "Procedure Format and Preparation"

2. AP-007) "Temporary Procedure Revision Review and Approval" 3.0 RESPONSIBILITIES 3.1 REPORTING RESPONSIBILITIES The Accident Assessment Team Leadez reports to the Plant Operations Director in the Technical Support Centez.

2~ Accident Assessment Team personnel report to the Accident Assessment Team Leadez.

3.2 ASSIGRKNT AND RELLY OF POSITION The on-shift Shift Technical Adv'sor zepor s to the Control Room and assumes the zesponsibil'ties of Accident Assessment Team Leader.

When the Technical Support Center is activated, a Princi-pal Engineer--Operations, Project Engineer--NSSS, oz Projec- Engineer-Performance will relieve the Shift Technical Advisor as Accident Assessment Team Leader. The Shift Technical Adv'sor will remain in the Control Room and assis" the Operat'ons Leader in evaluating indications on the control boards.

PEP-218 Rev. 0 Page 4 of 6

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APRO11

3. 0 RESPONSIBILITIES

3. 3 DUTIES The Accident Assessment Team Leader is responsible for:

1. Initiating and maintaining a record of Accident Assessment.

Team activities.

2. Monitoring and evaluating plant parameters during an emergency to determine the overall condition of plant systems, the core, and fission produc" barriers.

3. Monitoring emergency conditions for changes in Emergency Ac ion Levels, and making recommendations to the Plant Operations Director when such cond'tions indicate that the emergency classification should be changed.

4. Developing special operating procedu"es if needed to reduce the consequences of an emergency condi ion.

5. ~ Supervising the Accident Assessment Team.

6. Be formally relieved by an alternate trained for duty as an Accident Assessment Team Leader.

4. 0 DEEINITIONS None Applicable

5. 0 GENEEZ In some instances, the Emergency Action Levels used for classi ying emergencies cannot be direct)y related to a specific reading on a specific instrument. In other cases, the specified instrumentation may be inoperable or obviously malfunctioning. The Accident, Assess-ment Team will assist in evaluating plant conditions to ensure that sufficient information is available for the Site Emergency Coordina-tor to properly classify the accident.

6.0 INITIATING CONDITIONS An emergency has been declared by the Site Emergency Coordinator, and the Accident Assessment Team has been activated.

7.0 PRECAUTIONS/LIMITATIONS

1. Ensure that Accident Assessment Team personnel do not Leave the Technical Suppor- Center w'thout first. consult-ing the Personnel Protection and Decontamination Team Leader to determine protect'on requirements.

8.0 SPECIAL TOOLS AND E UIP ~

None Applicable PEP-218 Rev. 0 Page 5 of 6

APR011 9.0 PROCEDURE STEPS If you are relieving another individual, obtain a briefing on the emergency and actions that. have been completed oz are in progress.

2. Conduc all communications ac ivities in accordance with PEP-302 and PEP 303.

3. Report arzival in the Technical Support Center to the Emergency Communicator-Technical Support, Cence" {Emergency Communicator-Contzol Room if the Emergency Communicator-Technical Support Center is not yet manned), and inform the Plant Opeiations Director that you are assuming (oz relieving, if appropz'te) the position of Accident Assessment Team Leader.

4, Initiate and maintain a record of you" activities and the activities of the Accident Assessment Team in accordance with PEP-405.

5. Direct Accident Assessment Team personnel to continuously monitor plant parameters and system status indicators, and to evaluate those parameters and indicators against Emezgency Action Level criteria in accozdance with PEP-101. Keep the Plant Operations Director informed of significant changes in plant status and recommend changes in the emergency classification when so indicated.

6. When sample analysis data is available fzom the Plant Monitoring Teen, di ec Accident Assessment Team personnel to estimate core damage in accordance with PEP-362.

7. When requested by the Plant Operations Director, dizec Accident Assessment Team personnel to develop or revise procedures as necess~ to mitigate plant damage in accordance with AP-005 and/or hP-007.

8. When requested by the Plant Operations Directoz,di"ect Accident Assessment Team personnel to pezform calculations to aid in predicting the continued safety of the plant or to estimate the point at which degradation in safety might occur>>

9. When directed to do so, notify the alterna e for your position specified by the Plant Operations Director to arrange for relief at the end of the present shift in accordance with Section 9.2 of PEP-321. Not'fication messages shall be given only to the specified ind'vidual, and not to thef spouse, children, babysitter,etc.

10. If assistance is needed from the Nuclea>>>> Steam Supply

. System supplier, Architect/Engineer, or othe" contractors, inform the Plant Operations Di=ectoz.

10.0 DIAGRAMS/ATTACHMENTS None Applicable PEP-218 Rev. 0 Page 6 of 6

APR014 CAROLINA POWER" &. LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-302 TITLE: COMMUNICATIONS ACVIVITIES REVISION 0 APPROVED:

Signature Da e TITLE:

PEP-302 Rev. 0 Page 1 of 18

APR014 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3

'1.0 PURPOSE 4

2.0 REFERENCES

2.1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4, 3.0 RESPONSIBILITIES 4 3.1 Emergency Communicator 4 3.2 All Personnel 4 4.0 DEFINITIONS 4 5.0 GENERAL 4 6.0 INITIATING CONDITIONS 4 7.0 PRECAUTIONS AND LIMITATIONS 5 8.0 SPECIAL TOOLS AND EQUIPMENT 5 9.0 PROCEDURE STEPS 5 9.1 Communications Protocol 5 9.2 Use of Message Forms 5 9.3 Transmittal of Plant Parameter Data by Telephone 6 10.0 DIAGRAMS/ATTACHMENTS 6 PEP-302 Rev. 0 Page 2 of 18

APR014 LIST'OF, EFFECTIVE..PAGES .

~Pa e Revision 1 thru 18 0 PEP-302 Rev. 0 Page 3 of 18

APR014 1.0 PURPOSE This procedure implements Section 4.2, Notif'fication" of the SHNPP Emergency Plan. It specifies methods and priorities for communica-tions activities.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 3.8, "Communications Systems"

2. Section 4.2I "Notification"

2. 2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-217, "Emergency Communicator" It

2. PEP-301, "Notifications and Communications

3. PEP-303, "Use of Communications Equipment tt II

4. PEP-321, "Notification of Emergency Personnel

'It 5., PEP-322, "Mobilization of Outside Organxzatxons ~

3.0 RESPONSIBILITIES 3.1 EMERGENCY COMMUNICATOR The Emergency Communicator is responsible for documenting message traffic.

3.2 ALL PERSONNEL All emergency organization personnel are rres p onsible for observing emergency communications priorities.

4.0 DEFINITIONS None Applicable 5.0 GENERAL it f The comp 1 ex y o available communications links dictates that a'labiliti use of these systems be preplanned to maximize the avax a y of communications systems at each location.

6.0 INITIATING CONDITIONS The Site Emergency Coordinator has declared an emergency.

PEP-302 Rev. 0 Page 4 of 18

APR014 7".0 PRECAUTIONS AND LIMITATIONS None Applicable 8.0 SPECIAL TOOLS AND E UIPMENT None Applicable 9.0 PROCEDURE STEPS 9.1 COMMUNICATIONS PROTOCOL

1. All personnel will use Attachment 3 as a guide to select-the type of communications equipment to be used for contacting another individual in the. emergency organiza-.

tion.

2. If your specific communications application (person to person) is listed on Attachment 3, select the first, second, or third method listed in the "USE" column in that order of preference.

3. If your specific application is not listed, select the first, second, or third method, in that order of commu-preference, for the general (facility to facility) nications application, at all, or if none of If your application is not listed use the listed methods are available, any other method that is available. If necessary, request assistance from the Site. Communications Systems Coordinator via the Logistics Support Director.

9.2 USE OF MESSAGE FORMS (See Attachment 2 for an example)

The person receiving or originating information or a request for information or action will record the message or request on the upper portion of a message form, and enter the date and time in the "date" block. They will print .the title of the addressee on the "to" to" line and the title of the originator on the "Please reply originator.

line, then print their name next to the title of the He will then remove and retain the pink copy, and deliver the original to the addressee.

2. The addressee will respond to requested information or actions by entering his reply in the lower section of the message form. He will then sign at the bottom and enter the date and time. If the response action involves contact with an outside agency, the addressee will obtain concurrence from the Site Emergency Coordinator by obtain-ing his countersignature at the bottom of the message form. The addressee will then detach and retain the yellow copy of the message form and return the original to the originator or Emergency Communicator.

PEP-302 Rev. 0 Page 5 of 18

APR014 9.0 PROCEDURE STEPS 9.2 USE OF MESSAGE FORMS (Cont'd)

3. The originator or Emergency Communicator will take action as directed in the addressee's response, retain the original copy of the message form, and discard the pink copy.

9.3 TRANSMITTAL OF PLANT PARAMETER DATA BY TELEPHONE

1. The Shift Technical Advisor, in the Control Room will fill out all or part of Attachment 1, "Safety Parameter Data and Status Information 'Form". Only those parameters that, have changed significantly since the last form was filled out should be listed, and all other parameters will normally be left blank. He will give the form to the Emergency Communicator - Control Room.

2. The Emergency Communicator - Control Room will establish communications with the Status Board Plotter(s) in the Technical Support Center and (if activated) the Emergency Operations Facility', and verbally transmit the data on the form to those locations.

3. The Status Board Plotter(s) will transcribe the .data onto a blank copy of the .form as it is read, then transfer the information to the status .boaid.

4. The Status Board Plotter(s) will retain the completed forms until the emergency is terminated, then deliver them to the Senior Specialist - Emergency Preparedness.

10.0 DIAGRAMS ATI'ACHMENTS

1. Safety Parameter Data and Status Information Form.

2. Example Message Form.

3. Communications I

Priorities.

PEP-302 Rev. 0 Page 6 of 18

APR014 ATTACHMENT 1 SAFETY PARAMETER DATA &, STATUS INFORMATION FORM Nuclear Instrumentation Source Range: Level SUR Intermediate Range: Level SUR Power Range: Level Highest Core Exit Temp oF Gross Failed Fuel CPM oF Reactor Coolant Cold Leg Temp A F B F C oF Reactor Coolant Hot Leg Temp A F B F C Reactor Coolant System Pressure Pressurizer Level '

Reactor Vessel Level Steam Generator Level A '1m C Condensate Storage Tank Level Ft.

Containment Pressure psig Hydrogen Sump Level Wide Range Ft. Area Radiation High Range R/hr Isolation Valves closed?

'Reactor Coolant Subcooling or Superheat oF Plant Vent Stack gl: Noble Gas yCi/cc Flow Waste Processing Bldg. Vent Stack g5: Noble Gas pCi/cc Flow Waste Processing Bldg. Vent Stack /$ 5A.-: Noble Gas pCi/cc Flow Condenser Vacuum Pump Exhaust Stack 3A: Noble Gas- yCi/cc Flow Safety Injection Accumulator Tanks Levels-1A inches 1B inches 1C inches Pressures: lg~sig IB~sig IC~sig High Pressure Injection Flow gpm Isol vlv pos. IA Low Pressure Injection Plow 1B 1C gpm RWST Level 10 Primary Relief Valve Positions: PORV A B C Pressurizer Relieve Tank: Level Pressure Temp F Pressurizer Heater Current: A Amps B Amps sig Main Steam Flow (Thousand Pounds Per Hour): A B C Auxiliary Feedwater Plow, (Thousand Pounds Per Hour): A B C Containment: Spray Flow A gpm B gpm Atmosphere Temp. F Containment Sump: Narrow Range. Water Level Ft. Water Temp. oF CVCS: Makeup flow gpm Letdown flow gpm VCT Level RHR Loop Flows: 1A . gpm 1B gpm RHR Heat Exchanger Outlet Temp: 1A F 1B oF Emergency Ventilation Damper Status 230KV Switchyard Bus Voltage: North South 120VAC Uninterruptable Power Supply Bus Voltage 120VAC Bus Voltage: IDP-1A-SI IDP-1B"SII IDP-1A-SIII IDP-1A-SIV 125VDC Emergency Bus Voltage: 1A-SA 1B-SB 125VDC Battery Bus DP-lA Voltage 250VDC Battery Bus DP-1 Voltage Diesel Generator Distribution Panel Voltage: 1A1 1B1 Emergency Bus Voltage: 1A 1B PEP-302 Rev. 0 Page 7 of 18

APR014 Component Cooling Water Flow and Temperature:

RHR Heat Exchanger lA outlet gpm oF RHR Heat'xchanger 1B outlet gpm oF Containment Fan Cooler Status:

AH-1 AH-2 AH-3 AH"4 Boric Acid Emergency Bypass Flow gpm Containment Spray Additive Flow gpm Atmospheric Steam Dump Valves Status Main Steam Relief Valve Status:

Main Steam Line Noble Gas:

A pCi/cc B yCi/cc C pCi/cc Main Steam Isolation Valve Hydraulic Accumulator Pressures:

A psig B sig C Sig Feedwater Isolation Valve Hydraulic Accumulator Pressures:

A psig B sig C 0

sig Wind Speed mph Direction" (from)

Lower Level oF Atmospheric Temperature: Upper Level F Control Rod Position: All full in or RCS Boron Concentration pm Reactor Coolant Pump Current: A amps B amps C amp s Main Feedwater Flow: A "Waste Gas Decay Tank Pressures:

Recycle Holdup Tank Level gpm A~sig Ft.

B B~sig C~siggpm C D~sig gpm PEP-302 Rev. 0 Page 8 of 18

. APR014 MONITOR DESIGNATION DESCRIPTION REM"1SW-3500A-SB Service Water From Containment Fan Cooler AH-1 gCi/cc REM-.1SW-3500B-SA Service Water From Containment Fan Cooler AH-2 yCi/cc REM-1SW-3500C-SA Service Water From Containment Fan Cooler AH-3 pCi/cc REM"1SW-3500D-SB Service Water From Containment Fan Cooler AH-4 yCi/cc REM" 1CC-3501A" SA Component Cooling Water A yCi/cc REM" 1CC-3510B-SB Component Cooling Water B yCi/cc REM-1LT-3502A-SA Containment Leak Detection yCi/cc (NG) yCi/cc (P)'Ci/cc REM-1LT-3502B-SB Containment Leak Detection (NG) yCi/cc (P)

RM"1CZ-3504A-SA Control Room Normal Outside Air Intake A yCi/cc RM-1CZ-3504B-SB Control Room Normal Outside Air Intake B yCi/cc RM-1CZ-3505$ 1-SA Control Room Emergency Outside Air Intake 10A yCi/cc RM-1CZ-3505A2-SA Control. Room, Emergency Outside-Air Intake 11A yCi/cc RM-1CZ "3505B1-SB Control Room Emergency Outside Air Intake 10B pCi/cc RM-1CZ-3505B2 "SB Control Room Emergency Outside Air Intake 11B yCi/cc li REM"1FL-3506 FHB Spent Fuel Pool Normal Exhaust South yCi/cc (P) 1 yCi/cc (I) yCi/cc (NG)

REM-1FL-3507 FHB Spent Fuel Pool Normal Exhaust, South yCi/cc (P)

I yCi/cc (I) yCi/cc (G)

REM-1FL-3508A-SA FHB .Spent Fuel Pool Emergency Exhaust A yCi/cc (P) gCi/cc (I) pCi/cc (NG)

REM-1FL-3508B-SB FHB Spent Fuel Pool Emergency Exhaust B yCi/cc (P)

M gCi/cc (I) yCi/cc (NG)

REM<<1AV-3509-SA Plant Vent Stack gl yCi/cc (P) gCi/cc (I)

REM-1BD-3527 Steam Generator Blowdown pCi/cc REM"1MD-3528 Turbine Building Drain QC1/CC REM-1MD-3530 Tank Area Drain Transfer Pump 'pC1/CC REM"lAV-3531 RAB Normal Exhaust System yCi/cc (P)

PEP-302 Rev. 0 Page 9 of 18

APR014 yCi/cc (I) yCi/cc (NG)

REM-1AV-3532A RAB Emergency Exhaust System A pCi/cc (~)

yCi/cc (I) pCi/cc (NG)

REM"1AV-3532B RAB Emergency Exhaust System B yCi/cc (P,)

yCi/cc (l) yCi/cc (NG)

REM.-1AV-3533 Hot Machine Shop Vent yCi/cc (P) yCi/cc (I) yCi/cc (NG)

REM-21WL-3541 WST Monitor Tank Discharge yCi/cc REM-21WS-3542 Secondary WST Sampling Tank Pump Discharge yCi/cc REM-21AC-3543A Auxiliary Steam Condensate WPS Tank Pump Discharge HDR yCi/cc REM-43AC-3543B Auxiliary Steam Condensate WPS Tank Pump Discharge HDR yCi/cc REM-1WC"3544 WPB WCHX A&B Header Inlet yCi/cc

'REM-21WG-3545 Waste Gas Compressor Suction Header yCi/cc Waste Gas Compressor, Suction Header yCi/cc REM-43WG-.3545 REM<<1WV-3546 WPB Exhaust System Penthouse I .Stack '5 yCi/cc yCi/cc (p>

(I)

~

'REM" 1WV-3547 WPB Exhaust 'System"Penthouse II Stack 5A yCi/cc (P) yCi/cc (I)

REM- 1WV-3548 WPB Health Physics Calibration Room yCi/cc (P)

'Ci/cc (I) yCi/cc (NG)

REM"1FL-3549 FHB Operating Floor yCi/cc (P) pCi/cc (I) yCi/cc (NG)

REM"1WV"3550 WPB Control Room pCi/cc (P) yCi/cc (I)

REM-1WV-3551 Volume Reductions System yCi/cc (P) yCi/cc (I) yCi/cc (NG)

REM"1WV-3552 Solidification System . yCi/cc (P) pCi/cc (I) yCi/cc (NG)

REM- 1WV-3553 WPB Personnel Handling Facility Exhaust Fan yCi/cc (P)

PEP-302 Rev. 0 Page 10 of 18

APR014 REM-1MV-3553, VPB Personnel Handling Facility yCi/cc (I)

(continued) Exhaust Fan yCi/cc (NG)

REM-1WV"3554 Hot I ab yCi/cc (P) gCi/cc (I) yCi/cc (NG)

RM"21RR"3560-SA Control Room R/hr RM-1CR-3561A"SA Containment Isolation System A R/hr RM"1CR-3561B-SB Containment Isolation System B R/hr RM-1CR-3561C-SA Containment Isolation System C R/hr-RM-1CR-3561D-SB Containment Isolation System D R/hr RM"1FR-3564A"SA Spent Fuel Pool (South) R/hr RM"1FR"3564B-SB Spent Fuel Pool (South) R/hr RM"1FR-3565A"SA Spent Fuel Pool (South) R/hr RM-1FR"3565B-SB 'Spent Fuel Pool (South) R/hr RM-1FR-3566A-SA Spent Fuel Pool R/hr (North)'pent RM"1FR-3566B"SB Fuel Pool (North) R/hr RM"1FR-3567A-SA. Spent Fuel Pool (North) R/hr RM-1FR-3567B-SB Spent Fuel Pool (North) R/hr RM-1CR-3575 Containment South Stairwell EL. 261 R/hr RM-1CR-3576 Containment North Stairwell EL. 261 R/hr RM-1CR-3577 Containment Bldg. Incore Instrument Controls R/hr RM-21CR-3578A Recycle Monitor Tank R/hr RM-21CR-3578B Recycle Monitor Tank R/hr RM"1CR-3579 Boric Acid Filters R/hr RM"1CR-'3580 Valve Gallery R/hr RM-21CR-3581A Access Aisles Between Valve Gallery R/hr RM-21CR-3581B Access Aisles Between Valve Galleries R/hr RM-1CR"3582 Containment North Stairwell EL. 286 R/hr PEP-302 Rev. 0 Page 11 of 18

APR014 RM-1CR-3583 Containment South Stairwell EL. 286 R/hr RM-1CR"3584 Pressurizer Area R/hr RM-1CR-3585 South Secondary Containment R/hr RM"1CR-3586 Primary Cooling Duct R/hr RM-1CR"3587 Reactor Coolant Drain Tank R/hr RM-1CR-3588 Personnel Lock 6 Equipment Removal Area R/hr RM-1RR-3595 Volume Control Tank R/hr RM-1RR-3596 Main Steam 6 Feed Water Tunnel Floor R/hr RM-1RR-3597 RAB RHR Pump 1B Corner R/hr RM"1RR-3598 RAB RHR 1A Corner R/hr RM-1RR-3599A Charging Pump 1A R/hr

-'RM" 1RR-3599B Charging Pump 1B R/hr RM-1RR-3599C Charging Pump 1C R/hr RM-1RR-3600 Recycle Evaporator Valve Gallery R/hr RM-1RR-3601,. Letdown Heat Exchanger Valve Gallery R/hr

'RM "3.RR-3602 Moderating .Heat Exchanger Valve Gallery R/hr

"'RM-1RR-3603 Boric Acid Pumps Valve Gallery R/hr RM-21RR-3604 Access Aisle R/hr RM-1RR-3605A Sample Room 1A R/hr RM-1RR-3650B Sample Room 1B R/hr RM-1RR-3606A RHR Heat Exchanger 1A R/hr RM-1RR-3606B RHR Heat Exchanger 1B R/hr RM-1RR-3607 "Decontamination Area EL. 236 R/hr

.RM-1RR-3608 'econtamination Area EL. 261 R/hr RM-21RR"3609A Waste Monitor Tank R/hr RM-21RR-3609B Waste Monitor Tank R/hr RM-21RR-3610 Secondary Waste Sample Tank R/hr PEP-302 Rev. 0 Page 12 of 18

.. APR014 Recycle- Holdup Tank R/hr RM-1FR" 3620 Spent Fuel Pool Area South R/hr RM"1FR"3621 Spent Fuel Pool Area North R/hr RM-1FR"3622 Spent Fuel Pool Shipping Cask Area R/hr RM-1FR-3623A Spent Fuel Heat Exchanger (1&4A) R/hr RM-1FR-3623B Spent. Fuel Hea't Exchanger (1&4B) R/hr RM-1FR<<3625 Access Aisle Between Spent Fuel Heat Exchanger R/hr RM-32FR-,3626 Purification Pump Filter (2A&3A) Area R/hr RM-41FR-3626 Purification Pump Filter (1A&4A) Area R/hr RM"1FR-3628 New Fuel Storage Area R/hr RM-1WR.-3635 Filter. Backwash Transfer Tank Valve Gallery R/hr RM-1WR"3636A Filter Particulate Concentrates Tank Valve Gallery R/hr RM-1WR-3636B Filter Particulate Concentrates Tank Valve Gallery R/hr RM-21WR-3637 Gas Decay Tank Drain Pump R/hr RM-43WR-3637 Gas Decay- Tank Drain Pump R/hr RM"1WR"3638A Filter Backwash Storage Tank Pump Valve R/hr Gallery RM-1WR-3638B Filter Backwash Storage Tank Pump Valve Gallery R/hr RM-21WR-3639A Waste Gas Compressor 1A & 2A R/hr RM-4 3WR-3639A Waste Gas Compressor 3A & 4A R/hr RM"21WR-3639 B Waste Gas Compressor 1B & 2B R/hr RM-43WR-3639B Waste Gas Compressor 3B & 4B R/hr RM-21WR-3640 Waste Evaporator Concentrates Valve Gallery R/hr RM-43WR-3640 Waste Evaporator Concentrates Valve Gallery R/hr PEP-302 Rev. 0 Page 13 of 18

APRG14 RM-21WR"3641 Waste Evaporator Feed Pump Gallery R/hr RM-43WR-3641 Waste. Evaporator Feed Pump Gallery R/hr RM-21WR-'3642A Waste Evaporator Valve Gallery R/hr RM"43WR-3642A Waste Evaporator Valve Gallery R/hr RM-21WR-3642B Waste Evaporator Valve Gallery Area R/hr RM-43WR-3642B Waste Evaporator Valve Gallery Area R/hr RM>> 1WR-364 3 Waste Evaporator Sample Rm. gl R/hr RM- 1WR-364 4A Spent Resin Pumps (1-4A) R/hr RM-1WR-3644B Spent Resin 'Pumps (1-4B) R/hr RM-21WR-3645A Catalytic Recombiner (1&2A) R/hr RM-43WR-3645A Catalytic Recombiner (3&4A) R/hr RM-21WR-3645 B Catalytic Recombiner (1&2B) R/hr RM-43WR-3645B Catalytic Recombiner (3&4B) R/hr RM-1WR-3646 Waste Processing Control Rm. R/hr RN-21WR-3647A Gas Decay Tank Valve Gallery R/hr RM-43WR-364 7A Gas Decay Tank Valve Gallery R/hr RM"21WR-3647B Gas Decay Tank Valve Gallery R/hr RM-43WR-3647 B Gas Decay Tank Valve Gallery R/hr RM-1WR"3648 Reverse Osmosis Module East . R/hr RM-1WR-3649 Reverse Osmosis Module West R/hr RM-2.1WR-3650 ,Floor Drain Reverse Osmosis Module R/hr RM-43WR-3650 Floor Drain Reverse Osmosis Module R/hr RM"21WR-3651A Floor Drain Tank (1&2A) R/hr RM"43WR-365 1A Floor Drain Tank (3&4A) R/hr RM-21WR-3651B Floor Drain Tank (1&2B) R/hr RM-43WR-365 1B Floor Drain Tank (3&4B) R/hr RM- 1WR" 3652A WPB Mens Locker Room R/hr PEP-302 Rev. 0 Page 14 of 18

, APR014 RH-1WR,"',3652B MPB.Hens, Locker Room R/hr=

RH" 1MR-3652C VPB Vomens Locker Room R/hr PEP-302 Rev. 0 Page 15 of 18

EXAMPLE MESSAGE page REPLY MESSAGE FOld IC OUIdO I III'Ohall IO NtldOEIP BOEIIOOO d'or dP CAROUNA POWER 8 .UGHT'.Co SUSJSCT ATTBNTION u~ g uA n WS5 PLEASE REPLY TO ~ SIGNED AIPD a" 8 O, eP 4 e.

DATE Z Z J SIGNED RECIPIENT.RBPI.Y SI RSTAIN PINK COPY4OKTACH 5 MTURN THLS COPY TO SENDS R.

~ESOSM5ETXCA THIS COPY&STAIN FOQPILS. SSND VIHIThAND PINk COPIESPtITH CARBONS INTACT PEP-302 Bev. 0 Page 16 Of 18

ATTACHMENT 3 COMMUNICATIONS PROTOCOL FROM JO CONTROL ROOM Technics I Support Center l. EOF Telephone Extension

2. Plant Tetephone Extension Operations Leader Plant Operations Director 1. ARD to Plant Operation Director

2. EOF Telephone Extension

3. Plant Telephone Extension Operators Plant Radio Channel Ill Plant PA System f Emergency Communicator NRC 1. NRC Emergency Notification System

2. Bell System

3. NRC Health Physics Network N.C. State and Loca I Warning ARD to Warning Points Points Bell System Status Board Plotters - TSC l. EOF Telephone Extension and EOF 2. Plant Telephone Extenston Shift Technical Advisor Accident Assessment Team Leader I 1 ~ EOF Telephone Extension 1

2. Plant Telephone Extension OPERATIONAL SUPPORT CENTER Technical Support Center l. EOF Telephone Extension

2. Plant Telephone Extension All Other Plant Locations Plant Telephone Extension 2~ Plant Radio Channel III2'amage Control Team Leader Damage Control Team Coordinator 'I. Plant Radio Channel Itr2 r 2 Plant

~ Telephone Extension Plant Mont toring and Person-nel Protection and Decontam-Team Leaders in Technical Support l. Plant Radto Channel gl Center 2. Plant Telephone Extension ination Teams I

Environmental Monitoring Teams Environmental Monitoring Team Leader l. UHF Radio Emergency Channel

2. Bell System Fire Brigade, First Aid, and Search and Rescue Teams Team Leaders Center in Technica I Support l.

2~

Plant Radio channel Ital Plant Telephone Extension Assembly Area Leaders Emergency Security Team Leader Plant Telephone-Extension TECHNICAL SUPPORT CENTER Control Room l. EOF Intercom

2. EOF Telephone- Extension

3. Plant Telephone Extension

Operations Support Center 1. EOF Telephone Extension

2. Plant Telephone Extension Emergency Operations Facil.ity l. EOF'ntercom

2. Plant Telephone Extension via EOF Switchboard C)

Site Emergency Coordinator Emergency Response Manager 1. ARD to Emergency Response Manager

2. EOF Telephone Extension Emergency Communicator - TSC Emergency Communicator - EOF 1. ARD to EC - EOF

2. EOF Telephone Extension Phone Talker - TSC NRG 1. NRG Emergency Notification System

2. Bell System

3. NRC Health Physics Network NG State and Local Harning Points 1. ARD to Wa ming Pq ints

2. Bel I System Environmental Monitoring Environmental Monitoring UNF Radio Emergency Channel Team Leader Teams Plant Operations Director Ope ra t I ons Leader l. ARD to Control Room

2. EOF Telephone Extension

3. Plant Telephone Extension Accident Assessment Team Leader 1. EOF intercom and First Aid Team Leader 2. EOF Telephone Extension 3~ Plant Telephone Extension F.l.re Brigade Leader Plant Radio Channel gl

%L Accident Assessment Team Shift Technical Advisor 1. EOF Telephone Extension Leader 2. Plant Telephone Extension First Aid Team Leader First Aid and Search and Rescue 1. Plant Radio Channel g1 Teams 2. Plant PA System Emergency Repair Director Operations I Support Center Leader 1. EOF Telephone Extension

2. Plant Telephone Extension

3. Plant Radio Channel g2 Damage Control Team Damage Control Team Leader 1. Plant Radio Channel g2 Coordinator 2. Plant PA System Dose Projection Team Leader Dose Assessment Team Leader 1, ARD to EOF S 2. EOF Telephone Extension Plant Monitoring Team Plant Monitoring Teams, and Per- 1. Plant Radio Channel gl Leader and Personnel sonnel Protection and Decontamlna- 2. Plant PA System 0ltl Prqtectton and Decontamination tion Teams Team Leader

APR008 CAROLINA POWER,&.- LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-321 TITLE: NOTIFICATION OF EMERGENCY PERSONNEL REVISION 0 APPROVED:

Signature Date TITLE:

PEP-321 Rev. 0 Page 1 of 8

APR008 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 4 2.2 Referenced Emergency Plan Procedures 4 2.3 Other References 4 3.0 'ESPONSIBILITIES 4 4.'0 DEFINITIONS 4 5.0 GENERAL 5 6.0 INITIATING CONDITIONS 5 7.0 PRECAUTIONS AND LIMITATIONS 5 8.0 SPECIAL TOOLS AND EQUIPMENT 5 9.0 PROCEDURE STEPS 5 9.1 Initial Notification I 5 9.2 Continuous Staffing of Emergency Response Organization 10.0 DIAGRAMS/ATTACHMENTS

1. "Emergency Response Organization Notification Form" PEP-321 Rev. 0 Page 2 of 8

APR008 LIST."'OF EFFECTIVE PAGES

~Pa e Revision 1 through 8 0 PEP-321 Rev. 0 Page 3 of 8

APR008 1.0 PURPOSE The purpose of this procedure is to implement SHNPP Emergency Plan Section 2.2.2, "Plant Emergency Response Organization" and Section 4.2, "Notification."

This procedure provides instructions for notifying the CPGL emergency response organization and NRC Resident Inspector.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 2.2.2, "Plant Emergency Organization"

.2. Section 4.2, "Notification" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES 1 PEP 302 p "Communications Activities"

2. PEP-303, "Use of Communications Equipment"

2. 3 OTHER REFERENCES

1. Plant Special Order; ."Emergency Phone List" 3.0 RESPONSIBILITIES 3.1 The Site Emergency Coordinator is responsible for ensuring that on-site emergency personnel should be activated and whether off-duty emergency personnel are notified.

3.2 The Emergency Communicator is responsible .for performing the notifications when directed to do so by the Site Emergency Coordinator.

3.3 The Logistics Support Director is responsible for coordinating the preparation of shift schedules.

3.4 All personnel, when filling -a position on the emergency response organization, are responsible for contacting alternates to ensure 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> staffing capability for the position that they are filling, when directed to do so by the Site Emergency Coordinator/Emergency Response Manager.

4.0 DEFINITIONS

1. Key Person - A principle member of the emergency response organization (Site Emergency Coordinator, Directors, Leaders, State Emergency Response Team Representative, and Emergency Preparedness Specialist).

PEP-321 Rev. 0 Page 4 of 8

APR008 4.0 DEFINITIONS

2. Plant Emergency Personnel - Plant personnel who have pre-assigned duties in the Emergency Response Organization.

5.0 GENERAL None Applicable 6.0 INITIATING CONDITIONS

1. An emergency has been declared by the Shift Foreman.

7.0 PRECAUTIONS AND LIMITATIONS

1. To avoid disruption of communications systems when performing notifications, use the equipment and extension/channel number specified in PEP-302.

2. Emergency notification messages shall be given ~onl to the specified individuals and. not to their spouse, children, baby-sitter, etc., or anyone who does not identify them-self.

8.0 SPECIAL TOOLS AND E UIPMENT.

Emergency communications.-equipment which has the ability to contact off duty emergency personnel. Use of this equipment is discussed in PEP-302 and PEP-303.

9.0 PROCEDURE STEPS 9.1 INITIAL NOTIFICATION The Site Emergency Coordinator prepares an Emergency Response Organization Notification Form (Attachment 1).

He checks the box at the top of the form appropriate to the emergency classification. The Site Emergency Coordinator may select additional personnel to notify or activate, and/or facilities to activate by placing the appropriate symbol in the corresponding box. He then signs the formgives it to the Emergency Communicator, and directs him to perform the notifications.

2. The Emergency Communicator announces the emergency classi-fication and facilities 'to be activated on the Public Address system.

PEP-321 Rev. 0 Page 5 of 8

APR008 9.0 PROCEDURE STEPS 9.1 Initial Notification (Cont'd.)

NOTE: Any personnel with emergency assignments who are on-site when the Public Address announcement is made will report to their assigned location. If a primary or alternate designee reports in before the Emergency Communicator has attempted to contact designees for a given emergency organization position, the Emergency Communicator will record the time reported in on the Emergency Organization Notification Form, and the initial notification is then considered complete. If an alternate designee assumes a position in this manner, it becomes his responsibility to notify the primary designee for his posdtion if he considers it appropriate.

3. The Emergency Communicator refers to Plant Special Order, "Emergency Phone List," to obtain telephone numbers, then attempts to contact the primary designee for the first position indicated on the Emergency Response Organization Notification Form unless an individual has already repor'ted in for 'that position.

NOTE: If the Site Emergency Coordinator so requests, indicate in the notification that. responding personnel report to the SHE&EC to obtain protective clothing before arriving on

.site.

If the primary designee cannot"be contacted, the Emergency Communicator continues through the list of alternate designees in'- Pl'ant.Special Order, "Emergency Phone List" until one is contacted. If neither .the primary nor any of the alternates can be contacted by telephone, the" Emergency Communicator attempts to notify them by pager.

'If none of the designees can be contacted by any available method, the Emergency Communicator notifies the Site Emergency Coordinator.

5. When an individual is contacted and identified, the Emergency Communicator informs him of the emergency classification, the emergency organization position that he is to assume, whether that position is being notified or activated, and what facilities are 'being activated.

The Emergency Communicator obtains an estimated time of arrival from the individual, then records the person' name, time notified, and estimated time of arrival on the Emergency Response Organization Notification Form.

6. The Emergency Communicator repeats steps 3 through 5 for each emergency organization position indicated on the form,. proceeding in order from top to bottom of the list.

PEP-321 Rev. 0 Page 6 of 8

APR008 9.0. PROCEDURES STEPS 9.1 Initial Notification (Cont'd)

7. After individuals have been contacted for all positions indicated on the Emergency Response Organization notification Form, the Emergency Communicator signs the form and informs the Site Emergency Coordinator that all personnel have been notified.

8. As personnel report in from their assigned emergency facility, the Emergency Communicator records the time on the Emergency Response Organization Notification Form.

Sim'ilarly, he records the time that each emergency facility is reported activated.

9. When all activated personnel have reported in, and as each emergency facility is reported activated, the Emergency Communicator informs the Site Emergency Coordinator.

9.2 CONTINUOUS STAFFING OF EMERGENCY ORGANIZATION The Site Emergency Coordinator (in conjunction with the Emergency Response Manager) will evaluate the emergency condition and prognosis for continuance of the situation beyond several hours.

2 If the likelihood- exists that the emergency condition will remain beyond a few hours, the Site Emergency Coordinator will direct his staff to, and the Emergency Response Manager will direct his staff to, contact alternates and inform them to report for relief at a predetermined time.

The Logistics Support Director and Administrative and Logistics Manager will coordinate the preparation of shift schedules.

NOTE: It is useful for relief of the Technical Support Center Staff and Emergency Operations Center Staff to occur an hour or two apart to improve continuity during turnover.

3. Where alternates cannot be contacted for a position, the matter will be referred to the Logistics Support Director (Technical Support Center) or administrative and Logistics Manager (Emergency Operations Facility) for extraordinary measures to contact the alternates or for contacting trained individuals at Brunswick or Robinson who can serve the necessary functions.

10. 0 DIAGRAMS ATTACHMENTS

1. Emergency Response Organization Notification Form PEP-321 Rev. 0 Page 7 of 8

APR008 ATTACHMENT 1 EMERGENCY RESPONSE ORGANIZATION NOTIFICATION FORM check a ro riate box ~

TIME EHERGENCY RESPONSE NAME 0 ORGANIZATION W 'a 4J 4J POSITION 0 a0 C SITE EMERGENCY COORD-TSC A A A EMERGENCY COMMUNICATOR A A A PLANT OPERATIONS DIR. NAA RADIOLOGICAL CONTROL DIR. A A EMERGENCY REPAIR DIR. A A LOGISTICS SUPPORT DIR. A A EMERGENCY RESPONSE MGR. N N A NRC RESIDENT INSPECTOR N N N SERT REPRESENTATIVE .NA ACCIDENT ASSESSMENT TEAM LDR. A A OSC LEADER DAMAGE CONTROL TEAM COORD.

EMERGENCY SECURITY TEAM LDR. A A PLANT MONITORING TEAM LDR. A A DOSE PROJECTION TEAM LDR.

PERS. PROT. & DECON. TEAM LDR. A A ENV. MONITORING- TEAM LDR. A A EVACUATION ASSEMBLY AREA LDR.

SUPPORT SERVICES COORD.

SITE COMM. SYST. COORD. A A EHERG. PREPAREDNESS SPECIALIST N N N FACILITIES Activated Tech. S t. Center 0 ns. S t. Center Emer . 0 ns. Facilit A = Activate N = Notify Approved for Notification / /

Site Emergency Coordinator / Time ,/Date Notifications Completed / /

Emergency Communicator / Time /Date PEP-321 Rev. 0 Page 8 of 8

APR009 CAROLINA-POWER & LIGHT COMPANY,

. SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-322 TITLE: MOBILIZATION OF OUTSIDE ORGANIZATIONS REVISION 0 APPROVED:

S ignatuz e Date TITLE:

PEP-322 Rev. 0 Page 1 of 7

APR009 TABLE OF CONTENTS

'~Pa e Table, of Contents 2 List of Effective Pages 3 1.0 PURPOSE

2.0 REFERENCES

2.1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4, 3.0 RESPONSIBILITIES 4, 4.0 DEFINITIONS 5 5.0 GENERAL 5 6.0 INITIATING CONDITIONS 5 7.0 PRECAUTIONS AND LIMITATIONS 5

8. 0 SPECIAL TOOLS AND EQUIPMENT 5 9.0 PROCEDURE STEPS 5 10'.0 DIAGRAMS/ATTACHMENTS 6

1. Mobilization of Outside Organizations Form 7 PEP-322 Rev. 0 Page 2 of 7

APR009 LIST. OF..: EFFECTIVE PAGES

~Pa e Revision 1 through 7 0 PEP-322 Rev. 0 Page 3 of 7

APR009

1. 0 PURPOSE The purpose of this procedure is to implement Section 4.2, "Notification,"of the Shearon Harris Nuclear Power Plant Emergency Plan.

This procedure provides instructions for notification of off-site organizations who can provide assistance during the emergency or recovery phase of the accident either at their facilities or by providing personnel in the field.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

,1. Section 4.2, "Notification"

2. Annex G, "Interfacing Information from Supporting Emergency Plans" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-102, "Site Emergency Coordinator - Control Room" i2. PEP-103, "Site Emergency Coordinator - Technical Support Center"

3. PEP-203, "Logistics Support Director" PEP-302, "Communications Activities" 5; PEP-303, "Use of Communications Equipment"

6. Plant Special Order {PSO) "Emergency Phone List" 3.0 RESPONSIBILITIES 3.1 Until relieved of this responsibility by the Emergency Response Manager, the Site Emergency Coordinator is responsible for approving requests for assistance from outside organizations.

3.2 Upon activation of the Emergency Operations Facility, the Emergency Response Manager is responsible for approving requests for assistance from outside organizations.

3.3 The Logistics Support Director is responsible for coordinating requests for off"site assistance from all on-site members of the emergency organization. Until relieved of this responsibility by

~

the Administrative. and Logistics Manager, he is also responsible for contacting outside organizations after the request for assistance has been approved by the Site Emergency Coordinator.

3.4 The Administrative and Logistics Manager is responsible for obtaining approval from the Emergency Response Manager for requests PEP-322 Rev. 0 Page 4 of 7

APR009

3. 0 RESPONSIBILITIES off-site for contacting the necessary

'or assistance, and organizations.

4.0 DEFINITIONS None Applicable 5.0 GENERAL None Applicable 6.0 INITIATING CONDITIONS

1. An emergency has been declared by the Site Emergency Coordinator and a member of the emergency organization has identified a need for assistance from an off-site organization.

7.0 PRECAUTIONS AND LIMITATIONS Although any member of the emergency organization may request the assistance of the organizations listed in Attachment 1, the Site Emergency Coordinator's (or Emer-gency Response Manager') approval must be obtained before the contact is made.

8.0 SPECIAL TOOLS AND E UIPMENT None Applicable

9. 0 PROCEDURE STEPS

1. The Logistics Support Director decides that one or more organizations listed on Attachment 1 should be notified or asked for assistance based upon a request for assistance from a member of the on-site emergency organization, or his own evaluation of the emergency condition.

NOTE: If members of the Emergency Operations Facility staff wish to request outside assistance they do so directly from the Administrative and Logistics Manager'.

2. If the Emergency Operations Facility has been activated, the Logistics Support Director notifies the Administrative and Logistics Manager who, in consultation with the Logistics Support Director, recommends what organizations are to be contacted.

3. . The Logistics Support Director (or Administrative and Logistics Manager) indicates which organization is to be contacted and what assistance, if any, is to be requested by checking the appropriate blocks on Attachment 1 and 9.0 PEP-322 Rev. 0 Page 5 of 7

APR009 9.0 PROCEDURE STEPS briefly noting any assistance required. He then presents the form to the Site Emergency Coordinator (or Emergency Response Manager)for approval.

4. The Site Emergency Coordinator (or Emergency Response Manager) authorizes the request by signing Attachment 1.

5. The Logistics Support Director (or Emergency Response Manager) refers,to the Plant Special Order, "Emergency Phone List" for the telephone number, calls the outside organization which has been selected on Attachment 1, and requests assistance as indicated on the form.

6. The Logistics Support Director (or Administrative and Logistics Manager) records the name of the person contacted, the, expected assistance, and the expected arrival, or delivery time on Attachment 1. If possible, he obtains the. names of any personnel who will be coming to the site, Emergency Operations Facility, or Corporate Emergency Operations Center.

7. After contacting the organization, the Logistics Support Director (or Administrative and Logistics Manager) signs the form to indicate that the notification is complete, then returns the completed form to,the Site Emergency Coordinator .(or Emergency Response Manager.) If contact was made by the Administrative and Logistics Manager, the Administrative and Logistics Manager also informs the Logistics Support Director of what assistance is expected.

The Logistics Support Director will then .inform the Site Emergency Coordinator and the person who originally requested the assistance as to what assistance will be provided and when.

8. If the organization contacted was requested to send personnel to the Site or to the Emergency Operations Facility, the Logistics Support Director notifies the Emergency Security Team Leader, providing him with the name of the-organization, name(s) of personnel, destinations .and estimated time of arrival, if possible.

10. 0 DIAGRAMS ATTACHMENTS Mobilization of Outside Organization Form PEP-322 Rev. 0 Page 6 of'7

APR009 ATTACHMENT 1-,,

MOBILIZATION OF OUTSIDE ORGANIZATIONS ORGANIZATION:

a INPO o American Nuclear Insurers m Vestinghouse a Nuclear Mutual Limited a Ebasco 0 Department of Energy a Daniel Construction Co.

a Other Assistance Requested:

Authorization:

(Site Emergency Coordinator oz Emergency Response Manager)

Individual Contacted Date Time Assistance They Eave Agreed To Provide:

Individuals Who Vill Be Reporting To The Site Location Expected Arrival Re ortin To Date Time Notification Completed Logistics Support Director or Date Time Administrative and Logistics Manager PEP-322 Rev. 0 Page 7 of 7

APR011 CAROLINA POWER 6 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP"331 TITLE: EMERGENCY PLANT MONITORING REVISION 0 APPROVED:

Signature Da e TITLE:

PEP-331 Rev. 0 Page 1 of 7

APR011 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 4.

2.2 Referenced Plant Emergency Procedures 2.3 Other References 4 3.0 RESPONSIBILITIES 5 3.1 Plant Monitoring Team Leader 5 3.2 Personnel Protection and Decontamination Team Leader 5 3.3 Operations Leader 5 4.0 DEFINITIONS 5 5.0 GENERAL 5 6.0 INITIATING CONDITIONS 5 7.0 PRECAUTIONS/LIMITAT10NS 6 8.0 SPECIAL TOOLS AND EQUIPMENT 6 9,0 PROCEDURE STEPS 6 10.0 DIAGRAMS/ATTACHMENTS 7 PEP-331 Rev. 0 Page 2 of 7

APR011 LiST OF EFFECTIVE PAGES

~Pa e Revision 1 through 7 0 PEP-331 Rev. 0 Page 3 of 7

APR011 1,0 PURPOSE The purpose of this procedure is to implement Section 4.4.2, "Plant Radiological Monitoring", of the SHNPP Emergency Plan. It specifies the methods to be used for conducting radiological surveys at, the plant site, and for sampling and analyzing plant systems during an emergency.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 4.4.2, "Plant Radiological Monitoring"

2. Section 2.4.6, "Radiological Control Director"

3. Section 2.4.6.5, "Plant Monitoring Team Leader" Section 2.4.6.7, "Personnel Protection and Decontamination Team Leader" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-207, "Plant Monitoring Team Leader"

2. PEP-208, "Personnel Protection and Decontamination Team Leader" 2' OTHER REFERENCES

1. ERC-105, "Scheduling Radiation Control Activities"

2. HPP-066, "Preparation and Analysis of Air Samples"

3. HPP-503, "Operation of the Protechtor Portable Gas Alarm"

4. HPP-504, "Operation of'the Gastechtor Portable Gas Alarm"

5. CRC-110, "Primary Sample Room Procedure" *

6. CRC-154, "Secondary Sample Room Procedure" I

7. CRC-250, "Plant Vent Sampling"

8. CRC-821, "Post Accident Dilute Liquid Sampling"

9. CRC-822, "Post Accident Undiluted Liquid Sampling"

10. CRC-823, "Post Accident Containment Air Sampling"

11. CRC-824, "Post Accident Dissolved Gas Sampling and Analysis"

12. CRC-825, "Post Acci'dent pH/Conductivity/Dissolved Oxygen"

13. CRC-826, "Post Accident Chloride Analysis"

14. CRC-827, "Post Accident Boron Analysis"

15. HPP-505, "Operation of the Draeger Multigas Detector"

16. ERC-106, "Confined Space Monitoring Program"

17. CRC-828, "Isotopic Analysis for Core Damage Evaluation"

18. RCP-651, "Sample Preparation for Gamma Spectrometry"

19. RCP-701, "Operation of the Gamma Spectrometry System"

20. CRC-515, "Operation of the Gas Chromatograph"

21. CRC-004, "Chemistry Logs and Records"

22. OP-118, "Radiation Monitoring System"

23. Regulatory Guide 1.97, " Instrumentation for Light-Vater Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and After an Accident,"

PEP-331 Rev. 0 Page 4 of 7

APR011 3.0 RESPONSIBILITIES 3.1 PLANT MONITORING TEAM LEADER The Plant Monitoring Team Leader is responsible for assigning members of the Plant Monitoring Team to:

Operate the Post Accident Sampling System Conduct in-plant radiological surveys fox accident assessment purposes Obtain and analyze other plant samples Perform field interrogations of the Radiation Monitoring System to evaluate the radiological consequences of the accident.

3,2 PERSONNEL PROTECTION AND DECONTAMINATION TEAM LEADER The Personnel Protection and Decontamination Team Leader is re-sponsible for assigning members of the-Personnel Pxotection and Decontamination Team to perform in-plant radiological surveys to evaluate personnel protection requirements.

3.3 OPERATIONS LEADER The Operations Leader is responsible for directing the operation of the Radiation Monitoring System from the Control Room to collect grab samples from the plant vent stack.

4.0 DEFINITIONS None Applicable 5.0 GENERAL The Plant Monitoring Team collects and analyses chemistry samples, collects and analyses airborne activity samples, and may perform radiation and/or contamination measurements to provide data to assist the Radiological Control Director, Plant Operations Director and others in assessing core damage and possible release source terms.

The Personnel Protection and Decontamination Team performs radia-tion, contamination, and airborne activity and hazardous chemical surveys to determine the habitability conditions of areas for the protection of personnel who may need to enter these areas during the emexgency.

6.0 INITIATING CONDITIONS

1. An emergency has been declared and in-plant radiological ox hazardous chemical surveys or plant samples are re-quired.

PEP-331 Rev. 0 Page 5 of"7

APRO11 7.0 PRECAUTIONS LIMITATIONS Comply with personnel protection requirements established by the Personnel Protection and Decontamination Team Leader.

2. Chemistry samples should be taken and analyzed in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or less from the time the decision is made to sample, except for chloride which should be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />, as stated in NRC Regulatory Guide 1 97'. ~

8.0 SPECIAL TOOLS AND E UIPMENT

1. Post Accident Sampling System

2. Air Samplers

3. Protechtor Portable Gas Alarm Draeger Multigas Detector

5. Gas Chromatograph

6. Bi-23P Portable Command and Readout Device for the Radia-tion Monitoring System

7. Gamma Spectrometer 9.0 PROCEDURE STEPS NOTE: These steps may be performed in any order.

The Personnel Protection and Decontamination Team or the Plant Monitoring Team will perform radiation surveys in accordance with normal methods. Surveys shall be documen-ted in accordance with ERC-105.

2. The Personnel Protection and Decontamination Team or Plant Monitoring Team will conduct airborne radiological surveys in accordance with HPP-066, "Preparation and Analysis of Air Samples." Surveys shall be documented in accordance with ERC-105.

3. The Personnel Protection and Decontamination Team or Plant Monitoring Team will perform contamination surveys in accordance with normal methods. Surveys shall be docu-mented in accordance with ERC-105.

The Personnel Protection and Decontamination Team will perform surveys for airborne toxic/flammable gases or chemical in .accordance with HPP-503, "Operation of the Protechtor Por'table Gas Alarm, HPP-504, "Operation of the Gastechtor Portable Gas Alarm", and/or HPP-505, "Operation of the Draeger Multigas Detector." Surveys shall be documented on page 2 of Appendix A to ERC-106, "Confined Space Monitoring Program."

The Plant MoniCoring Team'ill collect containment air samples in accordance with CRC-823 or, if activity levels permit, in accordance with normal plant procedures.

6. The Plant Monitoring Team will collect Reactor Coolant or containment sump samples for laboratory analysis in accordance with CRC-821 for dilute samples and/or CRC"822 for undiluted samples, or if activity levels permit, in accordance with normal plant procedures.

PEP-331 Rev. 0 Page 6 of 7

APR011 9.0 PROCEDURE STEPS The Plant Monitoring Team will collect and analyze Reactor Coolant or containment sump samples for dissolved gases in accordance with CRC-824, or if activity levels permit, in accordance with normal plant procedures.

'8. The Plant Monitoring Team will collect and analyze Reactor Coolant or containment sump samples for pH, conductivity, and/or dissolved Oxygen in accordance with CRC-825 or, if activity levels permit, in accordance with normal plant procedures.

9. The Plant Monitoring Team will analyze Reactor Coolant or containment sump samples for chloride, Boron, and/or isotopic mixture in accordance with CRC-826, CRC-827, and/or CRC-828, respectively, or, if activity levels permit, in accordance with normal plant procedures.

10. The Plant Monitoring Team will prepare and analyze air samples for isotopic content in accordance with RCP-651 and RCP-.701, respectively.

The Plant Monitoring Team will analyze containment air samples for Hydrogen in accordance with CRC-515, "Opera-tion of the Gas Chromatograph," if the containment Hydrogen monitor is inoperative.

12. The Plant Monitoring Team will document all sample analysis in accordance with CRC-004, "Chemistry Logs &

Records."

13. The Plant Monitoring Team will obtain Radiation Monitoring System data from local RM-80 panels using the RM-23P in accordance with OP-'118 if individual monitors are opera-tional but the RM-11 consoles are not.

14. If area radiation levels and expected sample source terms permit, the Plant Monitoring Team may collect and analyze additional plant system samples using normal plant pro-cedures.

10.0 DIAGRAMS ATTACHMENTS None Applicable PEP-331 Rev. 0 Page 7 of 7

~c 0

APR014

CAROL1NA POWER 6 LIGHT COMPANY SHEARON HARRIS NUCLEAR POVER PLANT 4

",5 PLANT OPERATING MANUAL VOL%K 2

~ I PART I ~

4 5'ROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-341

'4'j C

TITLE: MANUAL DOSE CALCULATION r4] REVISION 0 4

cQ

~ 4J 4

APPROVED:

Signature Date 4 ~

TITLE:

V4 4

.:-3 PEP-341 Rev. 0 Page 1 of 20

APR014 TABLE OF CONTENTS

~Pa e Table of Contents 2 Lis- of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4 2.3 Other References 4 3.0 RESPONSIBILITIES 4 3.1 Site Emergency Coordinator 4 3.2 Dose Projection Team Leader 5 4.0 DEFINITIONS 5 5.0 GENERAL 5 5.1 Calculations 5 5.2 Release Pathways 5 6.0 INITIATING CONDITIONS 6 7.0 PRECAUTIONS AND IIMITATIONS 6 8.0 SPECIAL TOOLS AND EQUIPMENT 6 9.0 PROCEDURE STEPS 6 10.0 DIAGRAMS/ATTACHMENTS 12

1. SHNPP Gaseous Waste Streams 13

2. Manual Dose Projection Record Sheet 14

3. Meteorological Dispersion (X/Q) Value at SHNPP Plane Boundary (2500 Fc = 761 M) 15

4. Dose Conversion Factors 16

5. Extrapolation Factor for Es imating, Doses Beyond SHNPP Plant Boundary (2500 Ft) 17

6. SHNPP Exclusion Area Boundary Plan 18

7. Source Term and Dose Conversion Factor Vorksheet 19

8. Affected Downwind Sectors 20 PEP-341 Rev. 0 Page 2 of 20

APR014 LIST OF EFFECTIVi PAGES

~Pa e Revision 1 through 20 PEP-341 Rev. 0 Page 3 of 20

APR014

l. 0 PURPOSE llDose The purpose of this procedure is to implement Section 4.4.3, Projection," of the SHNPP Emergency Plan.

This procedure provides inst uctions to perform a manual calculation of projected off-site doses. This procedure is used when computer-ized systems are not available, and therefore PEP-342 or PEP"343 cannot be used. It can be used when various systems or pieces of equipment are not functioning, or when monitor zeadings are suspect oz off scale.

2.0 RErERENCES 2.1 EMERGENCY PLAN REFERENCES

1. Section 4.4.3, "Dose Projection"

2. Annex B, "Technical Basis of Emergency Dose Projection Program" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-101, "Initial Emergency Actions"

2. PEP-216, "Dose Projection Team Leader"

3. PEP-342, "Automation of Dose Projection Procedure - ERFIS"

4. PEP-343, "Automation of Dose Projection Pr'oceduze - IBM PC11

3. PEP-104, "Protective Action Recommendations"

6. Plant Special Order, "Emergency Phone List"

2. 3 OTHER REFERENCES

1. USNRC Regulatory Guide l.r109

2. SD-118, "Radiation Monitoring" 3.0 RESPONSIBILITIES 3.1 SITE EMERGENCY COORDINATOR The Site Emezgency Coordinator - Control Room is responsible for implementing been activated.

this procedure if the Technical Support CEnter has not PEP-341 Rev. 0 Page 4 of 20

APR014

3. 0 RESPONSIBILITIES 3.2 DOSE PROJECTION TEAN LEADER

~

The Dose Projection Team Leader is responsible. for implementing this after the Technical Support Center is activated.

proceduxe 4.0 DEFINITIONS None Applicable 5.0 GENERAL 5.1 CALCULATIONS The dose rate due to gaseous effluents at a given point downwind resulting from an identified release is calculated by the formu)a:

D = X/Q'Q'DCF~R where D is the dose xate in Rem/hx',

X/Q is the atmospheric dispexsion factor in units of

-~ ~

sec/H at the site boundary, Q is the souzce term in Ci/sec, Rem~M 4

DCF is the dose conversion factor in-------

~ and R Hr.Ci, is the combined lateral and veztical dispersion factor that ad)usts X/Q for distance fxom the xelease point and the p)ume center line.

The total dose rate at a given point is ca)culated by summing the dose rates for each identified re)ease pathway, each of which is calculated by the above fozmu)a.

The affected downwind sectors and the atmospheric dispersion factors (Z/Q) at a given distance downwind aze determined directly from tabular data as functions of atmosphyzic stability and wind speed.

Isotopic mix affects both the dose conversion factor (DCF), and the souzce term (Q) if source term is determined from an installed radiation monitor. If an isotopic analysis is available, it is used to calcu).ate both the dose conversion factor and the sou"ce term.

If isotopic analysis is not available, the dose conversion factor is determined from tabular data as a function of time after reactor shutdown. The table assumes a design basis isotopic release mix of 100 percent of the core gap inventory of noble gases and 25 percent of the halogens, and ad)usts the mixture for decay. When determined from installed radiation monitors, determination of source term assumes that noble gas detectors respond to noble gas activity only, that the containment area monitors respond to both iodine and noble gas activity, and that iodine activity is 15% of the noble gas activity.

PEP-341 Rev. 0 Page 5 of 20

APR014 E . 0 GENERAL 5.2 RELEASE PATHWAYS 5.2.1 Containment Leakage directly to the atmosphere is assumed to be occurring at the rate of 0.1 percent of the free volume per day for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following an accident and at 0.05 percent per day thereafter.

5.2.2 Primary to secondary leakage is assumed to be released to the atmosphere via the atmospheric steam dump valves and/oz steam generator relief valves whenever there is indication that any of these valves are open. The source tezm foz this release is determined from the measured or design flow rate through these valves, and either readings on the main steam line radiation monitors or analysis of a condensed steam sample.

5.2.3 Releases are assumed to be occurring at some or all of the four plant exhaust ventillation stacks in all cases. The source terms for these releases are determined by either

, measured or design ventillation flow zates and measured activity concentrations'.0 INITIATING CONDITIONS Immediately after recognition that an unplanned off-site release has occurzed, could have occurred, or may occur, this procedure should be implemented if automated dose projection methods are not available.

7.0 PRECAUTIONS AND LIMITATIONS

1. Thyroid dose projections made ~sing default values for isotopic mix are extremely conservative (i.e., give high results).

2. These projections pertain to the radioactive gases at ground level and do not include radiation from an overhead cloud that may contribute to the whole body dose at ground level. Undez certain meteorological conditions (elevated release and E, F, or G stabili y classes), direct radia-tion from an overhead plume may produce somewhat higher doses than those calculated by this procedure.

8.0 SPECIAL TOOIS AND E UIPMENT

1. Scientific calculator that can handle exponential

-6 functions (i.e., 2 x 10 ),

9.0 PROCEDURE STEPS 9.1 Enter the date and time on a blank copy of Attachment 2, "Manual Dose Projection Record Sheet".

PEP-341 Rev. 0 Page 6 of 20

APR014 9.0 PROCEDURE STEPS 9.2 Obtain wind speed, wind direction and atmospheric dispersion factor (K/Q) using one of the following methods, which are listed in order of preferred use.

1. Call Radiation Control and request the wind speed, wind direction, and atmospheric dispersion factor from the Radiation Monitoring System report processor (RM"21).

Record those parameters on Attachment 2.

2. Call the Corporate Meteorology Center and request the current wind speed, wind direction, and atmospheric stability class for the Harris plant. Record those parameters on Attachment 2. Determine the atmospheric dispersion factor (K/Q) from the table in Attachment 3 and record it on Attachment 2.

3. Determine wind speed, wind direction, and atmospheric conditions from visual observations outdoors and use the table below to determine stability class.

Atmospheric Conditions Clear Cloudy Clear Cloudy Wind ~Da ~Da ~Ni hs ~Ni ht ~Rainin Light or Calm B C E p D Moderate or Stzong C D D D D Circle either "Clear", "Cloud ", or "Raining", and either "Light/Calm" or "Moderate/Strong" on Attachment 2 to indicate the observed conditions, and record the selected stability class. Determine the atmospheric dispersion factor from Attachment 3, using four mph for light/calm winds or nine mph for moderate/strong winds, and record on Attachment 2.

if 9.3 Determine the activity concentration for one release pathway using the following step's.

NOTE: The available methods for obtaining the data are listed in order of preferred use to obtain the most accurate Child Thyroid dose projection.

Obtain the results of an isotopic analysis of a grab sample. Transcribe the activity concentration onto Column 2 of Attachment 7, "Source Term and Dose Convezsion Factor Worksheet" for each isotope listed. Ensure that the activities are in units of Ci/cc. Multiply pCi/cc by 1.0E-6 to convert to Ci/cc if necessary.

PEP-341 Rev. 0 Page 7 of 20

APR014 9.0 PROCEDURE STEPS

2. If the release pathway is containment leakage, obtain the containment high range area radiation monitor reading in R/hr. Multiply by (9.43E-10) to obtain Ci/cc noble gas, and by'2.78E-10) to obtain Ci/cc Iodine, and record all

3. 'fthree values on Attachment 2.

the release pathway is primary to secondary leakage via steam dump or relief valves, obtain the main steam line radiation monitor reading in uCi/cc, multiply by 1.0E-6 to convert to Ci/cc, and record this value on Attachment 2 as the noble gas activity. Multip}y the noble gas activity by 0.15 to obtain Iodine activity, and record on Attachment 2. Circle A, B, or C on Attachment 2 to indicate which steam line the reading is for.

4., If the release pathway is the ventillation exhaust, obtain the noble gas radiation monitor reading in yCi/cc for the appropriate vent stack, multiply. by 1.0E-6 to convert to Ci/cc, mu)tiply by 0.15 to obtain Iodine activity, and record both results on Attachment 2 in units of Ci/cc.

Circle 1, 3A, 5, or 5A on Attachment 2 to indicate which vent stack the reading is for.

9.4 Determine the release flovrate for the pathvay being evaluated using one of the following steps. Within each step, the available methods are listed in order of preferred use.

l. If the release pathway is containment leakage, select 736 cubic centimeters per second (cc/sec) if it is less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> since the accident began, or 368 cubic centimeters per second if it, is greater than 24 houzs since the accident began. Record the selected value on Attachment 2.

2. If the release pathway is primary to secondary leakage via steam dump or relief valves:

Obtain the steam flov reading in units of thousand pounds mass per hour (KLSM/HR) for the main steam line being evaluated and record on Attachment 2.

OR Record on Attachment 2 the quantity of each type of valve that indicates open. Multiply the number of valves open by the design flov rates (given on Attachment 2) for each open valve to obtain the total flow rate.

PEP-341 Rev. 0 Page 8 of 20

APR014 9.0 PROCEDUPZ STEPS

~ Calculate the source terms by multiplying the previously determined flow rate in cc/sec or mg/sec by the specific activities in Ci/cc. Use noble gas activity for the whole body calculation and Iodine activity for the child thyroid calculation. Record the products in Ci/sec on Attachment 2.

~ Multiply the source term by the dose conversion facto" and record the product on Attachment 2.

9.6 Calculate the child thyroid dose commitment rate and the whole body dose rate at the site boundary by mulitplying the source term ~ dose conversion factor products (Q~DCF) by the previous-ly determined atmopspheric Dispersion Factor (X/Q). Record the product on Attachment 2.

NOTE 'his gives the projected center, which is defined dose as at 2500 feet from the plant the site boundary for purposes of this procedure.

9.7 Calculate the projected dose rates at the Exclusion Area Boundary by multiplying the Child Thyroid Dose Commitment Rate and Whole Body Dose Rates at the site boundary by the appropri-ate extrapolation factor from Attachment 5 for the previously determined stabilty class. Record the product on Attachment 2.

9.8 Determine and record on Attachment 2 the known or estimated duration of the release in hours. If the duration is unknown, assume one hour. Notify the Radiological Control Director of the projected dose rates and duration of both the Site boundary and Exclusion Area boundary.

9.9 Calculate the integrated doses at the Exclusion Area boundary by multiplying the dose rates calculated in step 9.7 by the duration of release. Record the product on Attachment 2.

No"ify the Radiological Control Director of the projected doses, then repeat steps 9.7 and 9.9 to obtain the dose rate and integrated dose at distances .of two, five, and ten miles.

9.10 If requested, determine the dose rates and/oz integrated doses at additional distances in the same manner.

9.11 If releases from additional pathways are known or suspected to be occurring, repeat steps 9.1 through 9.10 foz each pathway.

The total dose "ates and integrated doses at any given point downwind are the sum of the dose rates and integrated doses calculated for each release pathway.

9.12 If requested, estimate the downwind sectors affected by con-sulting Attachment 8, and zecord them on Attachment 2.

PEP-341 Rev. 0 Page ll of 20

APR014

10. 0 DIAGRA"1S ATlACHMENTS SHNPP Gaseous Waste Streams (reference 2.3.2)

2. Manual Dose Projection Record Sheet

,3 Meteorological Dispersion (X/Q) Value at SHNPP Plant Boundary (2500 Ft = 761 M) (reference-later)

4. Dose Conversion Factors (reference-2.3.1)

Extrapolation:actor for Estimating Doses Beyond SHNPP Plant Boundary (2500 Ft) (reference-later)

6. SHNPP Exclusion Area Boundary Plan

7. Source Term and Dose Conversion Factor Worksheet

8. Affected Downwind Sectors PEP-341 Rev, 0 Page 12 of 20

0" WI'0 RAB FHO WASTE I'IIOCESSING DLUO IlEACTOR AUXILIAIIY FUEL IIANDLINODLDO OLD TunOINE aLOO VENT STACK SA ett htM ISV O'IN COtlD ENSATE VACUUMPUMP VIASTE PAOCESSINO OLDO VENT STACK 5 WPB IIOT 4 COLD LAUNDllY hEM hEM IWV.IIII IYPB OFFICE AIIEAEXHAUST WPO COLD LAUNDRYDIIYERS WPB OFFICE AREA iYPO CONTllOL AOOM SMOXE EXIIAIJST WPO CIIILLKABOOM EXIIAUST WPB OKNERAI. AREA KXIIAUST WASTE PROCESSINO AREAS FILTEflED KXlfhUST WASTE OAS DECAY TANKS WASTE PIIOCESSINO OLOO VENT STACK 5A HC NRM IWV $ 04P WPO SWITCHQ Ehfl ROOM EXHAUST WPB IIVACEOUIP~ ROOM EXHAUST IYPB I'ERSONNEL HANDLltIOFACILITYEXHAUST WPO IIOT SI LOW ACTIVITYKXIIAUST WPO LAB AflEAEXlthUST PLANT VENT STACK 1 W ht hIM.IAVPII>lh 0 CONTAINMENTPfIE KNTRY PUflOE h IM-I h Vi>I I I F tIO NORMAI.KXIIAVSTNORTII AA8 NORMA!. EXIIAUST haM-IAV.IIIIh ngM C) FIIB NORMAL KXtthuST SOVTII AAS EMERGENCY EXlfhuST tlRM.It4$~ I ~ FHB NOflMALEXIIAUST IOPEA FLI SOUTII DAO VENTILATIONSYSTEM QgM FHB tIOflMALKXHAUSl IOPER. FL) SOUTII IIYDROGENPURGE NCM ll!M-IF4II~ Ih 'I*

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ATI'ACHMENT 2 MANUAL DOSE PROJECTION RECORD SHEET TIME WIND SPEED mph WEND DERRCTEDN(from)

Observed Wind: Light/Calm or Moderate/Strong Observed Condition: Clear or Cloudy or Raining Stability Class m'ec Atmospheric Dispersion Factor (X/Q)

Cont ainment: R/hr Noble Gas Ci/cc Iodine Ci/cc Flow cc/sec Main Steam A or B or C: Noble Gas Ci/cc Iodine Ci/cc PCRV open x 462 = KLBM/HR SRV's open x 970 = KLBM/HR Aemospherfo Dmlps open x 709 = ZLBM/HR Uncorrected Steam Flow mg/sec or cc/sec Vent Stack: 1 or 3A or 5 or 3A Noble Gas Ci/cc Iodine Ci/cc Flowrate cfm x 4772 = cc/sec EIRM'm'ARR REM~m Child Thyroid: sec = HriSEC DCF QDDCF

'EM'm~

Ci. REM+m Whole Body: Ci'HR ~ sec = HriSEC DCF QDDCF Duration of Release Hours Dose Rate (Rem/hr) Integrated Dose (Rem)

Distance Child Th roid Whole Bod Child Th roid Whole Bod Site Boundary Exclusion Area Boundary .

2 miles 5 miles 10 miles PEP-341 Rev. 0 Page 14 of 20

APRD14 ATTAC1BfENT 3 METEOROLOGICAL DISPERSION (X/Q) VALUES AT S~~oP EP~DARy (2~300 PT ) GROUND LEVEL RELEASE Z/Q Values by Atmospheric Stability Type (Units: Sec/m )

Mind Speed mph m/sec A D , G 1 0.4 1.8E-05 7.7E-05 1.7E-04 3. 1E "04 5.9E"04 1.3E-03 2.0E-03 2 0.9 9. 1E-06 3.9E-05 8.5E-05 1. 6E-04 3.0E-04 6.7E-04 9.9E-04 3 1.3 6.0E-06 2.6E-OS 5.6E-05 1. OE-04 2.0E-04 4.5E-04 6.6E-04 4 1.8 4.3E-06 1.9E-05 4.2E-05 7. BE "05 1.3E-04 3.3E-04 4.9E-04 5 2.2 3.6E"06 1.5E-OS 3.4E-OS 5. 1E-05 6.9E-05 2.7E-04 3.8E-04 6 2.7 3.0E-06 1.3E-05 2.8E-OS 4. 5E-05 6.8E<<OS 2.4E-04 3.1E-04 7 3.1 2.6E-06 1.1E-05 2.4E-OS 4.4E-05 7.5E-05 2.0E"04 2.8E"04 8 3.6 2.3E"06 9.7E-06 2.1E-05 4.2E"05 7.4E-05 1.8E-04 2.5E-04 9 4.0 2.0E-06 8.6E-06 1.9E"05 4.0E-05 7.2E-05 1.7E-04 2.2E-04 10 4.3 1.8E-06 7.7E"05 1.7E-05 3.8E 05 7.0E-05 1.3E"04 2.0E-04 11 4.9 1.6E-06 7.0E-06 1.5E"05 3.7E-05 6.8E-05 1.2E-04 1.8E-04 12 5.4 1.5E-06 6.4E-06 1.4E-OS 3.4E-OS 6.2E-05 1. IE"04 1.6E"04 13 5.8 1.4E-06 6.0E-06 1.3E-05 3.2E-OS 5.7E-05 1. OE-04 1.5E-04 14 6.3 1.3E-06 5.5E-06 1.2E-OS 3.0E-05 5.3E-05 9.4E-OS 1.4E>>04 15 6.7 1.2E-06 5.2E-06 1. 1E" 05 2.8E-05 S.OE-05 8.7E-OS 1.3E-04 7.2 1.1E-06 4.8E-06 1. 1E-05 4.6E-OS 2.6E-OS 8.2E-05 1.2E-04 17 7.6 1.1E-06 4.6E-06 1. )E-05 2.4E-OS 4.4E-05 7.7E-05 1.2E"04 18 8.0 1.0E-06 4.3E-06 9.4E-06 2.3E-05 4.1E-05 7.3E-05 1.1E-04 19 8.3 9.3E-07 4. 1E-06 8.9E-06 2.2E-05 3.9E-05 6.9E-OS 1.0E-04 20 8.9 9. 1E-07 3.9E"06 B.SE-06 2.1E-05 3.7E-05 6.5E-05 9.9E-05 21 9.4 8.6E-07 3.7E-06 8. 1E" 06 2.0E-OS 3.5E-OS 6.2E-05 9.4E-05 22 9.8 8.2E"07 3.5E"06 7.7E-06 1.9E-05 3.4E-05 6.0E-OS 9.0E-OS 23 10.3 7.9E-07 3.4E-06 7.4E-06 1.8E-OS 3.2E"05 5.7E"05 8.6E-05 24 10.7 7.5E-07 3.2E-06 7.1E-06 1.7E-OS 3.1E-05 5.5E-05 8.2E-05 25 11.2 7.2E-07 3.1E-06 6.8E"06 1.7E-05 3.0E-05 5.2E"05 7.9E-05 26 11.6 7.0E-07 3.0E-06 6.5E-06 1.6E-OS 2.9E-OS S.OE-OS 7.6E-05 27 12. 1 6.7E"07 2.9E-06 6.3E-06 1.5E-05 2.8E-05 4.8E-OS 7.3E-05 28 12.5 6.5E-07 2.8E"06 6.0E-06 1.5E-05 2.7E-05 4.7E-OS 7.0E-05 29 13. 0 6.2E-07 2.7E-06 5.8E-06 1.4E-OS 2.6E-OS 4.5E-05 6.8E"05 30 .13. 4 6,0E-07 2.6E-06 5'.6E-06 1.4E-05 2,5E-05 4.4E-OS 6,6E-05 NOTE: If wind speed is between adjacent values, use the lower value to find X/Q.

~-341 Bev. 0 Page 15 of 20

APR014 ATTACHMENT 4 DOSE CO%'ERSION FACTORS Time After Reactor Shutdovn Dose Conversion Pactor (DCF)

~hours W~hole Bod 0.0 6.33E+5 4.73E+2 0.5 7.14E+5 4.25E+2 1.0 7.89E+5 3.96E+2 2.0 9. 18E+5 3.56E+2 ~

5.0 l. 18E+6 2.61E+2 8.0 1.35E+6 1.89E+2 12.0 1.53E+6 1.24E+2 24.0 1.95E+6 4. 32E+1 72.0 2.92E+6 1.77E+1 96.0 3. 15E+6 1.77E+1 120 3.28K+6 1.77E+1 144 3.35E+6 l. 77E+1 168 3.39E+6 1.77E+1 192 3.40E+6 1.77E+1 216 3.41E+6 1.77E+1 240 3.41E+6 1.77E+1 0240 3.42E+6 1. 77E+1 PEP<<341 Rev. 0 Page 16 of 20

ATTACHMENT 5 EXTRAPOLATION FACTOR FOR ESTIMATING DOSES BEYOND SHNPP BOUNDARY (2,500 FT) GROUND LEVEL RELEASE Distance from Plant Extrapolation Ratios b Atmosoheric Stabilit Class Miles IR A B C D E F G 1 1.6 1. 4E-01 2.3E-01 2.6E-01 3.5E-01 3.7E-01 3.7E-01 3.7E-01

• 1.3 2 1

~ 1.1E-01 1. 4E-01 1.6E-01 2. 4E-01 2 'E-01 2.7E-01 2.8E-01 2 3.2 7.2E-02 5.8E-02 7.6E-02 1.4E-01 1.5E-01 1.5E-01 1.5E-01 3 4.8 5.1E-02 2.6E-02 3.7E-02 7,7E-02 8.8E-02 9.2E-02 1.4E-01 4 6.4 3.9E-02 1.4E"02 2.2E"02 5.2E-02 6.1E-02 6.SE-02 1.0E-01 S 8.0 3.9E-02 1.0E-02 1.5E-02 3.9E-02 4.6E-02 4.9E-02 8.0E"02 6 9.7 3.9E-02 9.2E-03 1.1E-02 2.9E-02 3.6E-02 3.9E-02 6.5E-02 7 11.3 3.9E-02 9.2E-03 7.6E-03 2.3E"02 2.9E-02 3.3E-02 5.5E-02 8 12.9 3.9E-02 9.2E-03 6.5E"03 1.9E-02 2.SE-02 2.7E-02 4.6E-02 9 14.5 3.9E-02 9.2E-03 5.8E-03 1.6E"02 2.2E-02 2.4E-02 4.0E-02 10 16.1 3.9E-02 9.2E-03 5.5E-03 1.4E-02 1.9E-02 2.2E-02 3.5E-02

• Exclusion Area Boundary PEP-341 Rev. 0 Page 17 of 20

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APRO14

'I t ATTACHMENT 7 e

SOURCE TEAM AND DOSE CONVERSION FACTOR WORKSHEET re t

ej (2) (3) (4) (5) .(6)

AO A DCZ Specific Decay Activity Decay Corrected Dose of Sample Constant Activity Conversion Isotone Ci/cc for Isoto e Ci cc Factor ~

DCFig 1-131 3.59E"3 3.42E+6 1"132 3.07E-01 4.08E+4

,4 1-133 3.41E-2 8. 11E+5 e,

1-134 7.97E-1 1.07E+4 1-135 1.04E-1 1.67E+5 Rem m*

Child Thyroid Total Source Term Dose Conversion Factor Product = Hm Sec me Kr-83m 3.79E-1 8. 62E "3 Kr"85 7.38E-6 1.19E+0 Kr-85m l. 55E-1 8.44E+1

'Re Kr-87 5.46E-1 4.78E+2 Kr-88 2.44E-l 1.23E+3 Kr-89 l. 31E-1 1.09E+3

~ e e

Xe-131m 2. 44E-1 4.47E+0 Xe-133 5. 50E-3 1.78E+1 Xe-133m 1. 32E-2 1.54E+1 Xe-135 7. 61E" 2 1.52E+2 Xe-135m 2. 71E+0 2.28E+7 Xe-138 2.94E+0 6.71E+2 Rme t hole Body Total Source Term Dose Conversion Factor Product = m'z'Sec PEP-341 Rev. 0 Page 19 of 20 e

e e

ATTACIIIIENT 8 AFFECTED DOHNMIND SECTOAS MIND A FEGTE DOMNHIND SECIOAS 0 I AEGT IONS FAOH 4 SS S~SS S S SM SM Tl 0 X 0 0 X X X 0 0 X X 0 0 X X X 0 OI 0 X 0 -1 0 X X 0 X X 0 0 X X 0 X X 0 X X 0 0 X X X 0 869 2 I 0 0

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C) 0 ohl

APRO15 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-343 TITLE: AUTOMATION OF DOSE PROJECTION - IBM PC REVISION 0 APPROVED:

Signature TITLE:

~z'~.W~

PEP-343 Rev. 0 Page 1 of 25

~

~

APR015 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 through 25 0 PEP-343 Rev. 0 Page 3 of 25

APR015

5. 0 GENERAL The computer program DOSE uses the same calculational methods to project offsite doses as used in PEP-341, "Manual Dose Calculation."

The program calculates meteorological dispersion factors instead of using tabulated data. Section 9.1 describes the use of this program. Section 9.2 provides instructions for using the computer'o access the plant meteorological station by modem and convert the.

digital pulses to useable data. Section 9.3 provides instructions foz using the computer to obtain meteorological forecast data by modem from the corporated meteorological comput: er. Section 9.4 describes how to use the MET pzogzam to determine atmospheric stability c1ass from National Weather Service data.

6.0 INITIATING CONDITIONS

1. The Shift Foreman requires an offsite dose projection to determine whether an event should be classified as an emergency, or

2. An emergency has been declared.

7.0 PRECAUTIONS AND LIMITATIONS

l. Unless an actual isotopic mix is entered, the calculation for thyroid dose projection will most probably result in a gross overestimation of the thyroid dose commitment, which could zesult in recommending protective actions foz the public that would later prove to be unnecessary.

Consistent with providing timely information to the Site Emergency Coordinator, dose projections should be based on isotopic analysis of a grab sample.

8.0 SPECIAL TOOLS AND E UIPMENT

1. IBM Personal Computer with at least one disk drive, Hayes Smart modem, printer (optional), and plotter (optional)

2. Sheazon Harris Emergency Dose Projection Diskette 9.0 PROCEDURE STEPS NOTE: If you do not already know the stability class and vill want to determine it using another section of this procedure, perform that section prior to be'ginning Section 9.1. *"

NOTE: 'ou are in the DOS mode if you are not currently running a pzogram." You know you are in the DOS mode if the sequence "A appears in the left, of the screen. If you aze currently running a program, you can exit to DOS by simultaneously pressing the CTRL and SCROIL LOOK keys.

When the flashing prompt appeazs, enter "SYSTEM" then press RETURN.

PEP-343 Rev. 0 "

Page 5 of 25

APR015 9.0 PROCEDURE STEPS rO

'O O

9.1 DOSE PROJECTIONS (Cont d)

9. If a "1" was chosen for the pxevious question, the screen will display, "SOURCE TERM" and units of Curies, otherwise the screen will display "RELEASE RATE" and units of Curies/second, Ente'r the appropriate term in these units.

If the units chosen were CURIES/SEC, the screen will display "ESTIMATED DURATION OF RELEASE (HOURS) ~ EF UNCERTAIN OF DURATION ENTER 1 HOUR." By entering the duzation of release, a total curie amount can be derived.

If the duration is unknovn, enter 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This allows for easier correction later vhen the actual duration of release is know.

10. If the nuclide mix is unknown, the screen will display "TIME SINCE REACTOR SHUTDOWN (HOURS)." Enter this time in units of hour<.

The screen will display "STABILITY CLASS (A-G)." Enter the appropriate stability class.

The scx'een will display "VEND VELOCITY (MPH)." Enter the J'2.

appropriate vind velocity in units of miles per hour.

13. The screen vill display "DIRECTION WIND BLOWING FROM (DEGREES)." This is used on the isopleth plot to indicate the direction of the plume travel. Be sure to enter the direction the vind is blowing from similar to what is given in the meteorology pxogram.

,O The screen will display "STANDARD DISTANCES ARE SITE

'I Oi rOi BOUNDARY (2500 ft), EXCLUSION AREA BOUNDARY (7000 ft) 2, o r 5, 10 MILES. DO YOU VANT TO USE THESE (YES OR NO)." The program is asking whether the user wishes to look at centerline doses corresponding to the specific distances or to look at centerline doses corresponding to downwind distances yet to be specified. Enter YES ox NO, whichever is appropriate. Choosing nonstandard distances allows the usez to obtain a more refined isopleth.

15. If a NO vas entered to the previous question, the screen will display "MAXIMUM DISTANCE (MILES)." Enter the maximum downwind distance in miles for which centerline doses are desired. The screen vill then display "DOWiiVIND INCREMENT (MILES)." Enter the incremental distance in miles foz vhich centerline doses out to the maximum downvtnd distance aze desixed.

PEP-343 Rev. 0 Page 7 of 25

APRO15 9.0 PROCEDURE STEPS 9.1 DOSE PROJECTIONS (Cont'd) reference arrow exists on the map you are using, line up the tvo taking note of the proper polarity. The screen vill nov display "DO YOU MANT TO PLOT THE SAME ISOPLETH(S) .

AGAIN (YES OR NO)." If another plot is desired enter YES and return to Step 20.

NOTE: If the plotter is absent or inoperative, the program vill continue after a short delay.

23. The screen will clear, then display, "VILL NUCLIDE AMOUNTS BE IN CONCENTRATION (C) OR PERCENT (P)." If the concentrations of the nuclides are known, enter a C; if the percents are known, enter a P.

24. The screen will display, "ENTER TIME FROM SAMPLE TO RELEASE (HOURS). IF UNCERTAIN OF TIME EiKER 3 HOURS."

Enter the appropriate time between sample time and expected or actual release time. If the release occurred before the sample was taken, a negative time in hours vill be accepted. If uncertain, enter 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

25. The screen will clear and a message displayed at the top reading "ENTER NUCLIDE...THEN RETURN." This instzucts the user how to enter the nuclides and their amounts. The screen will also display titles for the nuclides and the amounts.

26. NOTE: The total X, need not exactly equal 100' a 2i, tolerance is built in: i.e., a total X between 98-102'5 is acceptable. Vhen the cursor is under the nuclide title, enter the nuclide in its common form in capitals, e.g.,

KR-85, XE-133, I-131, etc. Press RETURN and the cursor will shift over under the amount title. Enter the appropriate ~ or concentration, then RETURN. If dealing with percents, the input will cease when 100io has been reached. In any other situation, pressing the RETURN key when prompted for a nuclide vill end input.

27. The program vill display the sample to release time, the vhole body or thyroid DCF, and the units. A message vill also be displayed instructing the user to press any key to continue. After this, return to Step 7..

28. The screen will display a parameter menu and ask you if vish to make any changes. The instructions at the bottom of the screen should be followed to (1) change any parameter, (2) re-run the program, or (3) terminate the program. Once the parameter screen has been displayed, there is no need to start again at the beginning of the program unless to specify another site.

PEP-343 Rev. 0 Page 9 of 25

APR015 9.0 PROCEDURE STEPS 9.2 METEOROLOGICAL DATA (Cont'd)

Upper wind speed pulses, Upper wind direction sine pulses.

Upper wind direction cosine pulses.

Lower wind speed pulses.

Lower wind direction sine pulses.

Lower wind direction cosine pulses.

Temperature pulses.

Differential temperature 1 pulses.

Differential temperature 2 pulses.

8. The pulses and the usable information they represent will then be displayed on the screen. At the bottom of the screen two messages will be flashing. The first instructs the user to type SHIFT (the upward arrow on the keyboard) and PrtSc if In this case, they want a copy of what is on the screen.

make sure the printer is on. When you are done reviewing the meteorological data,'press any key as instructed by the second message and you will return to the dose projection program at Step 2.

9.3 METEOROLOGICAL FORECAST

1. When it is necessary to receive a forecast from the CP&L Corporate Meteorological staff, the user has the option of using the computer to obtain this information. If this is desired, type TAIZ then RETUR% when in the DOS mode. An introduction to the program is displayed and as instructed, press any key to continue.

2. Establish verbal communication with meteorological personnel to inform them that you want a forecast.

NOTE: It is advisable to maintain this separate communication line until the forecast is satisfactorily received.

3. If the meteorological unit decides to call your computer, then proceed to Step 5; otherwise, continue below.

PEP"343 Rev. 0 Page 11 of 25

APR015 9.0 PROCEDURE STEPS 9.3 METEOROLOGICAL FORESCAST (Cont'd)

Inform the meteorological personnel that the forecast vas correctly received and terminate verbal communication.

Reset the modem. Press the Alt key and X key simultaneously and enter Y for yes in answer to the next question in order to exit TALK.

12. To obtain a hard copy of the forecast, ensure you are in the DOS mode then enter FORECAST and press RETURN. The screen vill clear and the introduction to the program vill be displayed. As instructed, press any key. Next you will be asked for the forecast file name. Enter the forecast file name as you specified it in Step 7.

13. The program will search for the file and upon finding it will display it on the screen and direct it to the line printer.. When the. printer stops, the forecast is complete.

9.4 NATIONAL WEATHER SERVICE METEOROLOGY This section is mainly of use when meteorological information cannot be obtained from the MET tower or the CPBL Corporate Meteorological staff. The telephone number to contact the National Weather Service can be found in the Plant Special Order, "Personnel and Telephone Listing."

2. While in the DOS mode, enter NWS then press RETURN.

The screen vill clear and an introduction to the program vill be displayed. As instructed, press any key to continue.

3. The screen will display "WIND SPEED (KNOTS)." Enter the wind speed in these units.

The screen'ill display "CLOUD COVER (TENTHS)." Enter the cloud cover in tenths; i.e., a totally overcast sky would have a cloud cover equal to 10 tenths.

The screen will display "CLOUD CEILING (FEET)." Enter the cloud ceiling in feet. If there is no cloud ceiling, enter 99,999 feet.

I

6. The program now computes the stability class and displays it along

'age with the information entered and the time and date. If you want a hard copy, enter SHIFT and PrtSc.

This marks the end of the program.

PEP-343 Rev. 0 13 of 25

APR015 ATTACHMENT 1 VERIFICATION OF "DOSE" A COMPUTER PROGRAM FOR EMERGENCY DOSE PROJECTIONS This exhibit is intended to provide a means to ensure that "DOSE,"

the dose projection program designed for the IBM Personal Computer, is working properly. This is demonstrated by duplicating expected results of known computer inputs. These results can also be validated by comparison to manual calculations for the same input.

Three different test cases are presented so that a number of alternate paths within this program can be tested. The test cases with their expected results follcw.

PEP-343 Rev. 0 Page 15 of 25

APR015 ATTACHMENT 1 (Continued)

SHEARON HARRIS NUCLEAR POWER PLANT SITE WHOLE BODY DOSE PROJECTION 13:15:44 08-.02-1984 STABILITY CLASS; E WIND VELOCITY: 5 (MPH) BLOWING FROM 0 (DEGREES)

SOURCE TERM: 6804000 (CURIES)

ESTIMATED DURATION OF RELEASE: 1 (HOURS)

RELEASE HEIGHT: 0 (METERS)

TIME FROM SAMPLE TO RELEASE: 2 (HOURS)

A DCF AT POINT OF RELEASE: 178.1837 (REM/HR)/(CURIE/M 3)

DISTANCE DOSE X/Q (METERS/MILES) (REMS) (SEC/METERS 3) 1608 / 1.00 2.04E+01 6.05E-05 3216 / 2.00 7.25E+00 2.15E-05 4824 / 3.00 4.08E+00 1.21E-05 6432 / 4.00 2.74K+00 8.14E-06 8040 / 5.00 2.02E+00 6.01E-06 9648 / 6.00 1.58E+00 4.70E-06 11256 / 7.00, 1.29K+00 3.82E-06 12864 / 8.00 1.08E+00 3.20E-06 14472 / 9.00 9.22E-01 2.74E-06 16080 / 10.00 8.02E-01 2.38E-06 (yC/cc) (HOURS)

ISOTOPE CONCENTRATION HALF"LIFE DCF ADJ. DCF KR-85 10 93910 1. 19 . 1958915 KR-85M 10 4.48 84.4 10 19665

~

KR-87 10 1.27 478 26.42047 KR-88 10 2.84 1230 124.2889 KR-89 10 .053 1090 7.882991E-10 XE" 131M 10 284.16 4.47 .7322582 XE-133 10 125.88 17.8 2.898099 XE-133M 10 52.56 15,4 2.469127 XE-135 5 9.109999 152 10.74521 XE-135M 5 . 256 228 8.357615E-02 XE-137 5 .0638 102 3.085829E-09 XE-138 5 .2355 671 .1535296

.1 REM ISOPLETH COORDINATES (+/" METERS)

X Y 1608 256 3216 430 4824 577 6432 707 8040 824 9648 931 11256 1029 12864 1120 14472 1205 16080 1283 PEP-343 Rev. 0 Page 17 of 25

~ ~

APR015 ATTACHHENT 1 (Continued)

CASE 2 --" THYROID DOSE PROJECTION Comoutez Prompt Ex ected In ut

-Do you want to get met data? NO

-Is there a known DCP you wish to use? NO

-Do you know the nuclide mix'? NO

-Whole body (W) or thyroid (T) dose projection?

-Source tean units (0-curies/sec,l-curies)? 1

-Source term (curies)? 750

-Time since reactor shutdown (hours)? 1

-Stability class? B

-Wind velocity (mph)? 20

-Direction wind blowing fzom (degrees)? 180

-Standard distances aze site boundary (2500 ft.),

Exclusion Area Boundary (7500 ft.), 2, 5, 10 miles.

Do you want to use these? YES

-Isopleth value? RETURN KEY The results should resemble those on the following page. lf they do not, carefully check your inputs and try the test again. If the results still are not similar, try a backup copy of the program. If that fails then seek programming help.

PEP-343 Rev. 0 Page 19 of 25

APR015 ATTACHMENT 1 (Continued)

CASE 3 ""- THYROID DOSE PROJECTION--MIXED MODE RELEASE Com uter Prompt E ected lnout

-Do you want to get met data2 NO

-Is there a known DCF you wish to use'? NO

-Do you know the nuclide mix? NO

-Whole body {V) or thyroid (T) dose projection?

>>Source term units {0-curies/sec,l>>

curies)2 1

-Source term {curies)2 1500

-Time since reactor shutdown (hours)2 1

-Stability class'? D

-Mind velocity'? 15

-Direction wind blowing from (degrees)? 180

-Standard distances are site boundary (250 0 ft.),

Exclusion Area Boundary (7500 ft.), 2, 5, 10 miles.

Do you want to use these? YES

-Isopleth value2 RETURN KEY The results should resemble those on the following page. If they do not, carefully check your inputs and try the test again. If the results still are not similar, try a backup copy of the program. If that, fails then seek programming help.

PEP-343 Rev. 0 Page 21 of 25

~ ~ ~

~ ~

~ I~

~ ~

~ ~ ~

0 ~ ~

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II ~

~ I ~

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APRO15 (Continued)

YES NO G. OUTPUT FOR COMPARISON

1. X/Q (Function of Distance/Time)

Dos~etzo A. EXTERNAL DOSE

1. Cloud

a. Finite/Semi-Inf inite

b. Ground Level/Elevated

c. Shielding/Sheltering Factor

d. Dose Conversion Factors

2. Ground Contamination

a. Dose Conversion Factor X

B. INTERNAL (INHALATION) DOSE Thyroid-Iodine X 1.

a. Child/Infant Receptor

b. Breathing Rate

c. Dose Conversion Factor

2. Other Organs - Lungs

a. Critical X

b. Breathing Rate X

c. Nuclide

d. Dose Conversion Factor PEP-343 Rev. 0 Page 25 of 25

APR014 CAROLINA POWER 6 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP"351 TITLE: EMERGENCY PLANT ENVIRONMENTAL MONITORING REVISION 0 APPROVED:

Signature Date TITLE:

PEP-351 Rev. 0 Page 1 of 17

APR014 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4 2.3 Other References 3 ' RESPONSIBILITIES 4

4. 0 DEFINITIONS 5

5. 0 GENERAL 5 6.0 INITIATING CONDITIONS 5 7.0 PRECAUTIONS AND LIMITATIONS 5 8.0 SPECIAL TOOLS AND EQUIPMENT 6 9.0 PROCEDURE STEPS 6 10.0 DIAGRAMS/ATTACHMENTS 7 PEP-351 Rev. 0 Page 2 of 17

APR014 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 through 17 0 PEP-351 Rev. 0 Page 3 of 17

APR014

1. 0 PURPOSE This procedure provides instructions for performing prompt emergency off-site radiological environmental monitoring surveys in the event of a release of radioactive material fzom the plant. This procedure implements Section 4.4.4 of the SHNPP Emergency Plan.

2' REFERENCES 2.1 Emergency Plan References

1. Section 2.4.6.3, "Environmental Monitoring Team Leader"

2. Section 2.4'.6.4, "Environmental Monitoring Teams"

3. Section 4.4.4, "Environmental Monitoring"

4. Table 3.1-1, "Emergency Supplies"

5. Table 2.2-1, "On-Shift Staffing for Emergencies" 2.2 Referenced Plant Emergency Procedures

1. PEP-206, "Environmental Monitoring ~Team Leader"

2. PEP-321, "Notification of Emergency Personnel" 2.3 Other References

1. Shearon Harxis Energy and Environmental Center Instruction RC-EM-19,"Environmental Monitoring Team Field Procedures."

3.0 RESPONSIBILITIES 3.1 Prior to activation of the Technical Support Center, the Site Emergency Coordinator is responsible for implementation of this procedure.

3.2 When the Technical Support Center is activated, the Environ-mental Monitoring Team Leader is responsible for implementation of this procedure.

3.3 When the Emergency Operations Facility is activated, the Environmental Supervisor assumes responsibility for off-site en-vironmental monitoring.

3.4'oth the Plant and Sheazon Harris Energy and Environmental Monitoring teams report to the Technical Environmental'enter

,Support Center Prior to Emergency Operations Facility activation, after which the plant team members return to the plant site to assist the Plant Monitoring Team.

PEP-351 Rev. 0 Page 4 of 17

APR014 4.0 DEFINITIONS

1. Plant Team: An Environmental Monitoring Team composed of personnel from the Harris Plant Op-erations Section, Harris Nuclear Project Department.

2. Shearon Harris Energy and Environmental Center Team:

An Environmental Monitoring Team composed of personnel from the Radiological and Chemical Support Section, Operations Training and Technical Services Department.

5.0 GENERAL Upon the declaration of a Site Emergency or General Emergency, notification of the Environmental Monitoring Team Leader and the Environmental Supervisor is made in accordance with PEP-321, "Noti-fication of Emergency Personnel." Mobilization of Plant and Shearon Harris Energy and Environmental Center Environmental Monitoring Teams follows.

The activities of a Plant team are limited to performing direct radiation surveys and collecting water and air samples (for iodine measurements) in accordance with this procedure.

Shearon Harris Energy and Environmental Center Teams will be respon-sible for soil sampling, milk sampling, vegetation sampling, en-vironmental measurements using thermoluminescent dosimeters, and air sampling (particulate, iodine, noble gas), in addition to the above.

6.0 INITIATING CONDITIONS The Site Emergency Coordinator has declared an Alert, Site Emergen-cy, or General Emergency, and a release off-site of radioactive material is projected to occur, known to have occurred, or suspected to have occurred.

7 ' PRECAUTIONS AND LIMITATIONS I

7. 1 PRECAUTIONS

'I

1. Teams should maintain frequent radio contact with the Environmental Monitoring Team Leader.

2., The Personnel Protection and Decontamination Team Leader should be consulted'r'ior to dispatching teams to ensure appropriate protective clothing, dosimetry, and respirators are used. Changes in radioactive release conditions may cause the radiation protection requirements to be changed.

PEP-351 Rev. 0 Page 5 of 17

APR014 7.0 PRECAUTIONS AND LIMITATIONS

3. Teams should not linger in the plume (of airborne radioac-tivity).

Roads to survey locations in the southern sectors are very narrow, and usually require chains when snowpacked.

Exercise caution when traveling these roads to survey during inclement weather.

7.2 LIMITATIONS The iodine air sampling and analysis methods referenced are of limited accuracy. 1005 collection efficiency and 10K, counting efficiency are assumed.

8.0 SPECIAL TOOLS AND E UIPMENT

1. Hand held radio transceivers operating on the CP&L emer-gency environmental monitoring frequency (Motorola).

2. Environmental Monitoring Kits.

3. Vehicles.

4. Protective clothing, respiratory protection equipment, and dosimetry (as specified by the Personnel Protection and Decontamination Team Leader).

5. Portable electric generator, 9.0 PROCEDURE STEPS 9.1 DISPATCH OF PLANT ENVIRONMENTAL MONITORING TEAMS

1. The Environmental Monitoring Team leader shall brief the team members on plant status and radiological conditions likely to be encountered.

2. Obtain the environmental monitoring kit, portable genera-tor, and radio from the Operations Support Center.

Perform battery check and source check on survey instru-ments, then proceed to the Security Building.

E 3, Obtain vehicle keys from Security, and load equipment 'into the vehicle. .Check fuel level in .vehicle.

4... Make radio contact with the Environmental Monitoring Team Leader and proceed to locations as directed (Attachments 1 and 2). Don protective gear as directed.

PEP-351 Rev. 0 Page 6 of 17

APR014 9.0 PROCEDURE STEPS 9.2 DISPATCH OF SHEARON HARRIS ENERGY AND ENVIRONMENTAI CENTER ENVIRONMENTAL MONITORING TEAMS

1. The Environmental Supervisor (Emergency Operations Facili-ty position title) will be notified whenever an Alert, Site Emergency, or General Emergency is declared in accordance with PEP-321, "Notifications and Communica-tions.

2. The Environmental Supervisor will mobilize Shearon Harris Energy and Environmental Center Environmental Monitoring Teams ~

3. The Shearon Harris Energy and Environmental Center En-vironmental Monitoring Teams will, via radio, report their readiness to the Environmental Monitoring Team Leader in the Technical Support Center or if activated, the Environ-mental Supervisor in the Emergency Operations Facility.

9.3 DIRECT RADIATION MEASUREMENTS Proceed to locations as directed, stop vehicle, and perform direct radiation measurements in accordance with RC-EM-19, "Environmental Monitoring Team Field Procedure.,"

9.4 WATER SAMPLES Collect water at locations specified by the team leader in accor-dance with RC-EM-19, "Environmental Monitoring Team Field Proce-dures."

9..5 RADIOIODINE AIR SAMPLES Collect air samples and perform a field estimate of airborn radioiodine concentration in accordance with RC-EM-19, "Environmental Monitoring Team Field Procedures."

10.0 DIAGRAMS ATTACHMENTS

1. Emergency Environmental Monitoring Location Map (9 pages).

2. Locations for Initial Near-Site Emergency Environmental PEP-351 Rev. 0 Page 7 of 17

ATIACHM1RIT 1 EMERGENCY ENVZK5MENTAI'C5ITORINGIQCATION MAP NEW HILL 1149 BONSAL

> +5+

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i =I 1915 42 PEP-351 Rev. 0 page 8 of 17

ArZACHMENT 1 (Continued) auaO14 LOcAT1D Ns N ', NNE 1011 OLD US 1 NEW HILL ~

SCL RR DIXIE POWER POLE '

PIPELINE AIR SAMPLER 1Q US I MNC lx

/

0~%'+~

~ POWER POLE Q AIR SAMPLER 2 l BARRICADE L

PEP-351 Rev 0 Page 9 of 17

APR014 ATTACHMENT 1 (Continued)

LcIcELvIcIHE NE US 1 RALEIGH J C GARNES 0

REST HoHE ~

GAS STATION b

I NC 1135 SHNPP PEP-351 Rev. 0 Page 10 of 17

APR014 9.0 PROCEDURE STEPS

~ If the activity concentration was determined from a grab sample, convert flowrate in KLBH/HR to milligrams per second (mg/sec) by multiplying by 1.26E+5. Record the result on Attachment 2 as corrected steam flow and circle the units as mg/sec.

~ If the activity concentration was determined from the radiation monitoring system, select the correction factor from the -able below that most. closely corresponds to the indicated steam pressure, multiply the uncorrected steam flowrate in KLBM/HR by the selected factor, and record the result on Attachment 2 as corrected steam flow. Circle the units as cc/sec.

Steam Pressure PSIG Correction Factor 100 34,840 200 17,986 300 12,132 400 9,129 500 7,294 600 6,051 700 5,152 800 4,471 900 3,935 1000 3,503 1OOO 3,145 1200 2,845

i'A 1300 2,589 1400 2,368 t,' ~

3~ If the release pathway is ventillation exhaust:

Obtain the reading if available in cubic feet per minute from the appropriate flowmeter:

FI'-4875SA'or vent stack 1 FT-4420 for vent stack FT-3899A 'or vent stack 3A 5

FT-3899B for vent stack 5A OR Assume the maximum design flowrate:

vent stack 1 390,000 cfm vent stack 3A 22,650 cfm lt I

vent stack 5 207,000 cfm vent

~

stack 5A 103,500 cfm PEP-341 Rev. 0 Page 9 of 20

APRO14 9.0 PROCEDURE STEPS

~ Multiply the flowrate in cubic feet per minute by 472 to convert to cubic centimeters per second, and record both values on Attachment 2.

9.5 Determine the Source Term ~ Dose Conversion Factor Product by one of the following methods:

1. If activity concentration was determined from a grab sample:

Estimate the time in hours after reactor shutdown that the plume will pass the point of interest.

Calculate the decay corrected activity for each isotope and record it in Column 4 of Attachment 7,

-h using the formula A =Ao e t

For each isotope, calculate and zecozd the fractional source term ~ dose conversion factor product, using the formula (Q'DCF) = A 'DCF ~ (Flow Rate). Flow rate t

must be in units of cc/sec or mg/sec.

~ Add the fractional Iodine (Child thyroid) source term

~ dose conversion factor products. Record the total in Column 6 of Attachment 7 and also on Attachment 2.

~ Add the fractional noble gas (whole body) source term

~ dose conversion factor products. Record the total on Column 6 of Attachment 7 and also on Attachment 2, and append Attachment 7 to Attachment 2.

2. If activity concentration was detezmined fzom the radiation monitoring system:

~ Using the best available information on the type of accident, select a Thyroid and a Whole Body dose conversion factor fzom the table in Attachment 4.

Use Attachment 1 as an.aid in determining the type of accident. The accident type is used to aid in determining time after reactor shutdown when the plume is expected to reach the point of interest, which is specific to the source of the release.

(e.g., "Time After Reactor Shutdown" for a gas decay tsnk tha't was last on line with,the reactor at power 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> ago, with a five mile per houz wind and the point of interest is five miles=18 '+(5/5.) = 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />, you would use the closest conservative time in the table, i.e., 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for child thyroid and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for whole body.) If the time after reactor shutdown cannot be determined, use 4.73E+2 for the whole body dose conversion factor and 3.42E+6 for the child thyroid dose conversion factor. Record the selected dose conversion factors on Attachment 2.

PEP-341 Rev. Page 10 of 20

ApRO14 ATZACHMENT 1 (Continued)

EMERGENCY LQQATloH E.M @

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APRO14 ATZKZMZIT 1 (Continued)

EMEEKEKCY MOND)RING ZDCATZON MAP LocATlot4 LU x TH a5 LOcwT l0 eh 1$ Oo4 foe ap pO HILL OvEA L00tc sQC LAK4 ops%

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c+O PEP-351 Rev. 0 Page 12 of 17

APM14 ATI'ACHMENT 1 (Continued)

LocAvio~s E5E, SE SSE1 5

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BOAT RAMP)

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~(~I e~~~> I Cg+Ss+p~g 1127

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HOUSE PEP-351 Bev. 0 - Page 13 of 17

APBD14 LomT i @as S, S SW, SW t

p, 55m Se.c 'Top Sou> ~ Sac.>oq IW Q

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CGA,IQ TH PEP-351 Rev. 0 page 14 of 17

APRO14 lMZGENCY ENVIRCNMEÃlRL K5X'IORING LOCATION m Locp,>ia~s VV5V/, 4/, 4/N~

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ATZKCZBKNT 1 (Continued)

APRO14 Loc<vic+e N4', MM>

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PEP-351 Rev. 0 Page.16 of 17

APR014 ATTACHMENT 2 DESIGNATOR DOWNWIND LOCATION DESCRIPTION DEGREE MILES N Near intersection of S.R. 1134 and SCL 007 /02.6

'.R. at Dixie Pipeline R/W Approximately 0.15 miles S of US1 on 002/01.9 SR 1134 and intersection of unpaved dead end road Turn W at J.C. Garnes Texaco Station on 036/02.3 1135 - proceed to end of road near rest home Parking lot at vehicle maintenance/boat 060/02.0 shed at Harris En'ergy and Env, Center r

Proceed approximately 1 mile South of 081/02 '

HEEC on SR 1127- There is an open knoll on east side of road ESE Holleman's Crossroads 117/02.9 SE Approximately 1.0 mile WS of Holleman's 130/02.4 Crossroads on SR 1130 SSE Boat landing parking lot on SR 1130 155/02.0 Near barricade (Wake Co. line) on SR 1130 173/02.7 .

Near Harris Lake Dam Maintenance lot 190/04.7 SSW Near CP&L boat landing - East of SR 1912 194/04.3 SSW Near Prince Chapel on SR 1912 202/03.7 SW Near Christian Church on SR 1912 220/02.8 WSW Near intersection of SR 1912 and SR 1924 251/02.8 Near gate at end of SR 1911 265/01.4 Proceed approx. 0.8 miles on SR 1911 289/02 '

from SR 1912 at Merry Oaks From Bonsai, proceed SE on SR 1167- 318/02.0 after crossing over SCL RR, turn right into private road leading to the Fish residence - proceed approx. 0.5 miles vest to sharp bend in road Near Bonsai, near intersectioh of SR 1167 332/02.1 and SCL RR PEP-351 Rev. 0 Page 17 of 17

APR014 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR PONER PLANT PLANT OPERATING MANUAL VOLPiE 2 PART 5 PROCEDURE TYPE: PLANT -EMERGENCY PROCEDURE NUMBER: PEP-362 TITLE: INTERPRETATION OF LIQUID AND GAS SAMPLES REVISION 0 APPROVED: DATE: 4 Signature TITLE: ~~P W~p~

PEP-362 Rev. 0 Page 1 of 41

APR014 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

2.1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4 2.3 Other References 4 3.0 RESPONSIBlLITIES 4 4;0 DEFINITIONS/ABBREVIATIONS 4.1 Terminology 4 4.2 Acronyms 5.0 GENERAL 5 6.0 INl'TIATING CONDITIONS 5 7.0 PRECAUTIONS AND LIMITATIONS 5 8.0 SPECIAI TOOTS AND EQUIPNENT 6 9.0 PROCEDURE STEPS 6

10. 0 D IAGRAHS/ATTACRKNTS 13

1. Figure 1 15

2. Figure 2 16

3. Figure 3 17

4. Figure 4 18

5. Figuze 5 19

6. Figure 6 20

7. Figure 7 21

8. Figure 8 22

9. Figure 9 23

10. Figure 10 24

11. Figure 11 25

12. Figure 12 26

13. Figure 13 27

14. Figure 14 28

15. Figure 15 29

16. Figure 16 30

17. Figure 17 31

18. Figure 18 32

19. Figure 19 33

20. Form- 1. 34 21.- Form 2 35

22. Form 3 36

23. Form 4 38 24 . Form 5 40

25. Form 6 41 PEP-362 Rev. 0 Page 2 of 41

APR014 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 through 41 0 PEP-362 Rev. 0 Page 3 of 41

APR014 1.0 PURPOSE The purpose of this procedure is to implement Section 4.4, "Assessment Actions," of the SHNPP Emergency Plan.

This procedure provides the means to relate coze damage with measurements of radionuclide concentrations and with auxiliary indications (reactor vessel level, core exit thermocouples, containment hydrogen and radiation levels) such that it is possible to distinguish the four major fuel conditions: no damage, clad failure, fuel overheat, and core melt.

The approach utilized is the measurement of fission product concentra-tions via the post-accident sampling system and spectroscopic analysis. These results are corrected to account for sample pressures and temperatures, precursor effects, and radioactive decay to obtain the total activity release for the various isotopes. These are compared to the initial activity available for release from the core; the quantity and type of isotopes released are used to estimate the type and extent of coze. damage.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 4.4, "Assessment Actions" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-218, "Accident Assessment Team Leader"

2. 3 OTHER REFERENCES

1. CRC-828, "Isotopic Analysis for Core Damage Evaluation"

2. Westinghouse Owners Group document, "Core. Damage Assessment Methodology," February 1984.

3.0 RESPONSIBILITIES

1. The Accident Assessment Team is responsible for performing this procedure.

4.0 DEFINITIONS ABBREVIATIONS 4.1 Terminology None Applicable 4.2 ACRONYMS

1. BOL - Beginning of Life

2. CCW - Component Cooling Water

3. CF - Correction Factor PEP-362 Rev. 0 Page 4 of 41

APR014 4.0 DEFINITIONS ABBREVIATIONS 4.2 ACRONYMS (Cont'd)

4. EOL End of Life

5. EFPD- Effective Full Power Days

6. MCB Main Control Board

7. MOL Middle of Life

8. PASS- Post Accident Sample Systems

9. PCF Power Correction Factor

10. RCP Reactor Coolant Pump

11. RCS Reactor Coolant System

12. RTP Rated Thermal Power

13. RVLIS- Reactor Vessel Level Indication System

14. SGTR Steam Generator Tube Rupture

15. STP Standard Temperature and Pressure 5.0 GENERAL None Applicable 6.0 INITIATING CONDITIONS

1. An emergency has been declared and the Accident Assessment Team has been activated.

7.0 PRECAUTIONS AND LIMITATIONS

7.1. ACCURACY

The categories of core damage are considered to overlap considerably; this is, however, consistent with the intent of the procedure to provide a generalized estimate of the extent of core damage.

7.2 SPIKING PHENOMENA: If major transients in core power, pressure, or temperature have occurred prior to shutdown, iodine concentrations may indicate a significantly more severe damage state, and should therefore be considered--

Figure 6.

7.3 0 2 CONCENTRATION: If a significant decrease in containment oxygen concentration has occurred since shutdown, this may indicate a hydrogen burn has occurred, and should be considered in evaluating core damage.

7.4 SGTR OR OUTSIDE CONTAINMENT LOCA: If core activity has been released to systems not covered by the PASS, (e-.g., secondary system, CCM), this procedure will give a non-conservative estimate of core damage. This will be noted as auxiliary indicators estimating, more severe damage than the isotopic analysis. If accurate samples of these systems are available as well as reasonable estimates of the space volume or mass, PEP-362 Rev. 0 Page 5 of 41

APRO14 7.0 PRECAUTIONS AND LIMITATIONS the methodology of this procedure may be applied to improve the accuracy of the isotopic release estimate of the core damage.

8.0 SPECIAL TOOLS AND E UIPMENT None Applicable 9.0 PROCEDURE STEPS

/

NOTE: It is not necessary to have a complete isotopic analysis or to perform calculations for all the isotopes listed on Attachment 1, nor is it necessary to use sample analysis from all three locations. For a valid assessment of core damage, only one isotope from each of the three major groups is needed:

1. Clad Damage::Xe, Kr, I

2. Fuel Over-Temperature: Ba, Sr, Xe, Kr, I, Cs

3. Fuel Melt: Ce, Ba, Sr, Xe, I, Cs, Kr, Te, Sb Additionally, samples aze only required from locations consistent with accident conditions. For example, if no coolant has been released to containment, then containment sump and aiz sample analysis is not required.

9.1 As per Procedure CRC-828, "Isotopic Analysis for Core Damage Evaluation," request EMC to sample the Reactor Coolant System, ECCS Recirculation Sumps, and the Containment Atmosphere, and perform spectroscopic analysis. From the data received, complete Form 2, recording time and date of samples, the actual pressures and temperatures of the samples when analyzed, and the containment atmosphere hydrogen and oxygen concentrations.

9.2 On Form 1, Column 11, enter the sample specific activity (yCi/g or yCi/cc) for each isotope, as determined from the analysis of Step 9.1.

9.3 On Form 1, Column 1, enter the time after shutdown (hrs.) from Form 2, Lines 3, 6, and 9, for Reactor Coolant System (R), ECCS Recirculation Sumps (S) and Containment Atmosphere (A) for each analyzed isotope.

9.4 Calculate the sample pressure/temperature correction factors by completing Form 3 (Part A) per the following instructions:

NOTE: If a sample is reported pez unit mass, use a correction

= 1.0 on Form 1, Column 13. Do not complete that factor section of Step 9.4.

PEP-362 Rev. 0 Page 6 of 41

APR014 9.0 PROCEDURE STEPS 9.4.1 A-1"1 and A-1-2: Containment Atmosphere Sample pressure and temperature from MCB instrumentation.

A-1-3 and A-1-4: Sample pressure and temperature from Form 2, Lines 8 and 7.

A-1-5: Containment atmosphere correction factor:

A-1-1 0 A-1-4 (A-1-2) 2 (A-1-3)

Enter calculated value on Form 1, Column 13, for each analyzed isotope's atmospheric sample.

9.4.2 A-2-1

Use RCS Sample temperature from Form 2, i,ine 7, and Figure 1 Tem craters vs Densit Ratio H 0.

A-2-2: Use RCS average temperature from MCB instrumentation and Figure 1 Tem erature vs Densit Ratio HB 0.

A-2-3: CF = (A-2-2)/(A-2-1), Enter this value on Form 1, Column 13, for each analyzed isotope's RCS sample.

9.4.3 A-3-1

Use Containment Recirculation Sump Sample temperature from Form 2, Line 7, and Figure 1 Temperature vs Densit Ratio.

A-3-2: Use sump temperature from MCB instrumentation and Figure 1 Tem erature vs Densit Ratio H20.

$ -3"3: CF = (A-3<<2)/(A-3"1). Enter this value on Form 1, Column 13, for each analyzed isotope's sump sample.

9.5 Calculate the mass'r volume of the three sample spaces by completing Form 3, Parts B, C, and D per the following instructions:

9.5.1 B-1: Pressure/temperature corrected containment free volume:

~A-1-2

• 2.04 x 10 9

cm 3

(A-1-1)

Enter .the calculated value on Form 1, Column 15, for each analyzed isotope's containment atmosphere sample.

9.5.2 C-1: Containment level from MCB instrumentation or local indications.

C-2: Use Figure 2, H20 STP Mass vs. Containment, to find mass of sump liquid at stancard temperature and pressure.

PEP-362 Rev. 0 Page 7 of 41

APR014 9.0 PROCEDURE STEPS C-3: Multiply STP sump mass by sump CF: (C-2) <<(A-3-2).

Enter calculated value on Form 1, column 15, for each isotope's recirculation sump sample.

9.5.3 D-1: Vhen the pressurizer is empty, assume an otherwise filled RCS and multiply the RCS temperature correction factor by STP RCS mass: (A-2-2) << 2. 14 x 10 8 g.

t or D-2: Vhen the pressurizer has a liquid level, multiply the RCS temperature correction factor by STP RCS and Pressurizer mass: (A-2-2) << [2.14 x 10 8 g + (%%d PZR Level)

- 7

(.01) (3.96 x 10 g)].

Enter calculated value on Form 1, Column 15, for each analyzed isotope's RCS sample.

9.6 Calculate the correction factors for thermal power variation by completing Form 4 per the following instructions:

9.6.1 FART A: FCF for Long-Lived Isotopes [Cs-137, Sr 89,-

Sr-90]

A-1: Enter calendar days'rom initial criticality since refueling to time of reactor shutdown, obtained from operating logs.

A-2: Enter number of effective full power days during time period of A-l, obtained from operating logs.

A-3: PCF = ~(A-1 (A-2)

Enter this value on Form 1, Column 18, for these three isotopes.

9.6.2 PART B: PCF for Short-Lived Isotopes [Kr-85m, Kr-87, Kr-88, Xe-135, I-132, I-133, I-135, Rb-88, Te-129, La-142, Pr-144]

B-1: Ef the reactor thermal power has been constant over the four (4) days prior to shutdown ('10'TP variation from 4-day average power level.), then these isotopes have reached equilibrium, and the PCF is that fractional power level. Enter the value on Form 1, Column 18, for these nine isotooes.

Otherwise, Form 5 must be completed to account for power changes over the 4-day period. Using plant operating records, determine the power history for previous 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />. Whenever core power level has changed by more than PEP-362 Rev. 0 page 8 of 41

APR014 9,0 PROCEDURE STEPS 10% of rated thermal power (2775 5%), a separate Form 5 must be completed.

Instructiofis for Form 5:

NOTE: All transient time should be included at the lower pover level for conservatism in the calculations.

Line (1): P - thermal power level for interval (MV )

Line (2): t.j - duration of core operacion at Pj. (hrs)

Line (3): t << - duration from end of interval until shutdown (hrs)

Column (4): X. - decay constant of isotope Column (5): 1 - exp (-(Column 4) <<(Line 2))

Column (6): exp (-(Column 4) <<(Line 3))

Column (7): (Line 1) <<(Column 5) - (Column 6)

After completing the necessary Form Ss to cover the previous 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />, return to Form 4, Part B.

C~olumn 1: For esch isotope on the completed Form 3's, sum up the values recorded in Column (7), and enter that sum in the table.

-k Et.

~Column 2: RTP e (1-e i j)

~Column 3: PCF = ~1 (2)

Encer this value on Form 1, Column 18, for these nine isotopes .

9.6.3 PART C; PCF for Intermediate-Lived Isotopes [Xe-131m, Xe-133, Xe-133m, I-131, Te-132, Ba-140, La-140]

C-1: If the reactor thermal power has been constant over the thirty (30) days prior to shutdown ('0% RTP variation from the 30-day average power level), then these isotopes have reached equilibrium, and the PCF is that fractional power level. Enter the value on Form 1, Column 18, for these s'ix isocooes.

Otherwise, Form 6 must, be completed to account for power changes during the 30-day oeriod. Using plant operating records, determine the power history for che previous 30 days. Vhenever core paver level has changed by more chan 10% of raced thermal power (2775 iS), a seoarace Form 6 must be completed.

PEP-362 Rev. 0 Page 9 of 41

APR014 9.0 PROCEDURE STEPS Instructions for Form 6:

NOTE: All transient time should be included at the lower power level for conservatism in the calculations.

Iine (1): P. - thermal power level for internal t (AN )

3 I inc (2): t. - duration of core operation at P. (days) 3 Line (3): t. - duration from end of- interval until shutdown (days)

Column (4): X - decay constant at isotope Column (S): 1-exp (-(Column 4) + (Line 2))

Column (6): exp (-(Column 4) * (Line 3))

Column (7): (Iine 1) *'(Column S) <<'"(Column 6)

After completing the necessary Form 6's to cover the previous 30 days, return to Form 4, Part C.

~Column 1: For each isotope on che Form 6's completed, sum up the values recorded in Column 7 and enter that sum in the table.

~Colunm 2: RFP * (1-e -) i.Et.jj

~Column 3: PCF = ~1 (2)

Enter this value on Form 1, Column 18, for these six isotopes.

9.6.4 PCF for Cs-134 Using the PCF for long-lived isotopes (A-3) and Figure 3 PCF for Cs-1343 find the Cs-134 PCF. Enter this value on Form 1, Column 18 for Cs-134.

9.7 Complete Form 1 per the following instructions:

9.7.1 ~Column exp (-(2) "-

(1))

9.7.2 C~olumn 3 exp (-(3) * (1)) (if applicable for isotope) 9.7.3 (3) - (2) 1'o) M)l (if applicable for isotope)

(This is the isotope activity at time of sample.)

PEP-362 Rev. 0 Pace 10 of 41

APR014 9.0 PROCEDURE STEPS 9.7.4 (9)

(This is the fraction of the isotope activity due to initial 'inventory at shutdown.)

9.7.5 NOTE: For isotopes with two precursors,(Xe-133, Xe-135 and Te-129) add the two values of column 10 for each sample and subtract 1.0; then apply .formula for Column (12).

(This accounts for the calculated precursor contribution and for radioactive decay since shutdown.)

9.7.6 (This accounts for density variation of sample with the actual medium.)

9.7 '

(This value is the total activity actually released in the RCS, sump, or containment atmosphere.)

9.7.8 (This value is the source term corrected for power history and power level at shutdown.)

9.7.9 (19) as TOTAL.

(This value is the fraction of the total inventory available which was actually released to the RCS, sump, and containment atmosphere.)

Noble Gases - Divide isotope's column (20) Total by the Xe-133 column (20) Total.

Iodines - Divide isotope's column (20) Total by the I-1.31 column (20) Total.

9.8 Obtain the following general information from the data provided from the samples, plant operati.g records, control room personnel, Emergency Response Facility Information System and radiation monitors:

PEP-362 Rev. 0 Page 11 of 41

APR014 9.0 PROCEDURE STEPS 9.8.1 Containment Hydrogen (Form 1, Line 10) 9.8.2 Containment Radiation Monitor R/hr.

9.8.3 Divide (9.8.2) by 2775 0M and multiply by 1.125 = R/hr->Mt (This adjusts the radioactive levels to core power level and containment volume.)

9.8.4 All RCPs Stopped? Y/N 9.8.5 RVLIS - Was Core Uncovered? Y/N Duration and depth of uncovery:

9.8.6 Thermocouples - Superheated Steam? Y/N Highest temperatures and duration:

9.9 Core Damage Assessment From the isotope release fractions and gap activity ratios of Form 1, columns 20 and 21, estimate the state of the core using Figures 4 through 17. Categorize the fuel damage as -- (1) no damage; (2) clad failure (%); (3) fuel overheat (%); or (4) core melt (%) ~ See section 7.0 before making final determination.

Peyote that for each figure, maximum, nominal or minimum refer to core burnup--EOL, MOL or BOL.

As a correlation to these estimates, the data of Steps 9.8.1-9.8.3 is used with Figures 18 and 19. These provide estimates of clad failure based on noble gas activity and containment hydrogen concentration.

The following information applies to the analysis of RVLIS and core exit thermocouples, Steps 9.8.4 - 9.8.6:

• Highest clad temperatures will be greater than thermocouple readings -- thus if thermocouple readings are greater than 1300'F, clad failure may have occurred.

(1300 F is the lower limit for clad failure.)

• If any RCP's are operating, thermocouples will be good indicators of clad temperature -- no core damage should occur due to cooling by steam - water forced flow.

If no RCP's are operating, the following apply:

PEP-362 Rev. 0 Page 12 of 41

APR014 9.0 PROCEDURE STEPS No generalized core damage can occur if the core has not uncovered; so if RVLIS indicates full range and thermocouple indicates no superheated steam, no generalized damage has occurred, If RVLIS indicates a liquid level of less than 3.5 ft. in the core OR thermocouples indicate superheated steam, then the core has uncovered and core damage may have occurred depending upon the time after shutdown, duration and depth of uncovery.

If RVLIS indicates a liquid level between 3.5 ft. and the top of the core, then thexmocouple readings should be monitored for superheated steam temperatures to determine if core uncovery has occurred.

10.0 DIAGRAMS ATTACFMNTS Temperature Vs. Density Ratio, H 0

2. STP H20 Mass Vs. Containment Level Power Conversion Factor For Cs-134

4. Clad Damage Vs. Released Fxaction of Xe-133

5. Clad Damage Vs ~ Released Fraction of I-131

6. Clad Damage Vs. Released Fraction of I-131 With Spiking i

w, ~

7. Clad Damage Vs. Released 'Fraction of Kr-87

~ Y.'l 8. Clad Damage Vs. Released Fraction of Xe-131m

9. Clad Damage Vs. Released Fraction of I-132

10. Clad Damage Vs. Released Fraction of I-133 Clad Damage Vs. Released Fraction of I-135

12. Activity Ratios of Noble Gases and Iodines

13. Fuel Over-Temperatux e Damage Vs . Released Fractions o f Xe, Kr, I and Cs Fuel Over-Temperature Damage Vs. Released Fractions of Ba and Sr

15. Fuel Melt Damage Vs, Released Fractions of Xe, Kr, I, Cs and Te

16. Fuel Melt Damage Vs. Released Fractions of Ba and Sr.

PEP-362 Rev. 0 Page 13 of 41

APR014 10.0 DIAGRAHS AT1'ACHMENTS

17. Fuel Melt Damage Vs. Released Fraction of Pr.

18. Containment Hydrogen Concentration Vs. Zirconium - Water Reaction

19. Gamma Exposure Vs. Released Fraction of Noble Gases

20. Form 1, Isotope Release Worksheet

21. Form 2, PASS Data

22. Form 3, Sample Space Mass Calculations

23. Form 4, Paver Factor Calculations

24. Form 5, Worksheet for Short-Lived Isotype PCF

25. Form 6, Worksheet for Intermediate-Lived Isotype PCF PEP-362 Rev. 0 Page 14 of 41

1

~Fi re 1 Tannerature vs, Densi Ratio, H20 800.

740.

640.

S40.

4 a <40.

C)

%san R5 Cl 304-5 I

200.

'l 00.

CV C) p~362 Bev. 0 page 1S of 41

STP tt20 loess vs Containment Kevel 233 Q

231 230 229 228 227 226 225.'Q 224 8 223 0l11 222 221 0 10 20 30 35

Piqure Poem Conversion Factor for Cs-134 1 .0 90'OWER 0.9 D.n POWER CORRECTtou FACTOR 75$ POWER 0.6

0. 5.

0.$

0.3 0.2 0.1 0.0 . 200 400 600 lOPD.

CYCLE OPERATlON (CALENDAR .DAYS)

Fi~~e 4 Clad Dama vs Be1eased Fraction of Ze-133 0.

4~

r r

4o r

.4l r.

Ol rr' ICS (Q CXl

.4 .'0

~Oj r

.4 5 gO r

c,4 r

N~ h ~ ~ ~ ~

0

~ ~

~ hl P) N N Cl O Cl Pl CI O O O O .O C4 V7 Pea O C1ad Damage (")

PW- 362 Rev. 0 Pace 18 of 41

ATZACK&WT S

~inure S Clad Dame e vs. Released Fraction of I-131 l ~

0 7 0.5 0 3 4 2 Oil 47

.Q5 r

.03

.02 r r ge qO~ r

.Ol

'. COT

.00$

442.

r'~~ g4

~C r

rr

.40l 70+

50+

3.0 4 2+0 +

leO 0

7. 0-5 S. 4-5 3-0-5

2. 0-5 1.4 5

~

l7~ 0 ha

~ ~

~ ~

n

~

e ~ 4

~ ~ ~

0 hs0 Cf a o a o P) lA Q C1ad Damage (")

PW-362 Hev.

Page 19 of 41

AXThCEKNT 6

~Fun~ 6 CLad Dam vs. Released Fraction of I-131 with S ikina C.r 0 S rr r

0 rr

~ 1

.Cr F 05 g/r qr

.OS ggb

.QZ r r

~ 41 r

Ct

-OOT r a

-QOS r

44

'P) .COS r

. OLL Cl S

. OD'l T.d-k

$ +0~4 Z. 4-4

2. 0-+

1.4 t.

a cv')

a

~

a

~

a

~

~" ~ ~

or n~ ~ ~

e w a an a r) ea ~

~

a aa Clead Damage (~)

PW-362 Pav. 0 Pace 20 of 41

ATZPKTBKNT 7 Ficiure 7 Clad Dama vs. Released Fraction of Kr-87 0.

I 0

r

.0 r r

.00 r

~ 00 r

.00 r

.OC

'O gp,i ~<er

~C+r 00 ~ a+ r.

r r b~e r.Q-C5

$ .0- r

'O S

r 4'r r

+/

~

cCl Z. 0" c 2.0- ~O+ r r

rr 4$

5 O toQ 7.0-

$ 1

. 0 2 t.O hl\ N's 04 P7 O O O O 0 O O O CV P) V7 < O.

Clad'amage (~)

C PEP-362 Rev. 0 Pace 21 c>> 41

Fic~. 8 Clad Dama e vs. Released Fraction of Ze-13Im 0.7 0.

0~

0-

.QF r

~qC eOQF

.QO

.QO tV

~

h~

V7

~ ~

~

h ~ ~

le)

~

h, O

~

O O O O O O 04 V7 4 O Clead, Qamage (")

362 Bev 0 Paqa 22 oz 41

AT32C2BKiW 9

'Fi uze 9 Clad Dana vs. Beleased Pxaction of I-132 0.

h4 4

r

.04 rr r

.00 gC 00

+

r

.00

'a CJ

.04

~pe r C2 7.0- r 5' go r r

.t 3.0-r g

2.4-r r

h Le O

lh0 r gh

7. 0-r r 5.0 r 5.0" 2.0 "

r 1.0""

hl.

~

a.

R'7 o 'o

~ ~

ha a

~ hl P)

~

th h

~

o

~

aOl ~

o

.)

~

0o h

~

a aa

~

Clad Oamaqe ("..)

e P~362 Bev. 0 Pave 23 of 41.

BZIRCHKDT 10

~iciure 10 Clad Dama e vs. Released Fraction'f I-133 1

0.

0~

0.

0-

-0

.0

'Cl

.0 OyQ. rr Vl +0 R$

Cl .00 +~~r yS C7 ~

00 CI

.00 r

~qC

~yC} r

.00 Cl

.00 7.0-S 5 2i4>>

) ~ 4>>

p', 4>>

5.0-5 0-2 0->>

hl t1~ lC W ~ ~ ~ ~

~ ~ ~ c4 p7 tll h CI CI CI CI CI e CI CI CI Ol . ) teal N CI CIA Bamaqe (~)

PEP-362 Bev. 0 Page 24 of 41

RKRCERENT 11 C1ad Dama

~Fi tgre ll vs. Released Fraction oZ I-135 I

0~

4>>

0.

0.

0

.0

~ 4 r

.0

.0 r

.04

.00

.'0 r

.00 rr r

.00 r q4 r r g0 r 7'.0-

. 5-0" 5.4>>>> r 2>>0 1.4-7". 4-5>>0 5 '>> 0

2. 0-1.4-"

Al Q h>>

Q7 ~

e < ~

~ ~ ~

0

~

O

~

O

~

4

~ >>>>>> ne n O O O

'lO O

he O

O C1ad Damage {")

P~362 Rev. 0 Pave 25 oz 41

, 5'inure 12 Bctivi Batios of Nable Gases and ZocUnes nuclide Fuel Pellet Act1vk Ratio sa Acth v9 Ratk o Kr&5m 0.11 0.022 Kr-82 0.22 0.022 Kr-88 0.29 '.045 Xe-131m 0.004 0.004 Xe-133 1'.0 1.0 Xe-133m . 0.14 0.096 Xe-135 0.19 0.051 I-1 31 1.0 1.0 X-132 1.5 0.17 E.-133 2.1 0.71 E-135 1.9 0.39 Noble 6as lsoto e Tnvento Noble &s Mt$~ Xe-133 inventory Lod)ne Ratio Iadtne Ysoto e Invento

~ The measured ratios of various nuclides Found 3n reactor coolant during normal operation 3s a functfon of the amount of 'tramp'ranium on Fuel rod cladding, the number an4 size of 'defects'f.e. 'p$ n holes'), and the location of the Fuel rods conta3ntng the defects 1n the- core. The rat'los dertved $ n this report are based on calculated values of relative concentrate'ons in the fuel or $ n the gap. The use of these present ratios for post accident damage assessment 1s restricted to -an attest to 41fferentiate be~n Fuel overtamperature conditions and fuel cladding ssisur canditians. Thus the rstias derived here sre not related ta Fuel detect levels incurred during noreel aaeretian.

P~-362 Bev. 0 Page 26 of 41

ATiRCHME5T 13 Piiure 13 Pue1 Ovex'Matmexature Dama vs, Released Fractions of Xe Ke I, and Cs 100 FO

~ rr r

rr 20 r

t0 r r r

7g' q~ r ~Sr r r 3 r O 2 r r r .r r r 1

r .r O

Cd 0+7 r 0

Oo

.O . O O O O hs O Fuel Over"macr ature (")

~-362 Rev. 0 oage 27 of 41

ATBQKgg 14 1

Fiick~ 14 ture Dama vs. Released Fraction of Ba and Sz 0

0 0.

.4

~ 0

.0

+0 w+r

.0 r qO+

+40 S

~o 0

.40

.00 S

O CJ TeO Q.C 2.0 t.O Cl O hl P7 Fue1 Overtenper atur (~)

P~-362 Bav.-0 ?aae 2S of 41

~KMENT 15

~ . Ficiz.e 15 Fuel Mlt Dama vs. Released Fractions of Xe, Er, I, Cs, and Te i40 70 50 r r

y r

y

10. r g~~r r '0 r r

'r r

r r

0.7 0-0 O O O O W O Fue1 Malt (~)

P~-362 Bev. 0 Paae 29 of 41

ATZPCZRKiV216 Piiu~ 16 Fuel Melt Dama vs. Paleased Fractions of Ba and Sr 100.0

10. 0 0.1 0.01 1.0 10.0 FueI Ne1t (~)

PEP-362 Bev. 0 Page 30 of 41

ATEKHIIEVZ 17 Ficiaw 17 Fuel Melt Dana vs. Rel~ Fraction of Pr 100.0 10.0 1.0

~ JJ

~ al a

s. O.L OP 5

a 0.01 1.0 10;0 FueT Meit (")

~-362 Bev. 0 paae 31 of 43.

ArEcHmT l8 Ficimz 18 Cantainneat en Concentration vs. Zirconium-Water Reaction 26.0 24.

0'2.0 zo.a

'18.0.

HYORQGBl z6.0 CQNCNTRATiaN (v/0) N.a X2.0 ia.a 8.0 6.0 4.0 2.0 LO 20 30 40 60 60 70 80 90 100 ZERCQNEUN MATER REACTION (~)

PW-362 Bev. 0 Pace 32 of 4l

ATIRCHHE5T 19 Pic~. 19 Gama Exposure vs. Beleased Fraction of ~ale Gases 1000.0 =

100.0 100>> Noble Gas Release SV Noble 10.0 Gas Release 1.0 1.0-1 0.3 Noble Gas Rel ease 1.0-3= NS 18.1 Nodal 0perating Noble Gas Release 1.0 .0-1.0 100.0 1000.0 TINE A~Jr. ACCIDENT (HOURS)

~-362 Rev. 0 ~aae 33 of 41

APR014 ATTACHMENT 21 Form 2 PASS Data Reactor Coolant Sample Date:. / / (1) Temp:

Time: (2) Press.

psig (3) Time After Shutdown: hr.

Containment S Sample Date: / / (4) Temp:

Time: ~ (5) Press.

psig (6) Time After Shutdown: hr.

Containment Atmosphere Sam le Date: / / (7) Temp:

Time: (8) Press.

psig (9) Time After Shutdown: hr.

(10) Containment H2 Concentration: v/o (ll) Containment 02 Concentration: v/o PEP-362 Rev. 0 Page 35 of 41

APR014 ATTACHMENT 22 Form 3 Sample Space Mass Calculations A. Pressure Temperature Correction Factors A-1 Containment Atmosphere A-1-1 Containment Atmosphere Pressure psig + 14.7 =

psia A-1-2 Containment Atmosphere Temperature F + 460 = R A-1-3 Sample Pressure psig + 14e7 =

psi&

A-1-4 Sample Temperature F + 460 = R (A-1-2) * (A-1-3) =

A-2 RCS (Note:

= 1.0.)

If sample activity is reported per unit mass, use CF A-2-1 CF for Sample (Figure 1)

A-2-2 CF for RCS (Figure 1) 2-2-3 RCS Sanple CS = ~4-2-2 (A-2-1)

A-3 Sump (Note: If sample activity is reported per unit mass, use CF = 1.0) on Form 1).

A-3-1 CF for Sample (Figure 1)

A-3-2 CF for Sump (Figure 1)

A"3-3 RCS Sanple CP = ~A-3-2 (A-3-1)

B. Containment Free Volume e 2.04 x lO 9 3 3-\ ~i-1-2 cm (A-1-1)

C. Recirculation Sumo Mass C-1 Containment Level ft. MSL PEP-362 Rev. 0 Page 36 or 41

APR014 ATTACHMENT 22 (Cont'd)

Fora 3 (Cont'd)

Sam le S ace Mass Calculations C-2 Sump Mass g (Figure 2)

C-3 (C-2) * (A-3-2)

D. RCS (D-1) No Level Indicated on Pressurizer:

RCS Mass = 2.14 x 10 8 * (A"2-2) =

OR (D-'2) Level Indicated On Pressurizer:

8 7 RCS Mass = [2.14 x. 10 + (PZR Level)(0.01)(3.96 x 10 ) J

• .(A-2-2)

PEP-362 Rev. 0 Page 37 of 41

APR014 ATTACHMENT 23 Form 4 Power Factor Calculations PCF for Lon -Lived Isotopes A-1: Calendar Days in Core Cycle days A-2: EFPDs in Core Cycle EFPDs A-3: PCF = ~(A-1 (A-2)

B. PCF for Short-Lived Isotopes B-1: PCF = Thermal Power 277S MW OR If power not constant four days prior to shutdown:

(2) (3)

-k Zt.

Isotope Z(Form S, Column 7) RTP ~ (1-e i j) PCF = ~1

- ">> (2)

Kr-85m 2775 Kr"87 2775 Xe-135 2773 I-132 2775 I-133 2670 I-135 2775 RB-88 2775 Te-129 2775 I,a-142 2775 Pr-144 2775 PEP-362 Rev. 0 Page 38 of <1

APR014 ATTACHMENT 23.(Cont'd)

Farm 0 (Cont'd)

Power Factor Calculations C. PCF for Intermediate-Lived Isotopes C-1: PCF = Thermal Power 2775 MV OR If thermal power level not constant over 30 days prior to shutdown:

(2) (3)

Isotope E(Form 6, Column 7) RTP * (1-e i j) PCF ~ ~1 (2)

Xe-131m 2299 Xe-133 2722 Xe-133m 2775 I-131 2566 Te-132 2770 Ba-140 2229 La-140 2775 D. PCF for Cs-134 from Fi re 3 PEP-362 Rev. 0 Page 39 of 41

APR014 ATTACEIENT 24 Fora 5 Vorksheet for Short-Lived Isotope PCF (2) tj = hrs.

(3) t *= hrs.

(4) (5) (6)

Isotope i 1 h 1-e ij e k.tj Kr-'85m 0. 158 Kr-87 0.547 Kr-88 0.248 Xe" 135 7.58K "2 I-132 0.307 I"133 3.41K-2 I-135 0. 104 Rb-88 2. 34 Te-129 0.605 La-1'42 0.450 Pr-144 2.41 PW-362 Rev. 0 Page 40 of 41

APR014 ATTACHMENT 25 Foehn 6 Vorksheet for Intermediate-Lived Isotope PCF

() P)= NV (2) t~ = days (3) t - = days (5) (6) (7)

Isotope i (day i). 1-e ij -1 t) P "'(5)"(6)

Xe-131m 5. 88E-2 Xe-133 0.132 Xe-133m 0.307 I 131 8.62x10 Te-132 0.214 Ba-140 5.42E-2 La-140 0.413 PEP>>362 Bav. 0 Page 41 of 41

1982 SHNPP PERMANENT RESIDENT E'tis s ~

/ 't g.I," I sot C +o POPULATION ESTIMATES: SUBZONES R

> e ~+Soviet I

~ Soaeo

~E) a t I

~ a lEs e~ PS, tet )al EUBZONE PEOPLE I g 3 sell e to ~ e'5 I'.. t I A 0 t ~ e~ 1 Iis 4t I~ Ill t

!t.g )~

~ e I6S 930 B

~a~

a~ac IJ U a/. ~ ~

I

.os '

C 119 I r 5 ~

~

/ "-: "

sets 'r D 138 oEet a f ~ I'vN to at ao E 6,012 I tel Jtoooo~n tol Oa V.l a ~s ~

Q F 2,185 s ~ ei

"",y a

G 5,219 ~t c> SS i

1,424 (t~3tseie /

H \ rr ad o r~ /'~ Ii I 375 tla ars to ~

~

. ~

is I t.

J 725 1 litt ~ ool

%s I ~ eall t -i+

K 640 0 stol I sst

/ 1~ICE I

L 472 Q iatl M 943 l, O sen N 650 i t II TOTAL: 19,832

+t Ortega.

IO 3

V CXg: N, ieu 0 DI avoN

( st~as Inca IIÃ Ilo ~ QJI ~ I sl I boss t Il

'a eels Sseocv

~ I'e f II I I le te lol~ ~

RI ~ t'R '

Isl ~ e, ~

, ~ Iertyi

~

~N I seo toiled a list Isle t' nl Ut I tet ere EXCLUSION l~ I ~

'XM (.I'I' (t

~

~

Slit AREA I' Io Islt i~ ~ BOUNDARYI I

~ ~

Saetsooo PSS e

Isl tlat 0 iui sen s NO St

<>203 for establishing protective clothing requirements; and the normal criteria in PLP-510 for establishing respiratory protection re-quirements .

9. 1.5 CAUTION Planned exposure to fertile women shall not exceed regulatory limits.

The Personnel Protection and Decontamination Team Leader will determine the exposure history for each individual, then determine and enter on the Emergency Radiation Work Permit the allowable dose for each individual based on the criteria in Attachment 1.

9.1.6 The Personnel Protection and Decontamination Team Leader, will authorize all Emergency Radiation Work Permits. He PEP-371 Rev. 0 Page 10 of 15

APR010 9.0 PROCEDURE STEPS 9.1 RADIOLOGICAL CONTROLS FOR EMERGENCY WORKERS (Cont'd) shall obtain the Plant General Manager's authorization signature on the Emergency Radiation Work Permit if the proposed activity requires entry into radiation fields greater than 100 R/hr or may result in radiation exposure in excess of regulatory limits. In the absence of the Plant General Manager, the Environmental E Radiation Control Manager or Site Emergency Coordinator, in that order, may authorize invoking the emergency exposure limits.

9. 1.7 The Personnel Protection and Decontamination Team Leader will verbally transmit the Emergency Radiation Work Permit requirements to the Personnel Protection and Decontamina-tion Team and the appropriate Team Leader(s). Personnel Protection and Decontamination Team members will transcribe this information onto a facsimile copy Emergency Radiation Work Permit form, and have each individual listed on the form initial it to acknowledge the requirements.

9. 1.8 The Personnel Protection and Decontamination Team will issue equipment, as specified on the Emergency Radiation Work Permit:

1. Normal pre-issue documentation for dosimetry and respirators shall be filled out, but may be deferred until after the task is complete.

2. Assist individuals in donning protective clothing and respirators as required.

9. 1.9 The Personnel Protection and Decontamination Team will accompany other teams to provide continuous coverage, and/or neutron dosimetry in accordance with DP-005, as specified on the Emergency Radiation Work Permit.

9. 1. 10 When the task is complete, Personnel Protection and Decontamination Team personnel will:

Assist emergency workers in removing protective equipment and monitoring for contamination, if required.

2. Record exposures from Self Reading Pocket Dosimeters on the facsimile Emergency Radiation Work Permit and transmit the same verbally to the Personnel Pro-tection and Decontamination Team Leader, who will transcribe the information onto the original.

PEP-371 Rev. 0 'Page ll of 15

APR010 9.0 PROCEDURE STEPS 9.1 RADIOLOGICAL CONTROLS FOR EMERGENCY MORKER (Cont'd)

3. Ensure that any deferred issue documentation is completed.

9.1.11 The Personnel Protection and Decontamination Team Leader will enter exposure data into the Radiation Information Management, System as time permits, and direct Personnel Protection and Decontamination Team personnel to read Thermolumines'cent Dosimeters if any personnel are ap-proaching their exposure limit.

9.2 DOSIMETRY FOR IMMEDIATE RESPONSE PERSONNEL.

9.2.1 Emergency Security Team personnel will issue a packet containing a Thermoluminescent Dosimeter and a Self Reading .Pocket Dosimeter to each individual when they arrive on-site. No documentation will be completed at the time of issue.

9.2.2 Immediate response personnel exposures will be controlled in accordance with Section 9.1 of this procedure.

9.2.3 When immediate response personnel are ready to leave the site, Personnel Protection and Decontamination Team Personnel will collect their dosimetry, and record the name; social security number; Thermoluminescent Dosimeter, and Self Reading Dosimeter serial numbers; and the reading on the Self Reading Pocket Dosimeter for each individual.

9.2.4 Personnel Protection and Decontamination Team personnel will read the Thermoluminescent Dosimeters of immediate response personnel as soon as possible in accordance with DP-105.

9.2.5 The Personnel Protection and Decontamination Team will verbally transmit exposure information for immediate response personnel to the Personnel Protection and Decon-tamination Team Leader as soon as it is available.

9.3 DOSIMETRY FOR SHELTERED PERSONNEL 9.3.1 The Personnel Protection and Decontamination Team will issue one Thermoluminescent Dosimeter and one, self reading pocket dosimeter to each Assembly Area Leader in the on-site shelters. This dosimetry will be used to deter-mine the exposure to all personnel in the shelter who do not have permanently assigned dosimetry.

9.3.2 When the emergency is terminated or an evacuation is ordered, the Personnel Protection and Decontamination Team PEP-371 Rev. 0 Page 12 of 15

APR010 9.0 PROCEDURE STEPS 9.3 DOSIMETRY FOR SHELTERED PERSONNEL (Cont'd),

will collect assembly area dosimetry and read it as soon as possible in accordance with DP-105. The Personnel Protection and Decontamination Team will verbally transmit assembly area exposure information to the Personnel Protection and Decontamination Team Leader as soon as it is available.

9.3.3 After the emergency is terminated, Radiation Control personnel will determine the names of personnel who were present in the assembly area by contacting a manager, supervisor, or foreman for each organizational group as-signed to the assembly area and having them provide a list of who was present. The dose recorded for each assembly area will be assigned to all personnel who were not wearing, individual. dosimetry and who were present in that assembly area.

10.0 DIAGRAMS ATTACHMENTS

1. Emergency Worker Exposure Criteria.

2. Special Radiation Work Permit.

PEP-371 Rev. 0 Page 13 of 15

APR010 ATl'ACHMENT 1 EMERGENCY WORKER EXPOSURE CRITERIA TASK EXPOSURE LIMITS Whole

~Bod ~Th roid Removal of injured personnel from an area 75 Rem No Limit immediately hazardous to life; providing first aid, personnel decontamination, am-bulance service, or medical services when failure to do so would be life-threatening to the individual.

2. Undertaking corrective actions that are 75 Rem No Limit necessary to prevent or correct a condition that would probably result in death or in-jury to large numbers of persons, either on or off site.

3. Undertaking corrective actions that are 25 Rem 125 Rem necessary to prevent the release of radio-active material, and the projected dose from such a release would probably exceed EPA r Protective Action Guides (e.g., emergency

~ ~ operation of or repairs to equipment that is necessary to establish or maintain safe shutdown of the plant).

4. All other actions, including assessment Use regulatory actions. limits NOTES:

1. Exposure limits are based on EPA Protective Action Guides.

PEP-371 Rev. 0 Page 14 of 15

m RO10 ATTACRiENT 2 EMERGENCY RADIATION WORK PERMIT Date Time Requested by Task to be performed Location of personnel who will perform task:

Personnel who will perform task:

Projected Current Ex osure Allowable Dose Lifetiss Quarter ~Ex ssure IN OUT Estimated Area Dose Rate: Projected Stay Time:

Estimated Airborne Activity:

Access Point:

Access Route:

Dosimetry Required:

Protective Clothing Required:

Respiratory Protection Required:

Approval:

Personnel Protection and Decontamination Team Leader Plant General Manager/Environmental and Radiation Control Manager/Site Emergency Coordinator PEP-371 Rev. 0 ~

Page 15 of 15

APR005 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-381 TITLE: EVACUATION REVISION 0 APPROVED:

Signature Date TITLE:

PEP-381 Rev. 0 Page 1 of 11

APR005 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE

2.0 REFERENCES

4.

2.1 Emergency, Plan References 4 2.2 Referenced Plant Emergency Procedures 4 2.3 Other Referenced Plant Procedures 4 3.0 RESPONSIBILITIES 4 3,1 Site Emergency Coordinator 4 3.2 Vork Group Supervisors 4 3.3 Personnel Protection and Decontamination Team 5 3.4 Individuals on CP&L Property 5 4.0 DEFINITIONS/ABBREVIATIONS 5 5.0 GENERAL 5 6.0 INITIATING CONDITIONS 6 6.1 Protected Area and/or Site Evacuation 6 6.2 Exclusion Area Evacuation 6 7.0 PRECAUTIONS AND LIMITATIONS 6 8.0 SPECIAL TOOLS AND EQUIPMENT 6 9.0 PROCEDURE STEPS 6 9.1 Protected Area Evacuation 6 9' Plant Site Evacuation 8 9.3 Exclusion Area Evacuation 9 10.0 DIAGRAMS/ATTACHMENTS 9

1. Protected Area Evacuation Assembly Area 10

2. Site Evacuation Assembly Area 11 PEP-381 Rev. 0 Page 2 of 11

APR005 LIST OF EFFECTIVE PAGES LEP

~Pa e Revision 1 through ll ,0 PEP-381 Rev. 0 Page 3 of 11

APR005 1.0 PURPOSE The purpose of this procedure is to implement Section 4.6.2 of the SHNPP Emergency Plan, "Evacuation and Personnel Accountability."

r The procedure provides instructions for implementing an evacuation of the Protected Area, the Plant Site, and/or the Exclusion Area. It does not apply to evacuation of members of the general public from affected areas outside of the Exclusion Area.

This procedure is primarily directed at evacuations initiated by actual or imminent radiological conditions. The basic actions contained in this PEP also apply, where appropriate, to evacuations related to other habitability hazards, such as toxic gases, fire, or natural phenomena.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 4.6.2, "Evacuation and Personnel Accountability."

2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-101, "Initial Emergency Action"

2. PEP-102, "Site Emergency Coordinator - Control Room"

3. PEP-103, "Site Emergency Coordinator - Technical Support Center"

4. PEP-210, "Emergency Security Team Leader"

5. PEP-217, "Emergency Communicator"

6. PEP;371, "Radiation Vork Permits and Exposure Control"

7. PEP-382, "Personnel Accountability."

8. PEP-384, "Access Control" 2.3 OTHER REFERENCED PLANT PROCEDURES

1. SP-015, "Emergency Plan Support" 3.0 RESPONSIBILITIES 3.1 SITE EMERGENCY COORDINATOR The Site Emergency Coordinator is responsible for the safety and well-being of all personnel on site. It is his responsibility to determine the need for, and to direct an evacuation of hazardous areas, and for directing personnel to a safe assembly area.

PEP-381 Rev. 0 Page 4 of 11

APR005 3.0 RESPONSIBILITIES 3.2 YORK GROUP SUPERVISORS Vork group supervisors and assembly area leaders are responsible for the safety. of their assigned personnel.

3.3 PERSONNEL PROTECTION AND DECONTAMINATION TEAMS The Personnel Protection and Decontamination Teams are responsible for monitoring and decontamination, if necessary, of evacuating personnel and equipment, and for verifying the radiological safety of the assembly areas.

3.4 INDIVIDUALS ON CP&L PROPERTY All CP&L employees and contractors on CP&L property are responsible for responding to evacuation notifications and escorting ass'igned visitors to evacuation assembly areas as described in this procedure.

4.0 DEFINITIONS ABBREVIATIONS

1. Protected Area Evacuation - This is the evacuation of all personnel, except for emergency response personnel, from within the Protected Area boundary.

2. Plant Site Evacuation - This is the evacuation of all personnel, except for emergency response personnel, from the SHNPP site, including the Protected Area, outside construction areas, the parking lots, the cooling tower area, intake strbctures, cement plant, and construc-.

tion lay down areas.

3. Evacuation Assembl Area - This is the area where evacuating personnel assemble so that radiological monitoring of personnel that were in the affected area can be pezformed.

personnel assemble when an emergency is first declared for accountability purposes. These areas are designated in PEP-382, "Personnel Accountability."

5.0 GENERAL Evacuation is one of several available protective actions for on-site personnel. It is not applicable for personnel with emergency assignments, whose exposure will be contzolled in accor-dance with PEP-371. The general decision levels for taking protec-tive action are projected doses of 500 mrem whole body and 1500 mrem thyroid. Based on recommendations from the Radiological Control Director, the Site Emergency Coordinator will implement the protec-tive action that will result in the greatest dose reduction.

PEP-381 Rev. 0 Page 5 of 11

APR005 6.0 INITIATING CONDITIONS 6.1 PROTECTED AREA AND/OR SITE EVACUATIONS

1. An emergency has been declared, and all on-site personnel have been accounted for in accordance with PEP-382, and

2. Radiation doses in excess of 500 mrem whole body and/or 1500 mrem Thyroid are projected for personnel 'in one or more of the Assembly Areas, and

3. The Radiological Control Director has determined that evacuation will provide the greatest degree of protection for on-site personnel.

6.2 EXCLUSION AREA EVACUATIONS The Site Emergency Coordinator has recommended evacuation of Emergency Planning Subzone A to off-site authorities.

7.0 PRECAUTIONS AND LIMITATIONS

1. The implementation of evacuation must be based on the protective action which will result in the lowest person-nel exposure (or injury).

2. Ensure that proper health physics practices are followed to the extent possible during the evacuation.

3. Evacuations should be accomplished either before or after the passage of a release (typically a gaseous release),

and the evacuation route should be chosen that leads personnel away from the path of the plume. Direction from the Dose Projection Team Leader (or Radiological Control Director, if available) is needed to obtain this

. information.

8.0 SPECIAL TOOLS AND E UIFMENT

1. Public Address system, evacuation alarm, megaphones, and patrol boat.

9.0 PROCEDURE STEPS Proceed to the section that applies; i.e., Protected Area Evacuation (Section 9.1), Plant Site Evacuation (Section 9.2), or Exclusion Area Evacuation (Section 9.3).

9.1 PROTECTED AREA EVACUATION

1. Upon direction from the Site Emergency Coordinator, the Emergency Communicator - Control Room sounds the'ite Evacuation Alarm.

PEP-381 Rev. 0 .Page 6 of 11

APR005 9.0 PROCEDURE STEPS 9.1 PROTECTED AREA EVACUATION (Cont'd)

2. The Emergency Communicator instructs personnel over the Public Address system to evacuate:

+'~"- EXAMPLE MESSAGE <'s<r "ATTENTION, ALL PERSONNEL. UNSAFE CONDITIONS EXIST IN THE PROTECTED AREA. ALL PERSONNEL IN THE PROTECTED AREA WITHOUT EMERGENCY ASSIGNMENTS EVACUATE THE PROTECTED AREA AND ASSEMBLE IN THE PARKING LOT. WAIT THERE FOR FURTHER INSTRUCTIONS.

Continue with additional instructions as necessary.

3. The Emergency Communicator(s) repeat the alarm and announcement after. approximately one minute.

All personnel in the Protected Area who do not have emergency assignments exit thru the Security Building in accordance with normal Security proceduzes. If portal radiation monitors detect contamination on personnel, those individuals will be directed by a Personnel Protection and Decontamination Team member to return to the Waste Processing Building decontamination area for monitoring and decontamination by the Personnel Protection and Decontamination Team. If contamination is detected on large numbers of individuals, a Personnel Protection and Decontamination Team member will instruct an evacuating individual to direct the contaminated individuals assembled at the Waste Processing Building decontamination area to proceed through the security building to a segregated azea of the parking lot, and any additional contaminated personnel will be directed to assemble in the same area. If the portal radiation monitors are alarming continuously or inoperable they will be disregarded and all evacuating personnel will be assumed to be contaminated.

5. The Radiological. Control Director directs Personnel Prote'ction &, Decontamination Team personnel 'to perform radiological surveys in the assembly area.

6. If the radiation surveys at the Protected Area Evacuation Assembly Area (parking lot) indicate a projected dose in excess of 500 mrem whole body or 1500 mrem Thyroid, the Site Emergency Coordinator directs the relocation of evacuated personnel to the Construction Warehouse, oz if necessary initiates a Plant Site Evacuation (Section 9.2).

PEP-381 Rev. 0 Page 7 of 11

APR005 9.0 PROCEDURE STEPS 9.1 PROTECTED AREA EVACUATION (Cont'd)

7. Evacuated personnel will remain in the Assembly area until it is determined by the Site Emergency Coordinator that it is safe for them to return to the Protected Area, or until a Site or Exclusion Area evacuation is ordered.

Contaminated p'ersonnel will be decontaminated at the remote assembly area if a Site or Exclusion Area evac-uation is ordered, or at the Waste Processing Building decontamination area if conditions permit returning to the Protected Area.

9.2 PLANT SITE EVACUATION

1. The Site Emergency Coordinator ensures that the Radiological Control Director has directed the Personnel Protection and Decontamination Team to establish radiological monitoring stations at the Site Evacuation Assembly Area near the meteorological tower.

2. The Site Emergency Coordinator ensures that the Emergency Security Team Leader has implemented PEP-384, "Access Control."

3. When the access control points and radiological monitoring stations are ready, the Site Emergency Coordi-nator directs the Emergency Communicator - Control Room to sound the Site Evacuation Alarm and announce over the PA system to evacuate.

~~ EXAMPLE MESSAGE '~~

"ATZENTION, ALL PERSONNEL ON" SITE AN UNSAFE CONDITION AFFECTING THE SITE EXISTS. ALL PERSONNEL EXCEPT THOSE WITH EMERGENCY ASSIGNMENTS EVACUATE THE SITE AND ASSEMBLE AT THE METEOROLOGICAL TOWER. REPORT TO YOUR FOREMAN OR SUPERVISOR AND AWAIT FURTHER INSTRUCTIONS."

Continue with additional instructions as necessary.

4. The Emergency Communicator repeats the alarm and announce-ment after approximately one minute.

5. All personnel on site without emergency assignments exit the site in accordance with normal security procedures, proceed in their personal vehicles to the Site Evacuation Assembly Area near the meteorological tower, and report to their supervisor or foreman.

PEP-381 Rev. 0 Page 8 of 11

APR005 9.0 PROCEDURE STEPS 9.2 PLANT SITE EVACUATION (Cont'd)

.6. The Site Emergency Coordinator ensures that the Radiological Control Director has directed Personnel Protection & Decontamination Team personnel to perform contamination monitoring at the remote assembly area. If contamination is detected on personnel or vehicles, they will be directed by Personnel Protection & Decontamination Team personnel to report to- the Fire Training Area for decontamination.

9.3 EXCLUSION AREA EVACUATION NOTE: Exclusion Area evacuation will be implemented only when the Site Emergency Coordinator has recommended the evac-uation of Emergency Planning Subzone A to local authorities.

Conduct a plant site evacuation in accordance with section 9.2 of this proceduze, except that personnel will be directed to assemble at the CP&L Cape Fear plant (which is in Emergency Planning Subzone K) and/or at the CP&L District Office in Cary (which is outside of the Plume Exposure Pathway Emergency Planning Zone).

EXAMPLE MESSAGE ~~

"ATTENTION, ALL PERSONNEL'N THE EXCLUSION AREA. AN UNSAFE CONDITION AFFECTING THE EXCLUSION AREA EXISTS. ALL PERSONNEL EXCEPT THOSE WITH EMERGENCY ASSIGRKNTS ASSEMBLE AT: CP&L CAPE FEAR PLANT or CP&L DISTRICT OFFICE IN CARY (Specify one which is not in the downwind direction).

REPORT TO YOUR FOREMAN OR SUPERVISOR AND AWAIT FURTHER INSTRUCTIONS.

2. The Emergency Security Team Leader will assist in warning members of the general public that may be within the Exclusion Area in accordance with Security procedure SP-015, "Emergency Plan Support,"

3. The Emergency Security Team Leader will notify Emergency .

Operations Facility Security that evacuation of Emergency Planning Subzone A, which includes the Harris Energy and Environmental Center, has been recommended by the Site Emergency Coordinator. All Harris Energy and Environmental Center Personnel who do not have emergency assignments will evacuate with the local population as directed by local authorities.

10. 0 DIAGRAMS ATTACHMENTS Protected Area Evacuation Assembly Areas

2. Site Evacuation Assembly Area PEP-381 Rev. 0 Page 9 of 11

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>being of all personnel on-site. It is his responsibility to account for all personnel on-site, to direct search and rescue operations as required, to locate missing personnel, and to direct protective actions as appropriate.

3.2 EMERGENCY SECURITY TEAM LEADER The Emergency Security Team Leader is responsible for reporting personnel accountability to the Logistics Support Director within 30 minutes of (and continuously thereafter) an Alert, Site Emergency, General Emergency, or upon activation of this procedure by the Site Emergency Coordinator. The support given by security during an emergency is discussed in SP-016.

3.3 WORK GROUP SUPERVISORS Work group supervisors, assembly area leaders, emergency team leaders, and/or directors are responsible to account for all indi-viduals assigned to them on-site .and to ascertain and report the names of missing persons to the Emergency Security Team Leader.

3.4 INDIVIDUALS Individuals are responsible for expeditiously going to their .appro-priate emergency facility or assembly area, reporting to their PEP-382 Rev. 0 Page 4 of 10

APR005 3;"0 RESPONSIBILITIES

'.4 INDIVIDUALS (Cont'd) respective foreman or supervisor, and keeping their foreman or supervisor informed of their whereabouts after the initial assembly.

r 3.5 ESCORTS FOR VISITORS An individual who- is escorting visitors must escort them to the assembly area.

4.0 DEFINITIONS 4.1 TERMINOLOGY

1. Radiolo icall Controlled Area - an area that is controlled foz zadiological purposes.

2. Protected Area - the ares within the security fence azound Unit 1 buildings and other equipment necessary for the operation of Unit 1.

3. Shift eratin Crew - those plant staff personnel reporting operationally to the Shift Foreman, including the shift technical advisor, operators, radwaste operators, mechanics, electricians, radiation control technicians, instrumentation and control technicians, etc.

4. Qualified - a qualified individual ia one who haa, been trained to carry out emergency responsibilities in accordance with PEP-403.

5.0 ,GENERAL When an emergency of alert classification or greater is first declared on-sita, an assembly of all site personnel is conducted to account for all site personnel and determine missing persons. Once the initial accountability is 'determined, supervisors and emergency team leaders maintain accountability of their personnel until they are relieved oz the emergency is ended. The assembly areas can provide limited sheltering for nonessential personnel if immediate evacuation is not advisable.

The assembly azea for all personnel inside the Protected Area who are not primary designees for an emergency position is the Fuel Handling Building lunch room and auditorium during normal working hours.

assembly azea for all site personnel outside the Protected Area

'he who are not primary designees for an emergency position is the Construction Warehouse during normal working hours.

PEP-382 Rev. 0 Page 5 of 10

APR005

5. 0 GENERAL During off hours (2nd & 3rd shifts), the assembly area is the Security Building or other single location designated by the Site Emergency Coordinator.

At the assembly areas, nonessential personnel remain until the Site Emergency Coordinator has determined that they may return to their work place, evacuate, or remain sheltered in the assembly area.

Personnel at the assembly areas who are needed to fill the emergency organization proceed to their assigned emergency vacancies in facility ox work stations once the initial accountability has taken pl'ace.

6.0 INITIATING CONDITIONS

1. An Alert, Site Emergency, or General Emergency at SHNPP has been declared ..

2. Other conditions not specifically listed, as determined by the Site Emergency Coordinator (Shift Foreman).

7.0 PRECAUTIONS LIMITATIONS

1. Initial accountability must be performed,and the Logistics Support Director or Site Emergency Coordinator notified within 30 minutes after an-"Alert, Site Emergency, or General Emergency is declared.

2. Once the initial accountability has been completed, an evacuation can be performed at any time, without another assembly even if nonessential personnel have been permitted to return to their work place.

3. Once the emergency has been downgraded below the Alert level, the accountability requirement is removed and a new assembly will be required if the emergency cia'ssification is subsequently raised to Alert, or higher.

8.0 SPECIAL TOOLS AND E UIPMENT

1. Emergency organization personnel rosters

2. Public, address system, telephone system, and security/-

operations portable radios.

9.0 PROCEDURE STEPS 9.1 INITIAL ACCOUNTABILITY

1. Immediately upon declaration of an Alert, Site Emergency, or General Emergency, the Shift Operating Crew shall place their work area in a safe condition and proceed to their PEP-382 Rev. 0 Page 6 of 10

APR005 9=;0" PROCEDURE STEPS" 9.1 INITIAL ACCOUNTABILITY (Cont'd) assigned emergency locations unless specifically directed otherwise by the Site Emergency Coord'inator:

The Shift Technical Advisor, Control Operators, and Auxiliary Operators report to the Control Room.

All other personnel on shift report to the Operational Support Center.

2... The senior on-site member of the security organization vill request that all other security organization personnel report in by radio, and designate an individual to report to the Technical Support Center as Emergency Security Team Leader.

3. All personnel on-site who are not on the Shift Operating Crev or membezs of the security organization place their work area in a safe condition and report to their designated assembly area or emergency facility:

The primary designees for Technical Support, Center emergency positions will report to the Technical, Support Center.

E The primary designees for Operational Support Center positions will report to the Operational Support Center.

All personnel who normally work inside the Protected Area who are not primary designees for an emergency position, vill assemble in the Fuel Handling Building lunch room and auditozium.

All personnel vho normally vork outside of the Protected Area who aze not, primary designees for an vill

'n emergency position assemble in the construction varehouse.

NOTE back shifts,'hen few non-shift personnel are likely to be on-site, the Site Emergency Coordinator may designate a single assembly area (usually the security building so that only one Assembly Area Leader is needed for personnel inside and outside the Protected Area) for all on-site non-shift personnel who are not primary designees for an emergency position.

Any personnel who must exit Radiologically Controlled Areas, or enter or exit security areas to get to their designated assembly area or emergency facility, will do so in accordance with normal security and/oz radiation control procedures, PEP-382 Rev. 0 Page 7 of 10

APR005 9.0 PROCEDURE STEPS 9.1 INITIAL ACCOUNTABILITY (Cont'd)

.5. Upon arrival at the assembly areas, all personnel will report to theiz supervisor or foreman. Vithin twenty minutes after the emergency is declared, supervisors and foremen will report the names of unaccounted-for personnel to the Assembly Area Leader.

6. Personnel reporting to the Technical Support Center, Control Room, and Operational Support Center will report their arrival to the Emezgency Communicator - Technical Support Center, Emergency Communicator - Control Room, or Operational Support Center Leader, respectively.

7. Assembly Area Leadexs, the Operational Support Center Leader, the Emergency Communicator - Technical Support Center, the Emergency Communicator-Control Room, and the senior-on-site member of the, security organization will report the names of any personnel who have not been accounted for within 25 minutes after the emergency was declared to the Emergency Security Team Leader in the Technical Support Center.

8. The Emergency Security Team, Leader will .report a consol-idated summary of all missing pexsonnel to the Logistics Support Director (or Site Emergency Coordinator) within 30 minutes after the Emergency is declared. The Logistics Support Director will notify the Site Emergency Coordinator if any personnel are missing.

9. The Site Emezgency Coordinator will direct, the Plant Opezations 'Director to implement PEP-394, "Search and Rescue," if any personnel are missing.

10. Personnel who are alternate designees fo2 emergency positions, and those without emergency assignments will remain in the assembly areas at least until the Site Emergency Coordinator has determined that no additional personnel from the assembly areas are required to augment the emexgency organization. The Logistics Support Director will inform. the Assembly Area Leader(s) of which personnel to direct to report to emergency facilities to fill vacancies and/or augment the emergency organization.

Based on recommendations from the Radiological Control Director, the Site Emergency Coordinatoz decides what protective actions (if any) to implement for pexsonnel in the assembly areas. If on-site sheltering is implemented, personnel will remain in the assembly areas. If no protective actions are necessary, personnel may be allowed to return to work if conditions in their work area permit.

PEP-382 Rev. 0 Page 8 of 10

APR005 9'.'0" 'ROCEDURE" STEPS,

9. 2 MAINTAINING ACCOUNTABILITY l.

I All personnel on-site will ensure that their supervisor, foreman, or team leader is aware of their location at a)l times during the emergency by informing him before leaving their present building or facility of where they are going, and reporting their arrival when they get to the new location.

2. Supervisors, Foremen, and Team Leaders will report missing personnel to the Emergency Security Team Leader, 10.0'IAGRAMS ATI'ACHMENTS

1. Shelter/Assembly .Area Locations PEP-382 Rev. 0 Page 9 of 10

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AFR010 CAROLINA POWER &DELIGHT,COMPANY SHEARON HARRIS NUCLEAR POWER PLAiVZ PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-383 TITLE: ADMINISTRATION OF POTASSIUM IODIDE REVISION 0'PPROVED:

Signature Date TITLE:

PEP-383 Rev. 0 Page 1 of 13

APR010 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4 2.3 Other References 4 3:0 RESPONSIBILITIES 4 3.1 Site Emergency Coordinator 4 3.2 Radiological Control Director 5 3.3 Personnel Protection and Decontamination Team 5

4. 0 DEFINITIONS 5

5. 0 GENERAL 5 6.0 'INITIATING CONDITIONS 6 7.0 PRECAUTIONS/LIMITATIONS. 6 e.o SPECIAL TOOLS AND EQUIPMENT 6 9.0 PROCEDURE STEPS 7 9.1 Action of Radiological Control Director 7 9.2 Actions of Personnel Protection and Decontamination Team 7 10.0 DIAGRAMS/ATTACHMENTS 9

1. Instructional Material on the Use of Potassium S Iodide 10

2. Potassium Iodide Consent and 'Record Form 13 PEP-383 Rev. 0 Page 2 of 13

APRO10 LIST OF" EFFECTIVE. PAGES

~Pa e Revisions 1 thru 13 0 PEP-383 Rev. 0 Page 3 of 13

APR010 1.0 PURPOSE The purpose of this procedure is to partially implement section 4.6.3.3 of the SHNPP Emergency Plan, "Use of Pxotective Equipment and Supplies."

This procedure provides instructions for administering potassium iodide to emergency workers employed by Carolina Power 8 Light Company..

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 4.6.3.3, "Use of Protective Equipment and Supplies" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-204, "Radiological Control Director"

2. PEP-208, "Personnel Protection and Decontamination Team Leader" 2.3 OTHER REFERENCES

1. Department of Health, Education, and Welfare/ Food and Drug Administration Federal- Register Note FR No.232 December 15, 1978 "Potassium Iodide as a Thyroid Blocking Agent in a Radiation Emergency".

2. National Council on Radiation Protection and Measurements

, Report No.55, "Protection of the Thyroid Gland in the Event of Releases of Radioiodine", National Council on Radiation Protection and Measurements, Washington DC, 1977.

3. "Environmental Protection Agency, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," June 1980.

4. "Patient Package Insert for Thyro-Black", Wallace Laboratories, Inc. Publication CV-107915-10/79 3.0 RESPONSIBILITIES 3.1 SITE EMERGENCY COORDINATOR The Site Emergency Coordinator is responsible for authorizing the distribution of Potassium Iodide to on-site emergency workers.

PEP-383 Rev. 0 Page 4 of 13

APRO10 3;0, RESPONSIBILITIES 3.2 RADIOLOGICAL CONTROL DIRECTOR The Radiological Control Director is responsible for consulting with the Agreement physician as to the need for administration of Potassium Iodide. .The Radiological Control Directoz shall advise the Site Emergency Coordinator of any recommendation based on the consultation regarding the administration of Potassium Iodide to on-site personnel'.

3.3 PERSONNEL PROTECTION AND DECONTAMINATION TEAM Personnel Pzotection and Decontamination Team personnel are responsible= for administering potassium iodide to on-site personnel under the direction of the Radiological Control Director and agreement physician.

4 .0 DEFINITIONS

1. Agreement Physician - A medical doctor who has agreed to provide medical services as stated in (an) agreement letters(s) included in Annex A of the SHNPP Emergency Plan.

5.0 GENERAL The release of substantial quantities of radioiodines is postulated foz nearly every accident scenario that involves significant offsite exposures. These radioiodines pose a significant threat to the thyroid gland and will require protective action to minimize the thyroid exposure. Stable iodine is a useful agent to block the uptake of radioiodine by the thyroid gland. Blocking occurs when the thyzoid gland is saturated with stable iodine, thus preventing the uptake of radioactive iodine species. Potassium iodide has been approved by the Food aud Drug Administration for this use.

Potassium iodide must be taken. prior to exposure to radioiodine to be completely effective. Approximately 30 minutes are requized for the onset of blocking following administration. A substantial benefit is obtainable, howevez, when the potassium'odine is admin-*

istered within 3 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following acute exposure to radioiodine.

Limited benefits are obtainable up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following exposure.

Most of the radioiodine which is not taken up by the thyroid will be, eliminated from the body in about 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, however, some recizcu-lation is possible, so potassium iodide should be administered (about 130mg/day) for 3 to 10 days following confizmed acute exposure.

This procedure only applies to employees and contractors of CP&L.

CP&L personnel shall not supply potassium iodide to members of the general public. The risk of detrimental side effects from the short term use of potassium iodide foz thryoid blacking in a radiation PEP-383 Rev. 0 Page 5 of 13

APR010 5.0 GENERAL emergency have been determined by the U. S. Food and Drug Administration to be outweighed by the risks of radioiodine induced thryoid nodules or cancer at a projected dose to the thyroid gland of 25 Rem or greater (Reference 1).

6.0 INITIATING CONDITIONS

1. A release of radioactive iodine to the atmosphere has occurred, or is likely to occur, and projected thyroid doses to personnel are equal to or greater than 25 rem.

7.0 PRECAUTIONS LIHITATIONS

1. Potassium Iodide should only be administered if individual respiratory protection has been determined to be ineffectual or not feasible.

2. Potassium iodide has no effect for particulate radio-activity nor for noble gases. Appropriate protective measures must still be established for these types of airborne radioactivity.

3. There is no protection factor associated with the use of potassium iodide.

4. Potassium iodide will be administered in accordance with directives of the agreement physician. Since potassium iodide tablets have.a shelf life, they should not be if the expiration date has passed. 'dministered

5. ,Potassium iodide should not be used by individuals who know that they are allergic to iodine.

6. Potassium iodide should be administrated on a voluntary basis.

7. Whole body counting should be performed on individuals who have been administered potassium iodide to determine whether continued treatment 'is necessary.

8.0 SPECIAL 'TOOLS AND E UIPMENT

1. Whole, body counter (located in the Whole Body Counting Room)

2. Potassium Iodide tablets (located in the Technical Support Center and the Operations Support Center)

PEP-383 Rev. 0 Page 6 of 13

APR010 9,0 PROCEDURE STEPS 9.1 ACTIONS OF RADIOLOGICAL CONTROL DIRECTOR

1. The Radiological Control Director determines from the Dose Projection Team Leader, Personnel Protection and Decontam" ination Team Leader, Plant Monitoring Team Leader or others that conditions are such that personnel are likely to receive a significant dose (25rem) to the thyroid from radioiodine, and that alternative" protective actions are not feasible or would be ineffective.

2. 'he Radiological Control Director calls the agreement physician and:

Notifies the physician of the expected thyroid doses that will be received with and without the adminis-tration of potassium iodide.

Requests any guidance or recommendations that may be applicable to the specific situation, including how soon any allergic reactions are likely to occur and what actions should be taken if any do occur.

Obtains agreement from the physician to administer the KI.

~ Instructs the physician to standby in case there are any allergic reactions.

Logs any recommendations and the Doctors consent together with the date and time in the RCD Log book.

3. The Radiological Control Director notifies the Site Emergency Coordinator (and Radiological Control Manager, if the Emergency Operations Facility is activated) of the approval by the agreement physician to administer Potassium Iodide to selected personnel, and obtains authorization from the Site Emergency Coordinator to distribute it.

The Radiological Control Director directs the Personnel Pzotection and Decontamination Team Leader to administer potassium iodide to the selected personnel according to this procedure.

k 9.2 ACTIONS OF PERSONNEL'ROTECTION AND DECONTAMINATION TEAM The Personnel Protection and Decontamination Team Leader (or other available Personnel Protection and Decontamination Team personnel as directed by the Leader) performs the following steps.

PEP-383 Rev. 0 Page 7 of 13

APR010 9.0 PROCEDURE STEPS 9.2 ACTIONS OF PERSONNEL PROTECTION AND DECONTAMINATION TEAM (Cont'd)

1. Obtain authorization from the Radiological Control Director:to administer the potassium iodide.

2. Ask those individuals reporting to the potassium iodide administration locations if they have ever had an allergic reaction to iodide. Advise them that most table salt contains iodide.

3. Advise all'personnel that the use of potassium iodide is voluntary, have them.,read a copy of the Instructional Material on the Use of Potassium Iodide (Attachment 1) and ensure that they complete and sign the upper portion of a potassium iodide consent and record form (Attachment 2) before administering potassium iodide.

CAUTION: Administer potassium iodide only to individuals who are not allergic to iodide. Do not administer potassium iodide date has passed.

if its expiration Administer one potassium iodide tablet (100 mg. iodine per 130 mg. tablet) to each person.

5. Complete and sign the lower portion of the potassium iodide Consent and Record Form (Attachment 2) for each individual.

6. Instruct each individual to report, back the next day for an evaluation's to whether an additional dosage of potassium iodide is necessary.

7. On the following days, if it is known or suspected that an individual was actually exposed to elevated concentrations of airborne radioiodine at levels and for a duration whereby a dose commitment to his thyroid of 25 Rem could be exceeded, perform a whole body count for each individual (if possible) before the additional potassium iodide tablet is administered. lf the whole b~od burden of 1-131 is less then 17nCi, disoontinue administering potassium iodide. If a whole body count cannot be perfomsed or if the whole b~od burden exoeeds 17nCi, administer an additional dosage of potassium iodide and notify the Radiological Control Director. If actual exposure to an individual is not suspected, do not administer any additional tablets.

PEP-383 Rev. 0 Page 8 of 13

APROIO 10.. 0 DIAGRAMS(ATTACHMENTS

1. Instructional Material on the Use of Potassium Iodide

2. Potassium Iodide Consent and Record Form PEP<<383 Rev. 0 Page 9 of 13 H

APR010 ATZACER1ENT 1 INSTRUCTIONAL MATERIAL'n the USE OF POTASSIUM IODIDE General Many of the accident scenarios analyzed in the Shearon Harris Nuclear Plant Final Safety Analysis Report postulate the sudden release of large quantities of radionuclides, which might include a large number of isotopes of radioiodine, into the environment and into plant areas.

When iodines, including radioactive and non-radioactive, are inhaled or 'indigested, they rapidly accumulate in the thyroid gland. Radioiodines could reside in the thyroid gland long enough to allow localized radiation damage.

~ I In order to minimize the dose to the thyroid, some protective action must be taken to minimize uptake or to minimize the effects of this uptake. Saturating the thyroid with stable (or non-radioactive) iodine will "block" the thyroid, preventing the uptake of additional iodine. Most of the iodine indigested or inhaled,. but not absorbed by -the thyroid, will be eliminated from the body in about 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> by normal bodily processes. Thus, if stable iodine is administered prior to or immediately after (less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) exposure to radioiodine, the radioiodine will not, be taken up but rather, will be eliminated from the body.

Although a variety of chemical substances can block the accumu-lation of radioiodine in the thyroid gland, potassium iodide appears to,be the most suitable.

The blocking is essentially complete with a dosage of 100 mg iodide (130 mg potassium iodide).

The onset of blocking occurs at about 30 minutes following administration.

The blocking effect from a single dosage lasts about one day.

The potential for side effects is very low at the dosages involved.

PEP-383 Rev. 0 Page 10 of 13

APR010 General To be completely effective, the potassium iodide should be taken prior to exposure to radioiodine, or very shortly thereafter. Approximately 505 blocking will occur if'he iodide is administered vithin 3 to 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> after exposure.

Limited benefits are possible up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following acute exposure. Because of the potential for recirculation in the body, potassium iodide should be taken for 3 to 10 days folloving exposure to minimize the uptake af recirculated radioiodine.

Side Effects Potassium"iodide has been used videly for several years in the treatment of bronchial asthma. Daily oral doses of potassium iodide ranging from 300 to 1200 mg have been administered to patients over a long time. Only the repeated administration of daily doses far in excess of those necessary for thyroid blocking have resulted in significant side effects.

Although side effects are unlikely because of the small dose and short period of time that the drug would be used for thyroid blocking, effects noted have been:

The taking, of iodide has been associated vith skin rashes, swelling of the salivary glands, and iodism (burning in the throat. and mouton>, metallic taste, soreness of mouth and gums, symptoms of a head cold, and diarrhea). Also, allergic reactions may produce symptoms such as fever and pains in the joints, or on rare occasions swelling of various parts af the body wi'th severe shortness of breath.

Overactivity or underactivity of the thyxoid gland and/ar goiter. Symptoms of thyroid overactivity include nervousness, sweating, and rapid heartbeat.

If side effects are noted, report to your supervisor for possible transfer to a hospital or consultation vith a physician. Discontinue use of the potassium iodide. If the heartbeat's rapid and irregular, or if shortness of breath (associated with the iodide) is noted, seek medical attention immediately.

~Usa e The only people, who should not take potassium iodide are people who knov that they are allergic to iodide. (Note: table salt is commonly iodized). Yau may take potassium iodide even if you are taking medication for a thyroid problem. Pregnant and nursing women and childr'en may take the drug.

PEP"383 Rev. 0 Page 11 of 13

APR010

~Usa e I

Potassium iodide should be taken as soon as possible after you are directed. You will probable be directed to take one dosage every 24-hours for no more than 10 days. Do not take larger doses. Larger doses do not increase the radioiodine pro-tection, but may increase the chance of side effects.

Potassium iodide for emergency use will probably be provided in 130 mg tablets (corresponds to 100 mg iodide), but liquid solutions to be added to a glass of water may be used.

PEP-383 Rev. 0 Page 12 of 13

APR010 ATTACK'LENT, 2 POTASSIUM IODIDE CONSENT AND RECORD FOR"1 Full Name SSN Employer Employee No.

I have read "Instructional Material on the use of Potassium Iodide" and understand its contents. To the best of my knowledge, I am not allergic to iodide. I voluntarily consent to receive a dosage of 130 mg/day of KI for the next 10 days, or until it can be. determined that I have not ingested significant quantities. of radioiodines.

Employee Signature Date Initial dosage administered:

Lot number Expiration Date Administered by Signature Date Time PEP-383 Rev. 0 Page 13 of 13

S APR002 CAROLINA POWER &. LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: 'LANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP"384 ACCESS CONTROL REVISION 0 APPROVED:

Signature vniz ~C PEP-384 Rev. 0 Page 1 of 13

APR002 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4 2.3 Other References 4 3.0 RESPONSIBILITIES 5 3.1 Assembly Area Leaders 5 3.2 Personnel Protection and Decontamination Team Members 5 3.3 Emergency Security Team Leader 5 3.4 Members of the Security Force 5 4.0 DEFINITIONS 6 5.0 GENERAL 6 6.0 INITIATING CONDITIONS 7 7.0 PRECAUTIONS AND LIMITATIONS 7 8.0 SPECIAL TOOLS AND EQUIPMENT 8 9.0 PROCEDURE STEPS 8 9.1 Unusual Event 8 9.2 Alert 9 9.3 Site Emergency 10 9.4 General Emergency 11

10. 0 DIAGRAMS/ATTACHMENTS 12

1. Access Control Points and Varning Points 13 PEP"384 Rev. 0 Page 2 of 13

APR002 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 through 13 0 PEP-384 Rev. 0 Page 3 of 13

APRO02

~ n 1.0 PURPOSE The purpose of this procedure is to implement Section 4.5.3, "Public Alerting, Warning,- and Notification," Section 4.6.1, "On-site Alerting, Warning, and Notification," and Section 4.8, "Security Measures" of the SHNPP Emergency Plan.

This procedure provides instructions for controlling the movement of site personnel during an evacuation of the site,,controlling the movement of members of the general public inside the Exclusion Area during an emergency, controlling ingress and egress to the Exclusion Area, Protected Area and the Emergency Operations Facility during an Emergency.

2.0 REFERENCES

2.1 Emergency Plan References

1. 2.4.5.3, "Emergency Security Team Leader"

2. 2.4.5.4, "Assembly Area Leader"

3. 2.4.6.7, "Personal Protection and Decoritamination Team Leader"

4. 4.5.3, "Public Alerting, Warning, and Notification"

5. 4.6.1, "On-site Alerting, Warning, and Notification"

6. 4.8 "Security Measures" 2.2 Referenced Plant Emergency Procedures

1. PEP-208, "Personnel Protection and Decontamination Team Leader"

2. PEP-215, "Assembly Area Leader"

3. PEP-301, "Notification and Communications"

4. PEP-381, "Evacuation"

5. PEP-382, "Personnel Accountability" 2.3 Other References 1, SP-016, "Emergency Plan Support"

2. Code of Federal Regulations, Title 10, Part 100

3. Final Safety Analysis Report, Section 2.1.2.2

4. Final Safety Analysis Report, Section 2.1.2.3 PEP-384 Rev. 0 Page 4 of 13

APR002 3.0 RESPONSIBILITIES 3.1 Assembly Area Leaders Assembly Area Leader(s) are responsible for performing accountabil>>

ity functions and additionally directing and controlling personnel in the assembly areas as per PEP-215. In conjunction with Personnel Protection and Decontamination Team members, the Assembly Area Leader(s) are responsible for directing personnel/vehic)es to monitoring locations or to decontamination areas if the person" nel/vehicles are known or suspected to be contaminated.

3.2 Personnel Protection and Decontamination Team Members The Personnel Protection and Decontamination Team(s) are responsible

-for surveying assembly area(s), for monitoring personnel/vehicles at assembly areas (or monitoring areas they establish), for supervising the decontamination of contaminated personnel/vehicles (at decon-tamination areas) and for controlling the flow of personnel/vehicles at monitoring and decontamination areas as per PEP-208.

3.3 Emergency Security Team Leader The Emergency Security Team Leader has the responsibility to:

1. Direct members of the security force to control access at the east end of the plant access roads during an Alert or at the Exclusion Area Boundary during a Site or General Emergency.

2. Direct a member of the security force to exclude any rail traffic during a Site or General Emergency except as authorized by the Site Emergency Coordinator.

3. Direct a member of the security force to provide access control at the Emergency Operations Facility if it will be activated.

4. As needed, direct members of the security force to assist the Sheriff's Department in warning members of the public on the Harris Reservoir during a Site or General Emergency.

3.4 Members of the Security Force Upon direction from the Emergency Security Team Leader, members of the security force will provide warning and access control functions during a Site and General Emergency in addition to theiz normal security duties as follows:

1. Control access at the east end of the plant access roads during a Site Emergency and. at the Exclusion Area Boundary during a General Emergency.

2. Direct any railway vehicles/personnel to depart the site and close the railway barrier during a Site or General Emer-gency.

PEP-384 Rev. 0 Page 5 of 13

APR002 3.0 RESPONSIBILITIES 3.4 Members of the Security Force (Cont'd)

3. Warn the public on the Harris Reservoir by using a siren, smoke, and flares at the operations access road causeway and at, the auxiliary dam.

4. Provide access control at the Emergency Operations Facility.

5. At declaration of Site Emergency ready the patzol boat for use by a Sheriff's Deputy. If the Deputy has not arrived within 45 minutes after declaration, of a Site Emergency, Security will launch the patrol boat on the main reservoir and begin the warning process.

4.0 DEFINITIONS

1. Exclusion Area - An Exclusion Area is an area specified for the purpose of reactor site evaluation in accordance with 10CFR100. It is an area of such size that an indi; vidual located at any point on its boundary for two hours immediately following onset of the postulated release would not receive a total radiation dose to the whole body in excess of 25 rem or a total radiation dose of 300 rem to the thyroid from iodine exposure. The exclusion area around the SHNPP is CP&L owned property with a radius of approximately 7000 feet.

2. Protected Area - An area of the plant site encompassed by physical barriers to which access is controlled.

3. Radiolo icall Controlled Area - An area to which access is controlled for the purpose of limiting radiation exposure or preventing the spread of contamination.

4. Site - The area inside of an 'approximate 2500 foot radius from the plant center line, inclusive of the area. cleared for plant construction, and including all permanent and temporary buildings, the pazking lots, and concrete plant.

5.0 GENERAL When an Alert (or higher emergency classification) is first an-nounced, all personnel in the Protected Area, except for Shift Operating Personnel and on duty security personnel, are directed to assemble in the Fuel Handling Building Auditorium and Lunchroom (or other announced location). All personnel on-site outside the Protected Area assemble at the Construction Warehouse (or other announced area). Assembly Area Leaders, assisted by foremen and supervisors, perform accountability of personnel and direct and control personnel at the assembly areas (see PEP-382).

PEP-384 Rev. 0 Page 6 of 13

APR002

5. 0 GENERAL After personnel have initially assembled, security can check, via the security computer, whether any personnel other than Shift Operating Personnel are within security zones other than the general Protected Area zone (see SP-016).

If traffic control into the Site is required security closes the gates and/or posts personnel on the entrance roads. If traffic control into the Exclusion Area becomes necessary barriers are placed across state roads and railway spurs at the boundary of the Exclusion Area, telephone company activities are prohibited, and control of public access is maintained by plant security as described in this procedure. Assistance is provided by local agencies in accordance with agreements in the emergency plan (FSAR

'Section 2.1.2.3).

Signs are posted along both roads (and the rail spur) at the Exclu-sion Area boundary stating that the area is an Exclusion Area and advising that persons therein are sub)ect to evacuation (FSAR Section 2.1.2.2).

Signs are posted wherever the easement (granted to Southern Bell for telephone lines) intersects the Exclusion Area boundary, stating that the area is an Exclusion Area and advising that anyone therein is subject to evacuation (FSAR Section 2.1.2.2).

Warning signs are also posted at known points of entry on the Exclusion area boundary (land used for 'public recreation) and buoyed in conspicuous locations within and on the boundary of reservoir waters (used for public recreation) inside the Exclusion Area (FSAR Section 2.1.2.2).

When a Site Emergency is dec'lared a County Sheriff's Department deputy drives around Harris Reservoir and warns the public by stopping at locations near the water using his siren, public address system, flares, and smoke grenades to warn the public. Another deputy proceeds to the plant site and mans the Harris patrol boat while using a siren, public address system, smoke, and flares to warn the public on or near the reservoir. Security uses a siren, flares, and smoke grenades at the operations access road causeway and at the auxiliary dam to assist in the coverage of the reservoir.

If the emergency escalates to a General Emergency prior to the arrival of the deputy, a member of the security force will man the patrol boat and commence warning activities as presczibed above.

6.0 INITIATING CONDITIONS

l. An emergency has been declared.

7.0 PRECAUTIONS AND LIMITATIONS

'I,

1. Verify that the railway spur barrier at the Exclusion Area Boundary is closed by visual inspection.

PEP-384 Rev. 0 Page 7 of 13

APR002 8.0 SPECIAL TOOLS AND E UIPMENT

1. Signs posted at all major entzy points to the Exclusion Area advising personnel they are subject to evacuation.

2. Signs notifying recreational users of the Harris Reservoir to evacuate the reservoir upon hearing sirens, seeing red flares or red smoke, and tune to an Emergency Broadcast System radio.

3. Patrol boat

4. Traffic cones and signs

5. Megaphones

6. Portable road barriers with warning lights

7. Flares and smoke grenades.

9.0 PROCEDURE STEPS If an emergency classification higher than Unusual Event is initial-ly declared, start at the applicable section.

9.1 Unusual Event 9.1.1 If personnel in the Control Room announce over the public address system that a particular area inside the Protected Area is to be evacuated, security will conduct a computer check of access control records to determine if the area(s) has been properly evacuated.

9.1.2 The senior member of the security force notifies the Emezgency Security Team Leader, or if this position is not yet activated, the Site Emergency Coordinator of the results.

9. 1.3 The Emergency Security Team Leader notifies the Logistics Support Director or, if this position is. not yet, activat-ed, the Site Emergency Coordinator of the results, pzo-vides recommendations, and advises of actions in progress if the situation is a security emergency.

9.1.4 The Logistics Support Director or Site Emergency Coordinator determines if any personnel still in the area should be there (i.e. they are part of Shift Operating Crew or Radiation Protection staff performing evaluations or taking other corrective actions) and take appropriate action (such as paging them by name or requesting a search and rescue team be sent to locate the person(s)).

PEP-384 Rev. 0 Page 8 of 13

APR002 9.0 PROCEDURE STEPS 9.2 Alert 9.2. 1 The Assembly Area Leaders, in conjunction with foremen and supervisors, perform accountability functions, direct personnel, and control access at the Assembly Area(s) in accordance with PEP-382.

9.2.2 Security personnel check the security computer for those personnel who are in security zones other than the Assem-bly Area(s) or emergency facility locations (i.e. Control Room, Technical Support Center, Operational Support Center or Auxiliary Shutdown panel area) and notify the Emergency Security Team Leader of the results.

9.2.3 The Emergency Security Team Leader notifies the Logistics Support Director, or if this position is not yet activat-ed, the Site Emergency Coordinator of the results of the check. 'omputer 9.2.4 The Logistics Support Director or Site Emergency Coordinator determines if these people should be there and takes appropriate action.

9.2.5 Ef the Emergency Security Team Leader (at the advice or direction of the Radiological Control Director) directs Security personnel to temporarily evacuate the Radiologically Controlled Area, the senior member of the security force directs security personnel to accomplish this per SP-016.

9.2.6 Xf there is a train on site, the senior member of the security force dispatches a member of the security force to escort the train (or engine) and all railroad personnel off-site and close the rail spur barricade unless the Logistics Support Director or Site Emergency Coordinator authorizes them to be on-site.

NOTE: Check with Personnel Protection and Decontamination Team Leader to determine if the train needs to be monitored prior to release.

9.2.7 The senior member of the security force gives instructions for a member of the security force to close the contractor gate and post himself at, the normal construction gate. A second member of the security foxce is instructed to post himself at the CP&L entrance to limit access to emergency vehicles and members of the CP&L staff with company identification cards or those authorized by the Logistics Support Director or Site Emergency Coordinator via the Emergency Security Team Leader.

PEP-384 Rev. 0 Page 9 of 13

APR002 9.0 PROCEDURE STEPS 9.2 Alert (Cont'd) 9.2.8 The Emergency Security Team Leader checks with the Site Emergency Coordinator. to determine if the Emergency Operations Facility is being activated. If so, he directs the senior member of the security force to post a member of the security force at the Shearon Harris Energy and Environmental Center to provide access control for the Emergency Operations Facility.

9.2.9 Members of the security force stop incoming vehicles and check to verify that personnel are local emergency re-sponse personnel (police, fire or rescue squad members) or emergency response organization personnel reporting for duty. Proper verification includes:

1. Appropriately marked emergency vehicle with personnel in uniform or with appropriate identification. (If not previously notified that emergency vehicles have been called as per PEP-301, check with the Emergency Security Team Leader or alternate prior to allowing them to enter'the area.)

2. Emergency response organization personnel have CPEL marked vehicles and/or CP&L identification cards.

3. Emergency response organization personnel from other organizations (Daniel, Westinghouse, INFO, etc.) have identification and are on a personnel list(published by the Senior Specialist-Emergency Preparedness) or are authorized by the Logistics Support Director or Site Emergency Coordinator via the Emergency Security Team Leader.

9.3 Site Emergency 9.3.1 Perform steps 9.2.1 through 9.2.6.

9.3.2 The senior member of the security force directs one member of the security force to go to the Exclusion Area Boundary

'on State Route 1134 and another to go to the boundary on State Route 1135 to place a barricade (or cones) across the entry lane to limit access to authorized personnel.

9.3.3 The Emergency Security Team Leader directs the senior member of the security force to post a member of the security force at the Shearon Harris Energy and Environ-mental Center, to provide access control for the Emergency Operations Facility.

PEP-384 Rev. 0 Page 10 of 13

APR002 9.0 PROCEDURE STEPS 9.3 Site Emergency (Cont'd) 9.3.4 Security personnel obtain traffic cones with signs (instructing personnel not to leave the parking area until directed to do so), place these cones near the exit from the parking areas dmd then proceed to their access control positions.

9.3.5 Security personnel stop and check incoming vehicles as per Step 9.2.8.

9.3.6 One or more members of the security force, as directed by the Emergency Security Team Leader, readies the patrol boat for the Sheriff's deputy, and provides warning on the reservoir by using a siren, flares, and smoke at the operations access road causeway and the auxiliary dam.

9.3.7 If an evacuation of the site is announced, the Emergency Security Team Leader provides instructions to security personnel regarding evacuating personnel.

9.3.8 Personnel Protection and Decontamination Team members check personnel and/or vehicles, if directed, in the parking lot (or other monitoring area) and control person-nel movement at the monitoring areas.

9.4 General Emergency 9.4.1 Perform Steps 9.3.1 through 9.3.6 9.4.2 If the Sheriff's deputy has not arrived yet to man the patrol boat, the senior member of the security force notifies the Emergency Security Team Leader and directs a member of the security force to man the patrol boat. The member of the security force'uses the siren, public address system, smoke, and flares to warn the public on or near the reservoir until relieved by the Sheriff's deputy.

9.4.3 If an evacuation of the Exclusion Area is announced, the Emergency Security Team Leader provides instructions to security personnel regarding evacuating personnel and vehicles.

9.4.4 The Emergency Security Team Leader provides instructions, after consulting with the Personnel Protection and Decon-tamination Team Leader or Radiological Control Director, as to what protective equipment is required and arranges for issuance to security personnel at access control points o PEP-384 Rev. 0 Page 11 of 13

APR002

10. 0 DIAGR&iS/ATI'ACHMENTS

1. Access Control Points and Varning Points

.PEP-384 Rev. 0 Page 12 of 13

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PEP-391 Rev. 0 Page 16 of 39

APR010 ATTACHMENT 3 DIAGRAM OF REX HOSPITAL FACILITIES (Later)

PEP"391 Rev. 0 Page 17 of 19

APR010 ATTAC19iENT 4 DIAGRAH OF WAKE HEDICAL CENTER FACILITIES (Later)

PEP-391 Rev. 0 Page 18 of 19

APR010 ATTACHHENT 5 CONTP21INATED INJURED PERSONNEL LOG Date: Time:

Injured Person:

Transporting person(s):

(ambulance driver, CP6L driver, etc.)

Accompanying person(s):

(Personnel Protection and Decontamination Team, Environmental Honitoring Team, etc.)

Vehicle number:

(License jj, CPEL no., etc.)

Persons Involved in Treatment Exposure The Transportation Vehicle(s) has been monitored, decontaminated (if necessary), and released.

Record all recommendations, actions, and other data below.

PEP-391 Rev. 0 Page 19 of 19

AFR005 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP"394 TITLE: SEARCH AND RESCUE REVISION 0 APPROVED:

Signature Date TITLE:

PEP-394 Rev. 0 Page 1 of 14

APR005 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4 2.3 Other References 4.

3.0 RESPONSIBILITIES 4 4.0 DEFINITIONS 5 5.0 GENERAL 5 6.0 INITIATING CONDITIONS 5 7.0 PRECAUTIONS/LIMITATIONS. 5 7.1 Selection of Search and Rescue Personnel 5 7.2 Conduct of Mission 6 7.3 Rescue Priorities 6 8.0 SPECIAL TOOLS AND EQUIPMENT ,7 9.0 PROCEDURE STEPS 7 9.1 Initial Actions 7 9.2 Activation of Search and Rescue Team 8 9.3 Conduct of the Search and Rescue 10 10.0 DIAGRAMS/ATTACHMENTS 13 Attachment 1, Search and Rescue Team Briefing Form 14 PEP-394 Rev. 0 Page 2 of 14

APR005 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 thru 14 0 PEP-394 Rev. 0 Page 3 of 14

APR005 1.0 PURPOSE The purpose of this procedure is to implement Section 4.6.2 of the SHNPP Emergency Plan, "Evacuation and Personnel Accountability."

This procedure provides instructions for search and rescue measures necessary to locate personnel who are unaccounted for following accountability, and/or to rescue personnel who are trapped or disabled.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 4.6.2, "Evacuation and Personnel Accountability"

2. Section 4.6.3, "Radiological Exposure Control" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-301, "Notifications and Communications"

2. PEP-303, "Use of Communications Equipment"

3. PEP-371) "Emergency Response in Radiological Areas"

4. PEP-381) "Evacuation"

5. PEP-382, "Personnel Accountability"

6. PEP-383, "Administration of Potassium Iodide"

7. PEP-391, "First Aid and Medical Care"

2. 3 OTHER REFERENCES

1. SP"016, "Emergency Plan Support"

2. HPP-005, "Entry Into Radiological Areas"

3. HPP-251, "Personnel Decontamination" 3.0 RESPONSIBILITIES

1. PLANT OPERATIONS DIRECTOR The Plant Operations Director is responsible to the Site Emergency Coordinator for directing search and rescue operations.

2. FIRST AID TEAM LEADER (MEMBER)

The First Aid Team is responsible for searching for, locating, rescuing, and providing first aid to missing, trapped, and/or injured personnel during an emergency.

For the purposes of this procedure, the First Aid Team Leader is the Search and Rescue Team Leader.

PEP-394 Rev. 0 Page 4 of 14

APR005 4.0 DEFINITIONS None Applicable 5.0 GENERAL None Applicable 6.0 INITIATING CONDITIONS

1. One or more individuals are missing following accountability efforts (discussed in PEP-382).

2 ~ A report has been received of an individual trapped or disabled within the Plant.

7.0 PRECAUTIONS LIMITATIONS 7.1 SELECTION OF SEARCH AND RESCUE PERSONNEL

1. The search and rescue team should normally be composed of:

A First Aid Team member who is trained to perform the following procedures should be the search and rescue team leader:

Search for unaccounted for personnel; Rescue injured and/or trapped personnel; If possible, an individual who is an Emergency Medical Technician should be selected as the Team Leader or sent as a team member.

~ The missing person's supervisor or member of his work group;

~ A member of the security force {if available)...

~ A Personnel Protection & Decontamination Team Member They may be augmented by other personnel (such as radia-tion control, operations, maintenance, etc.) depending upon conditions at the time.

2. Since search and rescue personnel may receive increased exposure, they should be volunteers and be broadly familiar with the consequences of any, exposure received under emergency conditions (as discussed in PEP-371).

PEP-394 Rev. 0 Page 5 of 14

APR005 7.0 PRECAUTIONS LIMITATIONS (Cont'd) 7.2 CONDUCT OF MISSION

1. Conduct search and rescue missions in accordance with planned routes and actions as directed by the Plant Operations Director.

2. Team personnel should establish and maintain constant communications (via sight or radio, if possible) with'he team leader. (See PEP-303 for use of communications equipment.)

3. If an individual is trapped or disabled in a high radia-tion area, the rescue must be performed as expeditiously as possible to minimize the dose to the victim and the doses to the rescue personnel, and to ensure that first aid can be provided as soon as possible. Refer to PEP-371.

~ In an emergency situation, an exposure of up to 75 rem is appropriate if necessar to save a life.

~ If the situation is not one of life or death, but requires action to minimize the excessive exposure of the victim, rescue personnel may be allowed to receive doses up, to 25 rem.

~ If the situation is other than that described in the two steps above, normal Plant radiation exposure guides and regulatory. exposure limits apply.

7. 3 RESCUE PRIORITIES Rescue of a victim shall take precedence over fire-fighting efforts, unless the fire can be put out quickly with no detrimental effect to the victim, the fire must be suppressed to effect rescue, the fire poses an immediate threat. to the lives of others or the fire poses a threat to reactor safety,

2. Rescue of a victim shall take precedence over isolation of high energy fluids (steam, hot water under pressure, hydraulic fluids, etc.) unless isolation of the system is necessary to effect rescue, failure to isolate the system will seriously affect reactor safety, or failure to isolate the system will place the lives of other personnel in immediate danger.

PEP-394 Rev. 0 Page 6 of 14

APR005 8.0 SPECIAL TOOLS AND E UIP>KNT Appropriate equipment from the Operational Support Center for the particular mission will be selected from the following list:

Self reading pocket dosimeters - normal and high range (usually 500mR and 10R)

2. Thermoluminescent dosimeters (TLD)

3. Protective clothing (coveralls, hoods, gloves, booties)

4. Respiratory protection equipment (self contained breathing apparatus or respirator with iodine and particulate canister)

5. Normal and high range portable radiation survey equipment

6. First aid bag or kit

7. Stretcher and blanket

8. Searchlights or flashlights

9. Rope

10. Portable radios

11. Other tools in rescue cabinets, machine shop or elsewhere as needed to extricate a trapped person 9.0 PROCEDURE STEPS 9.1 INITIAL ACTIONS As soon as it is recognized that one or more individuals are missing, the Emergency Security Team Leader, Assembly Area Leader or the individual's Supervisor shall attempt to determine the possible location of the mi:ssing individual as per PEP-382. If following these efforts the individual is still unaccounted for, the Logistics Support Director (or Site Emergency Coordinator if the Logistics Support Director position is not activated) shall be notified as per PEP-382 and the following information provided:

~ Name(s) and badge numbers of individual(s) missing

~ Summary of efforts performed to locate the indi-vidual(s)

~ Last known location(s) of the individual(s) 1 The Logistics Support Director in turn notifies the Plant.

Operations Director who will activate the Search & Rescue Team ~

2. If personnel accidentally discover an individual needing rescue and/or medical assistance, the discoverer should:

~ Effect immediate rescue in accordance with the provisions of this procedure, if required and if within the capabilities of the individual(s) finding the victim.

PEP-394 Rev. 0 Page 7 of 14

APR005 9.0 PROCEDURE STEPS (Cont'd) 9.1 INITIAL ACTIONS (Cont'd)

~ Report the discovery of the victim to the Control Room and provide as much of the following information as is readily available:

Number of injured personnel and cause.

Location of the injured personnel.

and severity of injuries. 'ature Whether life sustaining actions are needed, whether they are being performed and/or whether the caller is capable of performing them.

Approximate radiation level (and contamination level, if known) where the injured are located.

Any complications affecting rescue and/or first aid efforts.

Name of caller and names of injured (if known).

~ Perform immediate life saving first aid if required and if within the capabilities of the individual(s) finding the injured person.

9.2 ACTIVATION OF SEARCH AND RESCUE TEAM Upon receipt of a report that an individual is missing or requires rescue, the Plant Operations Director (Site Emergency Coordinator or Shift Foreman if the Technical Support Center is not activated) will direct the search and rescue effort as follows:

~ Direct an announcement over'he PA system:

EXAMPLE MESSAGE "~-

"ATTENTION ALL PLANT PERSONNEL. THE FOLLOWING INDIVIDUAL(S) IS MISSING WITHIN THE PLANT (name

" INDIVIDUAL(S),

OF THE PLEASE CONTACT THE CONTROL ROOM ~

or "ATTENTION ALL PLANT PERSONNEL. AN INDIVIDUAL(S)

~(NAME IS MISSING/TRAPPED/ DISABLED WITHIN '

ecif location THE SUPERVISOR OF name of missin individual s AND SEARCH AND RESCUE PERSONNEL ASSEMBLE AT THE OPERATIONAL SUPPORT CENTER 'or other s ecified location PEP-394 Rev. 0 Page 8 of 14

APR005 9.0 PROCEDURE STEPS (Cont'd) 9.2 ACTIVATION OF SEARCH AND RESCUE TEAM (Cont'd)

~ Have the alarm and announcement repeated at least once.

2. The search and rescue team leader will contact the Plant Operations Director (Control Room if Technical Support Center not activated) and be briefed on the situation.

3. The Plant Operations Director (Site Emergency Coordinator or Shift Foreman if Technical Support Center is not activated) will determine from the team leader what personnel are available and will select the personnel that best meet the requirements of Section 7.1 (i.e., volun-teers, appropriately trained and knowledgeable about the consequences of emergency radiation exposures).

4. The Plant Operations Director (or Site Emergency Coordinator, depending upon the situation) will provide the available information to the search and rescue team leader. He may use Attachment 1, "Search and Rescue Team Briefing Form" depending upon radiological conditions in the area to be searched. Some of the things that are discussed if known and: if appropriate are:

Assembly location for the search & rescue team (Preferably in the Operational Support Center unless the Plant Operations Director indicates a more suitable location)

General radiation levels of areas to be searched (check area radiation monitoring systems and process radiation monitoring system).

Problems with equipment or operations that are likely drastically affect radiation levels in the

'o search area.

Data on the individual:

- Name and badge number

- Location, last known location, or likely location if known

- Physical description of individual Any known complications that might affect the search such as:

- High radiation levels, airborne activity levels, or contamination levels

- Fire, smoke, or toxic chemicals

- Gas, steam, water, or other fluid releases

- Wreckage PEP-394 Rev. 0 Page 9 of 14

APR005 9.0 PROCEDURE STEPS (Cont'd) 9.2 ACTIVATION OF SEARCH AND RESCUE TEAM (Cont'd)

~ Suggested search areas or routes

~ Suggested rescue equipment

5. If plant radiological conditions are abnormal or unknown, or the team is likely to enter high radiation or contamination areas on their search route, the Personnel Protection and Decontamination Team Leader specifies protective equipment and authorized doses for team personnel.

9,3 CONDUCT OF THE SEARCH AND RESCUE NOTE: If potassium iodide tablets are used by team members'or are administered to victims it should be in accordance with PEP-383, "Administration of Potassium Iodide."

The search and rescue team leader will:

Assemble his team, Brief his team, Identify necessary protective equipment, rescue equipment and first aid supplies to be taken; and Check that his team has the appropriate equipment and preparation for the mission NOTE: The team may be augmented with other personnel such as security, maintenance, operations, etc., and/or subdivided as necessary.

If a search pattern has not been given to the team leader, he will determine a pattern. If the team has to deviate from a predetermined pattern the team leader and the Technical Support Center (or Control Room) will be notified so that the team can be advised if there may be any problems as a result of the change of pattern.

3. If'the Technical Support Center (Contzol Room) r'eceives a report on the location of the missing individual, the Plant Operations Director (or other individual) will contact the .team leader via the radio (or PA System) and direct him to the scene.

4. Upon arrival of the team at the scene, the Personnel Protection and Decontamination Team member should enter the area and assess the radiological situation, if condi-tions permit. Entry into unknown radiation areas in the Controlled Area of the plant should be conducted as described in HPP-005, "Entry Into Radiological Areas".

PEP-394 Rev. 0 Page 10 of 14

APR005 9.0 PROCEDURE STEPS (Cont'd) 9.3 CONDUCT OF THE SEARCH AND RESCUE (Cont'd)

5. 'If the missing individual is located and is injured go to step 6. If he is not trapped proceed as follows:

~ Based upon who the individual is (i.e.,

worker, construction worker, etc.), the

'conditions of the area(s) where he has I other appropriate circumstances, he is directed) to the proper location (Radia access control point, Operational Suppo Security Building, etc.) for dosimetry debriefing, etc.

~ The search and rescue team leader notif Operations Director (or Site Emergency the Emergency Security Team Leader 'n

- The name and badge number of the he was found.

indi'here

- The location where he is being escort to report.

- Whether the team is returning to the Support Center (or other location).

-. Whether the team is continuing to sea locations that will be searched.

~ If the search is discontinued, the tean

- Returns to the Operational Support C~

area as directed by the Plant Operat:

- Completes dose information and turns briefing form', if used, to the Plant Director.

<< Discontinues the use of this procedu

~ If the search is continued, return to

6. The team leader if qualified (or medically individual) evaluates:

The injuries and physical condition o found, The radiological hazards affecting ea the rescuers Other conditions affecting the rescue PEP>>394 Rev. 0

APR005 9.0 PROCEDURE STEPS (Cont'd) 9.3 CONDUCT OF THE SEARCH AND RESCUE (Cont'd)

NOTE: IF AN INJURY IS SEVERE, RADIOLOGICAL CONDITIONS ARE CONSIDERED SECONDARY TO IMMEDIATE MEDICAL TREA'IVKNT UNLESS ACUTE RADIATION HAZARD FOR THE CASUALTY EXCEEDS THE INJURY HAZARD. FOR LIFE SAVING PURPOSES, 75 REM IS THE MAXIMUM EXPOSURE ALLOWED TO THE RESCUERS. THE CASUALTY SHOULD BE LIMITED TO 75 REM IF POSSIBLE.

7. After evaluating the situation, the search and rescue team leader specifies the course of action to be taken and directs the team in the completion of the rescue and/or first aid efforts, and/or requests additional support from the Control Room.

8. If a rescue cannot be carried out immediately, life sustaining first aid is given to the individual in the affected area, if necessary, as per PEP-391, "First Aid and Medical Care," to ensure heart, beat, breathing, and stoppage of excessive bleeding.

9. The team leader notifies the Technical Support Center (Control Room) that the individual(s) have been located, if not previously done, and provides the following inform-possible:

ation as soon as Number and location of trapped or injured personnel Name(s) and badge number(s) of trapped or injured personnel Extent of injuries and cause (if known)

Dose rates in the area (and contamination or airborne activity conditions, if known)

Whether additional support, a doctors assistance or an ambulance is needed and where it should respond.

(The Site Emergency Coordinator will obtain medical assistance or an ambulance as discussed in PEP-301, "Notifications and Communications. ")

NOTE: If a contaminated, injured person is sent to a hospital it is considered an Unusual Event (and also a Significant Event) and must be reported to the NRC within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> as in PEP-301 "Notifications and Communications."

10. As soon as it is advisable, the team removes the injured if person to the closest safe area (or first aid room conditions permit) and performs any required (or additional) first aid or medical treatment as discussed in PEP-391, "First Aid and Medical Treatment." If the person is likely to be contaminated (if in the Controlled Area assume he is) check for contamination and, if necessary, decontaminate, conditions permitting, prior to the injured leaving the site.

PEP-394 Rev. 0 Page 12 of 14

APR005 9.0 PROCEDURE STEPS (Cont'd) 9.3 CONDUCT OF THE SEARCH AND RESCUE (Cont'd)

11. If there are other missing personnel, the team leader may assign one or more personnel from the team to care for the injured or may turn the injured over to other medically qualified personnel and may use a portion or all of his team to continue the search as in step 9 '.2.

12. If there are no other missing personnel, the team leader will assist the Plant Operations Director in assuring timely and appropriate treatment of the victim is per-formed, as per PEP-391.

I

13. The team leader will close out the incident by:

Completing the Search and Rescue Briefing form, if used (i.e. dosimeter readings)

Reporting of events after the victim leaves the site (if he is accompanied to a hospital for treatment)

Assisting Regulatory Compliance in the Description of events for report to NRC, if required 10.0 DIAGRAMS ATTACHMENTS

l. Attachment 1, Search and Rescue Team Briefing Form PEP-394 Rev. 0 Page 13 of 14

APR005 ATTACHMENT 1 SEARCH AND RESCUE TEAM BRIEFING FORM

1. Date: Time: Briefing at: Team ID:

2. Briefing by:

3. Missing Individual: Name Badge No.

Last Location Description

4. Unusual Area/Env. Conditions:

~ ~

4

5. Communications Extensions:CR TSC OSC

6. Required Equipment: Search light Rope Other

7. Protective Equipment (check applicable):

. {1)

(2)

{3)

Self Reading Pocket Dosimeters Thermoluminescent dosimeters Respirator (8)

(9)

(10)

Gloves Booties Coveralls (4) . Self Contained Breathing Apparatus (11) Hood

{5) High Range Survey Equipment (6) Potassium Iodide C>> (7) Multigas Detector

8. Team member names and authorized doses (rem):

Lead Dose rem Asst.l Dose rem Asst.2 Dose rem

9. Team dosimeter readings (Before/After Mission):

Lead (500 mR Scale)- (5R Scale) /

Ass.t. 1(500 mR Scale)

Asst.2(500 mR Scale)

10. Special Instructions:

.0 See other side If block checked o .

PEP-394 Rev. 0 Page 14 of 14

APR016 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLAiNT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP"401 TITLE: RECORD KEEPING AND DOCUiiENTATION REVISION 0 APPROVED:

Signature Date TITLE:

PEP-401 Rev. 0 Page 1 of 8

APR016 TABLE OF CONTENTS'able

~Pa e of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 2.2 Referenced Plant Emergency Procedures 4 2.3 Other References 5 3.0 RESPONSIBILITIES 5 3.1 Record Preparers 5 3.2 Site Emergency Coordinator, Emergency Response 5 Manager, Directors,and Managers 3.3 Senior Specialist - Emergency Preparedness 5 4;0 DEFINITIONS 5 5.0 GENERAL 6 6.0 INITIATING CONDITIONS 6 7.0 PRECAUTIONS AND IIMITATIONS 6 8.0 SPECIAL TOOLS AND EQUIPMENT 6 9.0 PROCEDURE STEPS 6 9.1 Training Records 6 9 ' Drill Records 6 9.3 Exercise Records 6 9.4 Audit Records 7 9.5 Facility and Equipment,'ecords .7

.9.6 Emergency Records 7 9.7 Emergency Reports 8 10.0 DIAGRAMS/ATTACHMENTS 8 PEP-401 Rev. 0 Page 2 of 8

APR016 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 through 8 0 PEP-401 Rev. 0 Page 3 of 8

APR016 1.0 PURPOSE The purpose of this procedure is to implement Section 6.8, "Recovery Termination and Reporting Requirements," of the SHNPP Emergency Plan.

This procedure discusses the record keeping and documentation requirements for emergency preparedness.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 6.8, "Recovery Termination and Reporting Require-ments" 2 ~ Section 5.1.6, "Annual Independent Audit" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-102, "Site Emergency Coordinator - Control Room"

2. PEP-103, "Site Emergency Coordinator - Technical Support Center"

3. PEP-301, "Notification and Communications"

4. PEP-302, "Communication Activities"

5. PEP-321, "Notification of Emergency Personnel"

6. PEP-322, "Mobilization of Outside Organizations"

7. PEP-331, "Emergency Plant Monitoring"

8. PEP-341, "Manual Dose Projection"

9. PEP-342, "Automation of Dose Projection, ERFIS"

10. PEP-343, "Automation of Dose Proj'ection, IBM-PC"

11. PEP-351, "Emergency Environmental Monitoring"

12. PEP-362, "Interpretation of Liquid and Gas Samples"

13. PEP-371,. "Emergency Response in Radiological Areas"

14. PEP-383, "Administration of Potassium Iodide"

15. PEP-391, "First Aid and Medical Care"

16. PEP-394, "Search and Rescue" PEP-401 Rev. 0 Page 4 of 8

APR016

2. 0 REFERENCES 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

17. PEP-402, "Maintaining Readiness of Emergency Facilities"

18. PEP-403, "Performance of Training"

19. PEP-405, "Preparation of Activity Logs"

20. PEP-406, "Performance of Exercises and Drills" 2.3 OTHER REFERENCES

l. OMM-8, "NRC Reporting Requirements"

2. TI-906, "Training Records" 3.0 RESPONSIBILITIES 3.1 RECORD PREPARERS Functional team leaders, emergency communicators, phone talkers, log keepers, supervisors, managers and directors are responsible for assuring that legible records (checklists, surveys, forms, messages, and logs) of completed actions are prepared and maintained during an emergency. Personnel are responsible for supplying these records to their director or manager.

3.2 SITE EMERGENCY COORDINATOR, EMERGENCY RESPONSE MANAGER, DIRECTORS, AND MANAGERS The Site Emergency Coordinator, Emergency Response Manager, direc-tors and managers are responsible for seeing that their subordinates maintain appropriate records, for collecting these records, and for supplying these records to the Senior Specialist - Emergency Pre-paredness when the emergency is terminated.

3.3 SENIOR SPECIALIST - EMERGENCY PREPAREDNESS The Senior Specialist - Emergency Preparedness is responsible for collecting and maintaining all emergency related records following an emergency. He is also responsible for maintaining all emergency preparedness records not specifically assigned to another group.

4."0 DEFINITIONS None Applicable PEP-401 Rev. 0 Page 5 of 8

APR016 5.0 GENERAL

1. Corrections to records shall be made by drawing a single line through and initialing the incorrect entry, and not by erasures or the use of correction fluid.

2. All records shall be made by indelible means, such as ink or typing, and not with pencil or other erasable media.

6.0 INITIATING CONDITIONS None Applicable 7.0 PRECAUTIONS AND LIMITATIONS None Applicable 8.0 SPECIAL TOOLS AND E UIPMENT None Applicable 9.0 PROCEDURE STEPS 9.1 TRAINING RECORDS

1. Records of emergency preparedness training are maintained by the Harris Training Unit in accordance with TI-906.

9.2 DRILL RECORDS

1. Records of practical drills performed as part of initial training are maintained as part of the initial training record by the Harris Training Unit (see PEP-403 and TI-906) .

2. Records of test drills performed by subunits as continued training and/or testing are maintained by the subunit with a copy sent to the Harris Training Unit via the Senior Specialist Emergency Preparedness (see PEP-406).

9.3 EXERCISE RECORDS

1. Normal records (required by plant procedures) and emergen-cy records (required by emergency procedures) will be prepared by appropriate personnel (Managers, log keepers, etc.) as required during practical exercises and annual exercises (see PEP-406).

2. The Senior Specialist - Emergency Preparedness will collect and review exexcise recozds and will maintain any considered to be necessary f'r reference or demonstrating compliance with regulations.

PEP-401 Rev. 0 Page 6 of 8

APR016 9.0 PROCEDURE STEPS 9.4 AUDIT RECORDS The Corporate Quality Assurance Department will perform an independent audit of the SHNPP Emergency Preparedness Program on an annual basis. The records of these audits will be stored by the QA department as per their proce-dures with a copy to the Senior Specialist - Emergency Preparedness and other groups as specified in Section 5.1,6 of the SHNPP Emergency Plan.

2. The Senior Specialist - Emergency Preparedness (or others if appropriate)thewill prepare a response to any findings as copy of the necessary for Plant General Manager, and a response will be maintained with the copy of the findings for at least 3 years.

9.5'ACILITY AND EQUIPMENT RECORDS Records of facility and equipment checks, replacement of equipment and calibration of equipment, as specified in PEP-402, will be maintained by the Senior Specialist-Emergency Preparedness for a minimum of three (3) years.

9.6 EMERGENCY RECORDS emergency communicators, talkers, log Team members, keepers, and other personnel who fill phone out suzveys, ra-diation work permits, dosimetry records, or other forms as a necessary part. of their emergency function will prepare such records in a legible, accurate and timely manner.

Such records are forms included in or referenced by PEPs 102'03'01'02> 321s 322> 331> 341> 342' 3s 351>

362, 371, 383, 391, and 394.

2. Log keepers will prepare logs of events, messages, and major decisions in accordance with PEP-405 for the manager or director for whom they are keeping the log.

3. Directors, managers, and supervisors who do not have a log keeper should. keep a log of major events, messages, and

. major decisions in accordance with PEP-405.

4. After the emergency, personnel'r'e responsible for supply-ing these- records (or a legible copy) to their manager or director.-who in turn will give the records to the Senior Specialist - Emergency Preparedness.

5. The Senior Specialist Emergency Preparedness will maintain the records generated during the emergency for five (5) years.

PEP-401 Rev. 0 Page 7 of 8

APR016 9.0 PROCEDURE STEPS I

9.7 EMERGENCY REPORTS

1. The Plant General Manager will verify with the Director Regulatory Compliance that any required reports to the Nuclear Regulatory Commission are prepared and transmitted in a timely manner according to OMM-8, "Nuclear Regulatory Commission Reporting Requirements."

2. The Director - Emergency Preparedness will conduct an independent evaluation of the effectiveness of the Plant Emergency Preparedness Program within thirty (30) days of the termination of the emergency. The evaluation report will be provided to the Plant General Manager.

3. The Senior Specialist - Emergency Preparedness will maintain copies of the above reports for five (5) years.

10.0 DIAGRAMS ATTACHMENTS None Applicable PEP-401 Rev. 0 Page 8 of 8

APR011 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POMER PLANT PLANT OPERATING MANUAL VOL%K 2 PART 5 PROCEDURE TYPE: PLQlT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-403 TITLE: PERFORMANCE OF TRAINING REVISION 0 APPROVED:

Signacux e Dat:

TITLE:

PEP-403 Rev. 0 Page 1 of 13

~ ~

APRO12 TABLE OF CONTENTS

~Pa e Table of Contents List of Effective Pages 1.0 PURPOSE

2.0 REFERENCES

4 2.1 .Emergency Plan References 2.2 Referenced Plant Emergency Procedures 4 2.3 Corporate Emergency Plan and Implementation Procedures References 4 2.4 Other References 4.

3.0 RESPONSIBILITIES 5 3.1 Plant General Manager 5 3.2 Assistant to the Plant General Manager 5 3.3 Director-Training 5 3.4 Senior Specialist-Emergency Preparedness 5 3.5 Other Plant Personnel 6 3.6 Corporate Personnel 6 4.0 DEFINITIONS 6 5.0 GENERAL 7 5.1 Training Requirements 7 5.2 Training Objectives 7 5.3 Training Functions 7 5.4 Personnel To Be Trained 8 5.5 Frequency Of Training 8 5.6 Types Of Training Courses 9 5.7 Training Audits 9 6~0 INITIATING CONDITIONS 9 7.0 PRECAUTIONS AND LIMITATIONS 9 8.0 SPECIAL TOOLS AND EQUIPMENT 9 9.0 PROCEDURE STEPS 9 10.0 DIAGRkiS/ATTACHMENTS 10

1. Emergency Response Organisation Assignments and Training Courses 10 PEP-403 Rev. 0 Page 2 of 13

APR012 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 through 13 0 PEP-403 Rev. 0 Page 3 of 13

~ s' I

APR012 1.0 PURPOSE The purpose of this procedure is to implement Section 5.2, "Emergency Plan Training Program," of the SHNPP Emergency Plan.

This procedure describes the Emergency Plan Training Program for SHNPP including the related training responsibilities of employees of SHNPP.

This procedure also discusses the training of non-company personnel who may be called on to assist in an emergency at SHNPP.

Tzaining of corporate personnel who man the Corporate Emergency Operations Center (CEOC), of CP&L media personnel, and of the news media is addressed in the Corporate Emergency Plan Implementing Procedure CEPIP-19,"Emergency Plan Training Program."

Emergency response exercises and dzills which are used to provide hands on training and to perform an evaluation of the success of the training are discussed in PEP-406, "Performance of Exercises and Drills" and CEPIP-18, "Emergency Response Exercises and Drills" for SHNPP and corporate personnel, respectively.

2. 0 REFERENCES 2.1 EMERGENCY PLAN REFERENCES

1. Section 5.2, "Emergency Plan Training Program" 2; ',Section 5.1.2, "Emergency Plan and Plant Emergency Procedures Update and Changes tt 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-406, "Pezformance of Exercises and Drills"

2. PEP-404, "Public Education and Information" t

2.3 CORPORATE EMERGENCY PLAN AND IMPLEMENTATION PROCEDURES REFER" ~ 0 ENCES Lt 3

j't

1. Section 12.0, "Maintaining Emergency Preparedness" ~

t~

2. CEPIP<<18, "Emergency Response Exercises and Drills" !I t

3. CEPIP-19, "Emergency Plan Training Program" )j t

4. Harris Energy and Environmental Center, Radiological and Chemical Support Section Emergency 1'nstructions 2.4 OTHER REFERENCES

1. Title 10, Code of Federal Re lations, Part 50, Section 50.47, "Emergency Plans.

PEP-403 Rev. 0 Page 4 of 13

APR012

2.0 REFERENCES

2.4 OTHER REFERENCES (Cont'd)

2. Title 10, Code of Federal Re ulations, Part 50, Section 50.54(q), Conditions of License."

3. Title 10, Code of Federal Re lations, Part 50, Appendix E, "Emergency Planning and Preparedness for Production and Utilization Facilities."

NUREG-0654, FEMA-REP-l, Revision 1, "Criteria for Prepara-tion and Eval'hation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," November 1980.

5. SHNPP Technical Specifications.

6. SHNPP Security Personnel Training and Qualification Plan.

7. TI-105, "Fire Protection Training."

8. TI-302, "Emergency Plan Training."

3.0 RESPONSIBILITIES 3.1 PLANT GENERAL MANAGER The Plant General Manager ensures that. plant emergency plan training and retraining is performed in a complete and timely manner. He also provides for corrections of deficiencies noted as a result of tests, drills, exercises, and actual response during emergency situations .

3.2 ASSISTANT TO THE PLANT GENERAL MANAGER The Assistant to the Plant General Manager is the SHNPP Emergency Planning Coordinator. He is responsible for coordinating on-site and selected off-site radiological emergency response planning. He is also responsible for identifying off-site training needs of state and local emergency support personnel, and arranging for training to meet the identified needs.

3.3 DIRECTOR - TRAINING (HARRIS TRAINING UNIT)

The Director-Training is responsible for the conduct of the emergency plan training program of plant personnel and for off-site support personnel who must assist the plant in an emergency.

3.4 SENIOR SPECIALIST " EMERGENCY PREPAREDNESS The Senior Specialist - Emergency Preparedness assists the Director-Training in the conduct of the emergency plan training program by:

PEP-403 Rev. 0 Page 5 of 13

APR012 3.0 RESPONSIBILITIES 3.4 SENIOR SPECIALISTS-EMERGENCY PREPAREDNESS (Cont'd)

1. Preparing and updating selected lists of personnel to be I trained. 4 4

2. Determining and/or reviewing training needs, reviewing lesson plans, study guides, tests and training schedules to assure that they meet emergency planning commitments.

3. Evaluating emergency plan training, drills, and exercises.

4. Performing follow-up on action items resulting from

,~

exercises and other training functions.

4 4

I II 3.5 OTHER PLANT PERSONNEL The following specialists, supervisors and managers assist the Director-Training in the conduct of the emergency training program by providing input in areas related to their normal and/or emergency functions: 4 4

Senior Specialist-Fire Protection Senior Specialist-Security Managez - E&RC Manager - Technical Support Manager - Maintenance Manager - Operations

3. 6 CORPORATE PERSONNEL pff ~ Corporate personnel provide assistance in emergency plan

~ ~

training as discussed below:

Directoz Emergency Preparedness, OT & TSD

- Training of offsite officials

- Training of hospital and medical personnel

- Training of offsite first aid and rescue personnel

" Training of Corporate Emezgency Support personnel 4 4

Vice President - Corporate Communications

- Training of media personnel

- Training of CP&L media personnel Corporate Quality Assurance

- Audit training program 4~

440 DEFINITIONS

1. Annual - once every 366 days 4 41

2. Badged - badged by security for unescorted access to the Protected Area 4

PEP-403 Rev. 0 Page 6 of 13

APR012

5. 0 GENERAL 5.1 TRAINING REQUIREMENTS The training requirements for emergency plan training are specified in references 2.4.1 through 2.4.5. The training requirements for .

specific functions that may also be emergency related (i.e.,

~ ~

security and fire protection) are discussed in references 2.4.6 through 2.4.8 ~

5. 2 TRAINING OB JECTIVES The primary objectives of the training program are to:

~ Familiarize appropriate individuals with the Emergency Plan and the procedures that implement the Plan.

~ Instruct individuals and their alternates in their duties and responsibilities.

~ Periodically present significant changes in the scope or contents of the Plan or procedures which implement the Plan.

~ Provide annual refresher training to ensure that personnel are familiar with their duties and responsibilities

assigned by the Plan and procedures which implement the Plan.

5. 3 TRAINING FUNCTIONS The Emergency Plan Training Program provides for the performance of the following training functions:

'-,1 l. Identification of training needs (From Section 5.2 of the Emergency Plan).

2. Development of course content/lesson plans and study guides.

3. Scheduling training.

4. Conducting training and retraining.

5. Testing of students and evaluation of training.

6. Documentation of training activities.

7. Preparation and conduct of training drills performed as a part of the training courses.

8. Modification of lesson plans, study guides, and quizzes as a result of student performance on training course tests, drills, and/or exercises.

PEP-403 Rev. 0 Page 7 of 13

APR012 5.0 GENERAL 5.3 TRAINING FUNCTIONS (Cont'd)

9. Maintenance of current (updated) lists of personnel who require emergency response training.

5.4 PERSONNEL TO BE TRAINED All personnel who are allowed unescorted access to the Protected Area receive minimal training as part of the

'General Employee Training (GET) on evacuation alarms and personnel accountability measures used at SHNPP in the event of an evacuation.

2. Personnel who have emergency assignments are trained for their specific job functions in accordance with the re-quirements identified in Section 5.2 of the Emergency Plan. Specific courses are developed around the needs of the identified job functions. This training is discussed in references 2.4.6 through 2.4.8. Personnel, by title, who fill the various emergency positions are shown in Attachment 1.

3. Personnel who man the Emergency Operations Facility, Corporate Emergency Operations Facility, Media Center and provide environmental sampling are provided training as discussed in reference 2.3.3.

4, Loca) off-site support personnel are trained as discussed in reference 2.4.8.

5.5 FREQUENCY OF TRAINING Initial training relating to evacuation is provided for all personnel prior to the first full scale exercise.

Initial training for personnel with emergency assignments is provided to personnel who participate as players in the first full exercise. Initial training for all personnel with emergency ass3.gnments is provided prior to receipt of the Operating License.

2. New employees receive General Employee Training prior to being given unescorted access to the Protected Area and specialized training prior to their becoming part, of the emergency organization.

3. Non-badged site personnel receive training prior to receipt of the Operating License.

4. Retraining of all personnel is conducted annually.

5. Training drills are conducted as needed or in conjunction with training courses. The frequency of test drills and exercises is discussed in reference 2.2.1.

PEP-403 Rev. 0 Page 8 of 13

APR012

5. 0 GENERAL 5.6 TYPES OF TRAINING COURSES To provide the required emergency plan training the general and specialized courses listed in Attachment 1 are conducted under the direction of the SHNPP Training Unit.

'The details of these courses are described in Training Instruction TI-302, "Emergency Plan Training."

2. Emergency plan training for corporate functions are performed under the direction of the Manager Nuclear Training, Director of Emergency Preparedness, and Corpo-rate Communications Department. These courses include:

Media Personnel CP&L Media Pexsonnel Corporate Emexgency Support Pexsonnel Public Officials More information on corporate level training is provided in CEPIP-19.

I

3. CP&L corporate public information staff, in conjunction li with state and local government staffs, prepares programs to inform the news media and the public. These programs are conducted on an annual basis.

5. 7 TRAINING AUDITS An audit of the SHNPP Emergency Plan Training Program is conducted at least annually by the Emergency Planning Specialist, . Corrective actions deemed necessary from the audit(s) will be implemented in accordance with Section 5.1.2 of the SHNPP Emergency Plan.

6.0 INITIATING CONDITIONS None Applicable 7.0 PRECAUTIONS AND LIMITATIONS None Applicable 8.0 SPECIAL TOOLS AND EQUIPMENT None Applicable 9.0 PROCEDURE STEPS None Applicable PEP-403 Rev. 0 Page 9 of 13

APR012 10.0 DIAGRQiS/ATTACHHENTS

1. Emergency Response Organization Assignments and Training Courses PEP-403 Rev. 0 Page 10 of 13

hPRD12 ATTACHMENT 1 Emergency Response Organization Assignments and Training Courses Position Trainin Course Assi ed Personnel

1. Site Emergency Site Emergency Plant General Manager Coordinator - TSC Coordinator Manager<<Plant Operations Manager-Operations Manager-Maintenance

2. Site Emergency Coordi- Senior Reactor Senior Control Operators nator " Control Room Operators Emergency Shi.ft Foreman, Operations Leader Procedures Training Shift Technical Advisors

3. Plant Operations Director TSC Directors and Manager - Technical Support Emergency'epair Director Staff Manager - EGRC Logistics Support Director Assistant to the Plant Radiological Control Director General Manager Representative to SERT Director-Regulatory Evacuation Assembly Area Compliance Leaders, Operational Support Operating Supervisor Center Leader, Emergency Maintenance Supervisors Security Team Leader, Maintenance Project Emergency Communicators Specialists Designated Maintenance Engineers Administrative Supervisor Office Services Superv.

Material Control Superv.

Stores Foreman ESRC Supervisors and Project, Specialists Designated Communications Technicians Director"Planning S Sched.

Regulatory Compliance Specialists Planning & Sched. Engineers &

Specialists Emergency Preparedness Spec.

Designated Security Personnel

4. Emergency Communicator Emergency Communicator Auxiliary Operators Phone Talkers and Staff Director-Reg. Compliance Status Board Plotters Reg. Compl. Specialists ERFIS Console Operators Reg. Compl. Technicians Log Keepers Designated Clerks Designated Secretaries Designated Eng. Technicians Designated Draftsmen PEP-403 Rev. 0 Page 11 of 33.

ATTACR1ENT 1 (CONT'D)

Emergency Response Organization Assignments and Training Courses Position Trainin Course Assi ned Personnel

5. Radiological Emergency Teams

a. Dose Projection Dose Projection Proj. Spec. <<RC RC Specialists ALARA Specialists

b. Environmental Environmental Supervisor - E&C ~ ~

Monitoring Monitoring E&C Foreman E&C Technicians Ci Personnel Protection & Personnel Protection & Supervisor - RC Decontamination Team Decontamination Team RC Foreman RC Technicians

d. Plant Monitoring Plant Monitoring Proj. Spec. - E&C Specialist Chemistry Specialist ALARA Designated RC Technicians Designated Chemistry Technicians

6. Damage Control Team Damage Control Team Maintenance Supervisors Maintenance Specialists Designated Operators Designated RC Technicians Designated Maintenance Personnel

1. Fire Brigade Fire Brigade Training Designated Personnel (Per TI-105)

8. Emergency Security Team Security Force Designated Security Training Personnel (Per SHNPP Security Force T&Q Plan)

9. First Aid Team First Aid Multi-Media Designated Personnel

10. Accident Assessment Accident Assessment Shift Technical Advisors Team Team Training Principal Eng.-Operations Project Engineer"NSSS Project Engineer-Perf.

Designated Engineering Personnel PEP-403 Rev. 0 Page 12 of 13 1

APRO12 ATTACHMENT 1 (CONT'D)

Emergency Response Organization Assignments and Training Courses

]

Position Trainin Course Assi ed Personnel

11. Emergency Response EOF Personnel VP-Harris Nuclear Project Manager &, Staff Designated HNP Personnel Designated On-Site Nuclear Safety Personnel Designated HTU personnel Designated HENDEC personnel

12. Badged Site Personnel GET Level I All Badged Site Personnel

13. Non-Badged Site Non-Badged Site All non-badged personnel Personnel Personnel assigned to the Pxoject Site.

14. Off-site Organizations Per CEPIP-19 Off-site Emergency Response Organization Personnel (Per CEPIP-19)

15. All On-site Emergency Respiratory All assigned personnel Response Personnel Training in positions 1 through 10 above.

~ g PEP&03 Rev. 0 Page 13 of 13

CAROLINA-POWER 6r, LIGHT.",COMPANY,.'HEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE: PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-405 TITLE: PREPARATION OF ACTIVITY LOGS REVISION 0 APPROVED:

Signature TITLE:

PEP-405 Rev. 0 Page 1 of 7

APR011 TABLE OF CONTENTS

~Pa e Table of Contents 2 List of Effective Pages 3 1 0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 4 2.2 Referenced Plant .Emergency Procedures 3.0 RESPONSIBILITIES 4 3.1 Log Keepers 3.2 Directors, Managers,and Leaders 4 4.0 DEFINITIONS 4 5.0 GENERAL 4 6.'0 INITIATING CONDlTIONS 4 7.0 PRECAUTIONS AND LIMITATIONS 4 8.0 SPECIAL 'TOOLS AND EQUIPMENT 5 9.0 PROCEDURE STEPS 5 10.0 DIAGRAMS/ATTACHMENTS 6

l. "Emergency Log" 7 PEP-405'ev. 0 Page 2 of 7

APR011 L'IST'OF. EFFECTIVE;. PAGES

~Pa e Revision 1 thru 7 0 PEP-405 Rev. 0 Page 3 of 7

APR011 1.0 PURPOSE The purpose of this procedure is to 'implement Section 2.4, "Assi'gn-ment of Responsibilities" of the SHNPP Emergency Plan.

t This procedure provides guidance on prepar'ing activity logs during emergencies.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 2.4, "Assignment of Responsibilities" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-401, "Record Keeping, and Documentation" 3.0 RESPONSIBILITIES

1. LOG KEEPERS

~ J Log Keepers for the Site Emergency will prepare Coordinator-Technical'upport Center and Emergency Response Manager logs during emergencies.

2. DIRECTORS, 'MANAGERS, AND LEADERS

.-:Directors, Managers and Team Leaders who do not have Log Keepers assigned to them should maintain logs of their major activities.

Directors and Managers will transmit their logs and the logs of personnel who report to them to'.the Senior Spe-cialist - Emergency Preparedness immediately following the termination of the exercise or emergency.

4.0 DEFINITIONS None Applicable 5.0 GENERAL

~

None Applicable 6.0 INITIATING CONDITIONS

1. Upon initiation of any emergency class.

7.0 PRECAUTIONS 'AND LIMITATIONS None Applicable PEP-405 Rev. 0 Page 4 of-7

APR011 8;0, SPECIAL, TOOLS.AND E UIPMENT None Applicable 9.0 PROCEDURE STEPS

1. Initiate Attachment 1, "Emergency Log" as follows:

ORGANIZATION: Enter the name of the emergency position or organization for which the log is being kept (i.e., Site Emergency Coordinator, Accident Assessment Team, Emergency Communicator - Technical Support Center, etc.).

LOCATION: Enter the location of the individual or organization (i.e., Control Room, Technical Support Center, Operational Support Center, Emergency Opera-tions Facility, etc.).

PAGE NUMBER: Enter "1" on the first page and sequen-tial. numbers (2,3,4, etc.) on the following pages as they are used.

PERIOD COVERED: FROM: Enter the time the log is initiated using. the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock system (i.e., 1pm is 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />) and the date (i.e., 3, Aug 84).

2. Enter chronologically those. events that are pertinent to the particular individual or organizations:

ITEM No.:. Enter 1 for the first jncident, message, action, etc. and sequential numbers, (2,3,4,etc.) for the following ones.

TIME':

IN: Record the time (using the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock) that a message or information was received OUT: Record the time that a message, information or order was transmitted.

INCIDENTS MESSAGES ORDERS ETC.: Briefly record the incident, message or order received or transmit-ted. Indicate the time of the incident, etc. For messages, reference message number.

~ ACTION TAKEN: Record'ctions taken, such as:

notified Emergency Response Manager, requested Accident Assessment Team to evaluate, ordered Opera-tional Support Center to dispatch First Aid Team, etc.

3. Upon relief from the position or termination of the emergency complete the log as follows:

NO. OF PAGES: Enter the total number of pages on each log page.

PERIOD COVERED: TO: Enter the time and date the log is closed out.

PEP-405 Rev. 0 Page 5 of 7

APRuil 9.0 PROCEDURE STEPS

'4 'AME AND TITLE: Enter your'ame and emergency title.

If you are preparing the log for someone else such as the Site'Emergency Coordinator or Emergency Response Manager enter his name and emergency title below yours.

~ SIGNATURE: Sign your name (across from your name and title). If prepared for another person, have the other person sign next to his name and emergency title.

4. The person'elieving the position will initiate a new log as per step 1 and maintain the new logs and any previously prepared logs to allow for continuity .of the position.

'5. Upon termination of the 'emergency -provide all completed logs to your director or manager who in turn, will supply them to the Senior Specialist - Emergency Preparedness (as per PEP-401).

10. 0 DIAGRAMS ATI'ACHMENTS

1. "Emergency Log" PEP-405 Rev. 0 Page 6 of 7

A'lTACHMENT ZÃERGE'KY IOQ WAOC IIOo.'I'-et ~AOC+

EMERGENCY'OG LOCA TI ON pCAIOO CQVClICO alIOu TO

~ t+glI OA N UII OA IC ItCQ'C4 our lllNOCNTS~ NC55AOCSy OIIOCRSg ETC'CV IOle TAIICN HAIK AIIO TITLE SIOIIATUOC PEP-405 Rev. 0 pygmy 7 QZ 7

APR011 CAROLINA POWER ga LIGHT'OMPANY'HEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE:, PLANT EMERGENCY PROCEDURE (PEP)

NUMBER: PEP-406 TITLE: PERFORMANCE OF EXERCISES AND DRILLS REVISION 0 APPROVED:

Signature Da e TITLE:

PEP-406 Rev. 0 Page 1 of 15

APR011 TABLE OF CONTENTS

~Pa e Tabl e of Contents 2 List of Effective Pages 3 1.0 PURPOSE 4

2.0 REFERENCES

4 2:1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4 2.3 Corporate Emergency Plan and Implementation Procedures References 4 2.4 Other References 4 3.0 RESPONSIBILITIES 5 3.1 Director - Emergency Preparedness 5 3.2 Manager- Nuclear Training, Operations Training and Technical Services Department 5 3.3 Manager-Radiological and Chemical Support Section,, Operations Training and Technical Services Department 5 3.4 Plant General Manager 5 3.5 Assistant to the Plant General Manager 6 3.6 Senior Specialist - Emergency Preparedness 6 3.7 Director - Harris Training Unit 6 3.8 Manager-Environmental and Radiation Control 6 3.9 Senior Fire Protection Specialist 6 3.10 Senior Specialist- Security 7 4.0 DEFINITIONS. 7 5.0 GENERAL 8 6.0 INITIATING CONDITIONS 14 7.0 PRECAUTIONS AND LIMITATIONS 14 8.0 SPECIAL TOOLS AND EQUIPMENT 14 9.0 PROCEDURE STEPS 14 9.1 Plant-Vide Test Drills 14 9.2 Exercises '15 10.0 DIAGRAMS/ATTACHMENTS 15 PEP-406 Rev. 0 Page 2 of 15

APR011 LIST'F EFFECTIVE; PAGES.,

~Pa e Revision 1 through 15 0 PEP-406 Rev. 0 Page 3 of 15

APR011 1.0 PURPOSE The purpose of this procedure is to implement Section 5.3, "Drills and Exercises," of the SHNPP Emergency Plan.

This procedure describes the types of drills and exercises and the policy and procedures related to conducting the drills.

This procedure is mainly concerned with test drills. Practical drills, which are used as part of the emergency preparedness training process, may be incorporated in or attached to the Harris Training Unit lesson plans. Plant wide practice exercises, and annual exercises are covered by CEPIP-18.

2.0 REFERENCES

2.1 EMERGENCY PLAN REFERENCES

1. Section 5.3, "Drills and Exercises" 2.2 REFERENCED PLANT EMERGENCY PROCEDURES

1. PEP-302, " Communications Activities'.

PEP-403, "Performance of Training"

3. PEP-404, "Public 'Education and Information" 2.3 CORPORATE EMERGENCY PLAN'ND IMPLEMENTATION 'PROCEDURES REFER-ENCES

1. Section 12.0; "Maintaining Emergency Preparedness"

2. CEPIP-18, "Emergency Response Exercises and Drills"

3. CEPIP-19, "Emergency Plan Training Program"

4. Harris Energy and Environmental Center, Radiological and Chemical Support Section Emergency Instructions 2.4 OTHER REFERENCES

1. Title 10, Code of Federal Re lations, Part, 50~ Section 50.47, "Emergency Plans.

2. Title 10, Code of Federal Re lations, Part 50, Section 50.54(q), Conditions of License.

3. Title 10, Cod'e of Federal Re lations, Part 50, Appendix E, "Emergency Planning and Preparedness for Production and Utilization Facilities."

4. NUREG-0654, FEMA-REP-1, Revision 1, "Criteria for Prepara-tion and Evaluation of Radiological Emergency Response 1

PEP-406 Rev. 0  :-Page 4 of 15

APR011 2.0~ REFERENCES I'.4 OTHER REFERENCES (Cont'd)

Plans and Preparedness in Support of Nuclear Power Plants," November 1980.

5. SHNPP Technical Specifications.

6. SHNPP Security Personnel Training and Qualification Plan.

7. TI-105, "Fire Protection Training."

8. TI-302, "Emergency Plan Training."

3.0 RESPONSIBILITIES 3.1 DIRECTOR' EMERGENCY PREPAREDNESS, Operations Training and, Technical Services Department,

1. 'oordinates the scheduling and conduct of annual exercises including preparation of exercise plans in coordination with the Nuclear Project Managers, Plant General Managers, Manager Nuclear Training, Federal Emergency Management Agency, state and local officials, and others as appropriate.

2. Coordinates the preparation of scenario's for the annual exercises.

3.2 MANAGER NUCLEAR TRAINING, OPERATIONS TRAINING AND TECHNICAL .

SERVICES DEPARTMENT

1. Assists in the preparation of scenarios for annual exercises by providing appropriate personnel with as much reactor operation expertise as needed to the Director - Emergency Preparedness.

3.3 MANAGER-RADIOLOGICAL AND CHEMICAL SUPPORT SECTION, OPERATIONS TRAINING AND TECHNICAL SERVICES DEPARTMENT

1. Plans, schedules, and conducts both practical and test drills in his area of responsibility as indicated in TI-302 Attachment 5.1.

3.4 PLANT GENERAL MANAGER

1. . Provides for corxection of deficiencies noted as a result of test .drills, exercises, and actual responses during emergency situations.

l PEP-406 Rev. 0 Page 5 of 15

APR011 3.0 RESPONSIBILITIES 3.5 ASSISTANT TO THE PLANT GENERAL MANAGER

1. Plans, schedules, -and conducts in coordination with the Director - Emergency Preparedness, the annual exercise and provides for the correction of discrepancies in perfor-mance, procedures, facilities, or equipment.

3.6 SENIOR SPECIALIST - EMERGENCY PREPAREDNESS The Senior Specialist- Emergency Preparedness reports to the Assis-tant to the Plant General Manager and may be delegated his Emergency Preparedness duties. In addition, 'the Senior Specialist;

1. Prepares, schedules, and conducts plant-wide test drills.

2. Ensures that all affected external organizations receive advance notification of test drills and practice exercises as appropriate.

3. Performs follow up on action items resulting from exer-cises, test drills, and other training functions, as described in Chapter 6 of the SHNPP Emergency Plan.

3. Maintains documentation on test drills.

3.7 DIRECTOR-KRIS .TRAlNING UNIT

1. Prepares, schedules, and conducts practical drills in his area of responsibility as indicated in TI-302 Attachment

5. 1.

2. Maintains documentation of practical drills.

3.8 MANAGER-ENVIRONMENTALAND RADIATION CONTROL

1. Prepares, schedules, and conducts practical drills in his area of responsibility as indicated in TI>>302 Attachment

5. 1.

2. Provides evaluators, and/or controllers for .test drills, practice exercises, and critiques.

3.9 SENIOR FIRE PROTECTION SPECIALIST

1. Prepares, schedules, and conducts practical drills in his area of responsibility as indicated in TI-302 Attachment 5.1.

PEP-406 Rev. 0 .Page 6 of,15

APR011 3'10 SENIOR. SPECIALIST-SECURITY Prepares, schedules, and conducts practical drills in his area of responsibility as indicated in TI-302 Attachment 5.1.

4 .0 DEFINITIONS

1. Monthly - means at least once per 31 days

2. Quarterly - means at least once per 92 days

3. Semiannually - means at least once per" 184 days

4. Annually - means at least once per 366 days

5. Scenario - A SCENARIO is a description of a hypothetical situation from start to finish which serves as the theme or basis upon which the action or play of the exercise or drill unfolds. The scenario may include exercise mess-ages/drill cards and/or System Parameter Data and Status (SPDS) sheets.

6. Practical Drills Provide practical application and hands-on experience.

Students work through assigned problems. These drills are useful for training. radiological teams,. emergency commu-nicators, the first aid team, and other personnel who work primarily with equipment. Practical drills are part of training.

7. Test Drills Are of limited scope and can include tabletop experience.

These drills are geared primarily toward developing supervisory skills and emphasize training in special areas of concern. For example, these drills are useful for the Technical Support Center, Emergency Operations Facility, communications, and radiological teams.

8. Practice Exercises Integrate the components of the Emergency Response Organi-zation using realistic 'scenarios. Practice exercises are used to prepare for the annual exercise.

9. Annual Exercises Demonstrate the overall effectiveness of the emergency preparedness program as required by regulations.

PEP-406 Rev. 0 Page 7 of 15

~4

APR011 4.0 DEFINITIONS (Cont'd)

10. Table Top Exercise - a TABLE TOP EXERCISE is a'ractical or test drill at which selected participants will work their way through a scenario by role playing and/or discussion azound a table or in a conference, or at predetermined exercise stations (usually the latter).

Pzewritten messages and System Parameter Data and Status sheets based on the scenario are used to initiate player response and keep the exercise action moving according to established objectives. A table top exercise may be used as a rehearsal for an annual exercise.

5.0 GENERAL 5.1 EXERCISE/DRILL REQUIREMENTS The purpose of exercises and. test drills is to periodically evaluate major portions of emergency response capabilities and other elements of plant radiological emergency response plans, corporate emergency plans, and state and local emezgency plans in accordance with the provisions of Nuclear Regulatory Commission Regulation 10CFR50.47(b)(14). Procedures for the conduct of emergency response exercises are contained in Corporate Emergency Plan Implementing Procedure CEPIP-18.

5. 2 OBJECTIVES OF EXERCISES/DRILLS

1. Exercise at least annually the emergency plan and imple<<

menting procedures.

2. Test the adequacy of timing and content of implementing procedures and methods.

3. Test emergency response facilities, equipment, and commu-nications networks.

4. Test the public alert'ing and notification system. (Not necessary during the annual exercise.)

'. Ensure that emergency with assignments,and organization personnel are "familiar proficient in performing their duties.

6. Demonstrate proficiency in recognizing, assessing, and .

classifying the emergency condition, and in employing corrective measures. t

7. Demonstrate .adequacy oi protective measures considered and used to protect people, both plant and public.

8. Meet SHNPP emergency plan training objectives.

PEP-406 Rev. 0. Page 8 of 15

APRO11 5'.0. GENERAL

'5.2 OBJECTIVES OF EXERCISES/DRILLS (Cont'd)

9. Demonstrate adequacy of interfaces between implementing procedures and other operating procedures (fire, security, etc.).

5.3 TYPES OF EXERCISES SHNPP in cooperation with Corporate Emergency Support Personnel shall conduct an annual exezcise as required by 10CFR50, App. E.IV.F.

2. Full-scale or small-scale practice exercises will. be conducted as required in accozdance with a plan prepared.

for each exercise. These exercises will have the charac-teristics described in Section 3.1 through 3.4 of CEPIP-18.

5.4 TYPES OF DRILLS-5.4.1 General - Test drills in additi'on to the annual exercise will be conducted at the frequencies indicated for various types of test drills described below. Emphasis will be on the effectiveness of procedures and actual use of emergency equipment.

5.4.2. Communication Test Drills

1. Communication from"the plant to the state and local government warning points and within the plume exposure pathway Emergency Planning Zone shall be tested MONTHLY.

2. Communications with federal emergency response organizations and states within the ingestion pathway shall be tested QUAR-TERLY.

3. Communications between SHNPP, state, and local emergency operations centers, and environmental monitoring teams shall be tested ANNUALLY.

4. Communication between the Contxol Room, the Technical Support Center, and the Emergency Opezations Facility shall be tested ANNUALLY.

5. Communications from the Control Room, Technical Support Center, and the Emergency Operations Facility to the NRC headquarters Operations Center and Region II Incident Response Center shall be tested MONTHLY.

6. Communication test drills shall be conducted in accordance with the plant technical specifications and fire protection manual.

7. Communication test drills shall also include the aspect of understanding the content of messages.

PEP-406 Rev. 0 Page 9 of 15

APR011 5.0 GENERAL 5.4 TYPES OF DRILLS (Cont'd) 5.4.3 Fire Test Drills - Fire test drills shall be conducted in accordance with the Plant Technical Specifications and Fire Pro-tection Manual.

5.4.4 Medical Emer enc Test Drills - A medical emergency test drill involving a .simulated contaminated individual with provision for participation by the local support services agencies (i.e.,

ambulance, and off-site medical treatment facility) shall be conducted ANNUALLY. The off-site portions of the medical drill may be performed as part. of the required annual exercise.

5.4.5 Radiolo ical Monitorin Test Drills - Plant environs,and radiological monitoring test drills (on-site and off-site) shall be conducted ANNUALLY. These drills shall include collection and analysis of all sample media, and provisions 'for communications and record keeping.

5.4 ' Health Ph sics Radiation Protection Test Drills

1. Health Physics test drills shall be conducted SEMIANNUALLY which involve response to, and analysis of, simulated elevated airborne and liquid samples .and direct .radiation measuxements in the environment.

2. Analysis of in-plant liquid samples with actual elevated radiation levels including use of the post-accident sampling system shall be included in Health Physics test dxills ANNUALLY.

5.5 EXERCISE/DRILL FACILITIES One or more of the following emergency facilities may be activated when required by the test dxill or exercise scenario .and operated in accordance with corporate and plant emexgency plans and procedures:

1. Control Room

2. Technical Support Center

3. Operational Support Centex

4. Emergency Operations Facility

5. Plant Media Center

6. Corporate Emergency Operations Center

7. . Corporate Headquarters Media Center State and local Emergency Operating Centers opexate according to state and local government, emergency preparedness plans. They may be activated by the state ox local government when they participate in exercises.

PEP-406 Rev. 0 'age 10 of 15

APR011 5;".0, GENERAL 5.6 COMMAND AND CONTROL 5.6.1 For Exercises The command and control organization for annual .exercises will consist of individuals with duties as discussed in Section 5.0 of CEPIP-18. For practice exercises the organization may be modified as appropriate.

5.6.2 For Drills The command and control organization for drills may be one (or more) instructors or Controll'er - Evaluators.who are, running the drill as-a hands on instructional period and/or as a test of personnel, equipment, and procedures.

5.7 EXERCISE/DRILL PLANS Exercises and test drills not addressed elsewhere (e.g., Fire Drills) shall have a plan for the exercise or drill. Exercise plans should be prepared in accordance with CEPIP-18.

If repeated test drills of the same scope are to be conducted, a standardized drill plan may be used with variations in drill scenar-ios ~

Test drill plans should contain the following:

1. The- basic objective(s) of each drill.

2. The date(s), time period, place(s) and participants. (This can be covered by a separate memorandum when a standard drill plan is used.)

3. Location(s) where test drills will take place including act-ivation of any emergency facilities.

4. Events to be simulated.

5. Whether any off-site individual or organization will be cont-acted as part of the drill.

6. A narrative summary describing the conduct of the drill.

7. Time schedule of initiating events, real and simulated. (This can be part of the appendix.)

8. Procedures that are applicable to the drill.

Criteria to be used for evaluation.

PEP-406 Rev. 0 Page 11 of 15

APR011 5.0 GENERAL 5.7 EXERCISE/DRILL PLANS (Cont'd)

10. Individual(s) who will evaluate the drill, other than the participants who will perform a self critique. (This can be addressed in a separate memo.)

11. Exercise messages, drill cards, and/or System Parameter Data and Status (SPDS) forms to be used should be attached as an appendix. (More than one set can be prepared for a particular type of drill when the drill is used to train the same group repeatedly.)

5.8 SCENARIOS Scenarios are prepared for exercises and for test drills in most cases. The scenarios for test drills are usually relatively simple.

The scenarios are prepared hy a Scenario Team selected by the Plant General Manager. The team normally consists of an individual from each o'f the following departments:

1. Emergency Preparedness

2. Operations

3. 'Environmental and Radiation Control

4. Technical Support 5.9 EVALUATION AND CRITIQUES 5.9.1 The facilities and the organizations listed below may be evaluated in addition to the Plant Emergency Plan and Procedures.

1. Control Room

2. Technical Support Center 3 ~ Operational Support Center

4. Emergency Operations Facility

5. Plant Media Center

6. Corporate Emergency Operations Center

7. Corporate Headquarters Media Center 5.9.2 The following activities,may be evaluated:

1. Accident recognition, classification, and assessment

2. Assessment and monitoring of on-site and off-site radiological consequences

3. Alerting, notification, and mobilization activities

4. In-plant corrective actions

5. Activation and use of emergency facilities and equipment

6. Public warning and notification

7. Use of communications equipment and procedures

8. Preparation of reports, messages, and records

9. Protective actions - Evacuation, Decontamination, etc.

10. Public information and public relations

11. First Aid measures, rescue, handling contaminated accident cases PEP-406 Rev. 0 Page 12 of 15

APR011 5;0'"

GENERAL'.9 EVALUATION AND CRITIQUES 5.9.2 The following activities may be evaluated: (Cont'd)

12. Security control, site access, personnel accountability

13. Fire fighting 14 Recovery and ze-entry 5.9.3 Each test drill shall provide for critiques by controllezs and pazticipants at the conclusion of the drill. The time and place of the critique meeting shall be speci, fied in the plan for each drill.

5.9.4 Any weskness in the emergency plan, facilities, training, etc., that are identified through the critique process shall be documented and corrected by the organizations and individuals who have responsibility. for the. areas identified. A copy of this documentation will be sent to the Senior Specialist - Emergency Preparedness.

5. 10 EVALUATION STANDARDS 5.10.1 The appropriate parts of the Corporate and Plant Emergency Plans and their Implementing Procedures that apply to the function, activity, facilities, and personnel will be used as standards for evaluation.

5.10.2 Guidance given in pze-drill meetings, notations in the "Actions Expected" portion of the Exercise Message/Drill Cards, and the drill ob)ectives as enumerated in. the drill plan will be used also as evaluation standards.

5.10.3 Evaluation standards for exercises will be those discussed in CEPEP-18.

5.11 TEST DRILL GRADING The dzill critique report will contain a grading or rating for each drill area 'evaluated as follows:

5.11.1 Excellent: Personnel and equipment always. functioned without error the first time, every time. There were no problems encountered and all personnel and equipment functioned as specified by the Exercise Plan, and the Corporate and Plant Emergency Plans and their implementing procedures.

according to expectations, with some i" '

minor exceptions. Any errors noted were not severe, would not reduce the effectiveness of the plant emergency response capability, and could be corrected without undue labor and/or expense.

/

performed below expectations and/or there were several significant PEP-406 Rev. 0 Page 13 of 15

APR011

5. 0 GENERAL P

5.11 TEST DRILL GRADING (Cont'd) deficiencies noted. The ability of pers'onne'1 and/or equipment to cage,out:assi~ed; mission was diminished. Performance of facility was not in accordance with the Corporate or'"Plant Emergency Plans and their implementing procedures.

Exercise critique reports will contain a grade or rating as dis-cussed in CEPIP-18.

6.0 INITIATING CONDITIONS None Applicable 7.0 PRECAUTIONS AND LIMITATIONS

1. Verify that any emergency notification messages to off-

-site authorities used during drills or exercises begin and end with "This is an exercise message" and that scenario message sheets contain the same statement.

8.0 SPECIAL TOOLS AND E UIPMENT None Applicable 9.0 PROCEDURE STEPS

9. 1 PLANT"WIDE TEST DRILLS

1. Prepare a scenario for a test drill and have it approved by the scenario committee or request the scenario commit-tee to prepare a scenario.

2. Prepare the appropriate Exercise Message/Drill Cards (Attachment to CEPIP-18) and System Parameter Data and Status (SPDS) sheets PEP-302) ~

if appropriate (See Attachment to

3. Schedule the test drills after coordinating with the unit supervisor and Senior Specialist- Emergency Preparedness.

4; The Senior Specialist - Emergency Preparedness obtains final approval for plant-wide drill schedules from the Plant Manager.

5. Notify drill participants of date, time, and place to assemble (usually well in advance unless this is an unannounced drill being used as a test).

6. Notify affected non-participants (Institute for Nuclear Power Operations, Distribution Engineering, contractors, etc.) of the drill'chedule.

PEP-406 Rev. 0 Page 14 of 15

APR011 9.0 PROCEDURE STEPS 9.1 PLANT-VIDE TEST DRILLS (Cont'd)

7. Conduct the drill.

8. Have the participants perform a self-critique.

Evaluate the drill orally V'.

for the participants and prepare a written critique (the form in CEPIP-18 can, be, used oE"

other appropriate form).

\

of the drill plan, scenario, and evaluation ".~

~ ~

10. Send a copy form to the Director - Harris Training Unit and to the Senior Specialist - Engineering Preparedness.

11. The Director - Harris Training Unit will update the training records in accordance with Training Procedures by indicating drill participation.

9.2 EXERCISES

1. Perform exercises as discussed in CEPIP-18.

10.0 DIAGRAMS ATTACHMENTS None Applicable PEP-406 Rev. 0 Page 15 of 15

fv V

,l 4

APR011 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLAN PLANT OPERATING AL VOLUME P 5 PROCEDURE TYPE: PLANT RGENCY PROCEDURE (PEP)

NUMBER: PE -331 TITLE: EMERGENCY PLAiXT MONITORING REVISION 3 APPR D:

Signature Date TITLE:

PQCE.WE.

0(,) 16 )985 OQCuVB~~

grvc~s Page 1 of 8

APR011 TABLE OF CONTENTS Section ~Pa e Table of Contents '2 List of Effective Pages 3 1 ~ 0 PURPOSE 4

2.0 REFERENCES

4 2.1 Emergency Plan References 4 2.2 Referenced Plant Emergency Procedures 4 2.3 Other References 4 3.0 RESPONSIBILITIES 5 3.1 Chemistry Coordinator 5 3.2 Radiological Control Coordinator 5 4.0 DEFINITIONS 5 5.0 GENERAL 5 6.0 INITIATING CONDITIONS 6 7.0 PRECAUTIONS AND LIMITATIONS 6 8.0 SPECIAL TOOLS AND EQUIPMENT 6 9.0 PROCEDURE STEPS 6 10.0 DIAGRAMSIATTACHMENTS 8 PEP-331 Rev. 3 Page 2 of 8

APR011 LIST OF EFFECTIVE PAGES

~Pa e Revision 1 through 8 PEP-331 Rev..3 Page 3 of 8

APR011

).0 PURPOSE The purpose of this procedure is to implement Section 4.4.2, "Plane Radiological Monitoring" of the SHNPP Emergency Plan, which is a regvlatory commitment. It also implements corrective action in response to NRC Emergency Preparedness Appraisal Insepction Report Nvmber 50-400/85-09. It specifies the methods to be used for condvcting radiological surveys at the plant site, inclvding outdoor surveys inside the Protected Area, and for sampling and analyzing plant systems dvring an emergency. It is not applicable for outdoor surveys ovtside of the Protected Area, which are performed in accordance with PEP-351, "Emergency Environmental Monitoring."

2.0 REFERENCES

2.1 Emer enc Plan References

l. Section 4.4.2, "Plant Radiological Monitoring" 2~ Section 2.4.6, "Radiological Control Director"

3. Section 2.4.6.5, "Chemistry Coordinator" 4~ Section 2.4.6.7, "Radiological Control Coordinator" 2.2 Referenced Plant Emer enc Procedures

1. PEP-207, "Chemistry Coordinator" 2; PEP-208, "Radiological Control Coordinator" 2.3 Other References

1. CRC-250, "Plant Vent Sampling"

2. CRC-820, "PASS Preoperational Test and System Calibration" 3~ CRC-821, "PASS RCS/RHR Pump Discharge Dilvte Liqvid Sampling During Accident Conditions"

4. CRC-822, "PASS RCS/RHR Pvmp Discharge Undilvted Liquid Sampling Dvring Accident Conditions" 5 ~ CRC-823, "PASS Containment Air Sampling"

6. CRC-824, "PASS RCS Stripped Gas Sampling and Analysis" 7l CRC-825, "PASS In-Line pH and Dissolved Oxygen 'Analyses of RCS/RHR Pvmp Discharge Sampling During Accident Conditions"

8. CRC-826, "PASS Sample Chloride Analysis"

9. CRC-827, "Post Accident Sample Boron Analysis by Fluoroborate Specific Ion Electrode"

10. CRC-828, "Isotopic Analyses for Core Damage Evaluation"

11. CRC-829, "PASS Sample Accountability, Storage, and Disposal"

12. ERC-106, "Confined Space Monitoring Program"

13. ERC-117, "Operation of the RM-23, RM-23P, and RM-23L"

14. HPP-005, "Scheduling Routine Activities"

15. HPP-060, "Performance of Radiation and Contamination Surveys

16. HPP-066, "Preparation and Analysis of Air Samples"

17. HPP-067, "Collection of Particulate/Iodine Air Samples" PEP-331 Rev. 3 Page 4 of 8

APROll 2.3 Other References (cont'd)

18. HPP-069, "Collection and Analysis of Noble Gas Samples"

19. HPP>>075, "Vehicle Survey"

20. HPP-503, "Operation of the Protechtor Portable Gas Alarm"

21. HPP-504, "Operation of the Gastechtor Portable Gas Alarm"

22. HPP-505, "Operation of the Draeger Multigas Detector"

23. RCP>>660, "Sample Preparation for Determination of Radioactivity"

24. RCP-701, "Operation of the Canberra Series 90 Gamma Spectrometry System"

25. Regulatory Guide 1.97, " Instrumentation for Light-Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and After an Accident"

26. Nuclear Regulatory Commission Inspection Report Number 50-400/85-009.

3.0 RESPONSIBILITIES 3.1 Chemistr Coordinator The Chemistry Coordinator is responsible for assigning members of the Chemistry Team to:

1. Operate the Post Accident Sampling System

2. ~

Obtain and analyze other plant samples

3. Operate the Radiation Monitoring System to collect grab samples from the plant vent stack.

3.2 Radiolo ical Control Coordinator The Radiological Control Coordinator is responsible for assigning members of the Radiological Control Team to:

1. Perform in-plant radiological surveys.

2~ Perform ield interrogations of the Radiation Monitoring System to evaluate the radiological consequences of the accident.

3~ Perform airborne hazardous chemical surveys and/or confined space monitoring.

4.0 DEFINITIONS None Applicable 5.0 GENERAL The Chemistry Team collects and analyzes chemistry samples to provide data to assist the Radiological Control Director, Plant Operations Director, and others in assessing core damage and PEP-331 Rev. 3 Page 5 of 8

APRO11 5.0 GENERAL (cont'd) possible release source terms. Where normal procedures referenced in this procedure specify actions to be performed by E&C Technicians, they shall be performed by the Chemistry Team. Where they specify actions to be performed by an E&C Foreman or E&C Supervisor, those actions shall be performed by the Chemistry Coordinator.

The Radiological Control Team performs radiation, contamination, and airborne activity and hazardous chemical surveys to determine the habitability conditions of areas for the protection of personnel who may need to enter these areas during the emergency. Where normal procedures referenced in this procedure specify actions to be performed by RC Technicians, they shall be performed by the Radiological Control Team. Where they specify actions to be perfox'med by an RC Foreman ox Supervisor, those actions shall be performed by the Radiological Control Coordinator.

6.0 INITIATING CONDITIONS

l. An emergency has been declared and in-plant radiological or airborne hazardous chemical surveys or plant samples are required.

7.0 PRECAUTIONS AND LIMITATIONS

1. Comply with personnel protection requirements established by the Radiological Control Coordinator

2. PASS samples should be taken and analyzed'in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or less from the time the decision is made to sample, except for chlox'ide which should be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />, as stated in NRC Regulatory Guide 1.97. Sampling during an emergency is not an automatic action, and shall be performed only after the Site Emergency Coordinator has decided that it is necessary.

8.0 SPECIAL TOOLS AND E UIPMENT

1. Post Accident Sampling System

2. Air Samplers 3~ Protechtor Portable Gas Alarm

4. Draeger Multigas Detector

5. RM-23P Portable Command and Readout Device for the Radia-tion Monitoring System

6. Gamma Spectxometer 9.0 PROCEDURE STEPS NOTE: These steps'ay be performed in any order.

1. The Radiological Control Team will perform and document radiation and contamination surveys in accordance with HPP-060.

PEP-331 Rev. 3 Page 6 of 8

APROll 9.0 PROCEDURE STEPS (cont'd)

2. The Radiological Contxol Team will collect and document air samples in accordance with HPP-067 and/or HPP-069 as appropriate except that the volume of sample collected for particulate and iodine samples vill be fifteen cubic feet unless specified otherwise by the Radiological Contxol Coordinator. They will analyze particulate and Iodine air samples in accordance with HPP-066, and deliver all iodine collection cartridges, regardless of the gross activity of the particulate sample, to the Chemistry Team for gamma isotopic analysis in accordance with RCP-660 and RCP-701.

3~ The Chemistry Team will prepare the Post Accident Sampling System for use in accordance with CRC-820.

4. The Radiological Control Team will perform surveys for airborne toxic/flammable gases or chemicals in accordance with HPP-503, "Operation of the Protechtor Portable Gas Alarm," HPP-504, "Operation of the Gastechtor Portable Gas Alarm," and/or HPP-505, "Operation of the Draeger Multigas Detector." Surveys shall be documented on Appendix A to ERC-106, "Confined Space Monitoring Program."

5 The Chemistry Team will collect containment air samples in if

~

accordance with CRC-823 or, activity levels permit, in accordance vith normal plant procedures,

6. The Chemistxy Team will collect Reactor Coolant or containment sump samples in accordance with CRC-821 for dilute samples and/or CRC-822 for undiluted samples, or if activity levels permit, in accordance with normal plant procedures.

7 ~ The Chemistxy Team will collect and analyze Reactor Coolant samples for dissolved gases in accordance with CRC-824, or if activity levels permit, in accordance with normal plant procedures.

8. The Chemistry.Team will collect and analyze Reactor Coolant or containment sump samples for pH, and/or dissolved oxygen in accordance with CRC-825 or, if activity levels permit, in accordance with normal plant procedures.

9. The Chemistry Team will collect and analyze Reactor Coolant or containment sump samples for chloride, boron, and/or isotopic mixture in accordance with CRC-826, CRC-827, and/c'r CRC-828, respectively, ox, if activity levels permit, in accordance with normal plant procedures.

10. The Chemistry Team will collect Plant Vent samples in accordance vith CRC-250.

PEP-331 Rev. 3 Page 7 of 8

APROll 9.0 PROCEDURE STEPS (cont'd) ll. The Chemistry Team will prepare and analyze air and plant vent samples for isotopic content in accordance with RCP-660 and RCP-701, respectively.

12. The Chemistry Team will document all sample analysis on appropriate data sheets in accordance with individual procedures. the'espective

13. The Radiological Control Team will obtain Radiation Monitoring System data from local RM-80 panels using the RM-23P in accordance with ERC-117 if individual monitors are operational but the RM-11 consoles are not.

14. The Radiological Control Team will conduct surveys outdoors within the Protected Area in accordance with methods specified in previous steps of this procedure as appropriate to the type of survey, and when directed to do so by the Radiological Control Coordinator. Predetermined survey locations for each of the 16 ma)or compass directions are shown in HPP-005.

15. If area radiation levels and expected sample source terms permit, the Chemistry Team may collect and analyze additional plant system samples using normal plant pro-cedures.

16. The Chemistry Coordinator will monitor chemistry data of the recirculation sump. If addition of sodium hydroxide solution is required, he will take appropriate actions to add the chemical.

17. The Chemistry Team and the Radiological Control Team will control all samples collected in accordance with CRC-829.

18. The Radiological Control Team will conduct surveys of all vehicles exiting the Protected Area in accordance with HPP-075, except for ambulances that are transporting ingured personnel, which will be surveyed after arrival at the hospital.

Note: The Radiological Control Manager may exempt any vehicle exiting the Protected Area from a survey upon recommendation by the, Radiological Control Coordinator.

10.0 DIAGRAMS/ATTACHMENTS None Applicable PEP-331 Rev. 3 Page 8 of 8

MAY 2 1 1986 DATE Procedure

Title:

~C9 /jd4 A

Peeeedure Number: g E (I L I Revision Temporary Change Advance Change INSTRUCTIONS FOR UPDATING DOCUMENTATION DELETE:

Revision The pages on the List Of Effective Pages denoted by A/C Other:

ADD:

The attached procedure to Volume " , Part in sequential order.

~ front of The attached pages in their place; put the the procedure.

Advance Change form in Place the Temporary Change in front of the procedure.

Other:

DOCUMENT SERVICES ADMINISTRATIVE LIBRARY PROCEDURES ZONE 1

OS1 ADVANCE CHANGE FORM (3) Prot. Do[El 3 II Rev. 2- Change 6 /I ~ ~/

(2) Title ()<<uQ l ota C.oldu /n~i'eve (3) Reason Eor the Change Cb.rv 6'.cf 4p t <<~ << lt: I R, mr-5

4) Despription oE the Change End,ydhy n fess/8 OSe ( '.~T V 8 rS 'O (5) Additional pages At ached 8 of Pages (6) Prepared by /5 ad'6 g A/4(S Date 0 /5 -darfo Na itle

-(7) Recommended for approval:- s emergor,;y Preg"'afodnes Date p />

1st echnical Reviewer Signature Title 2nd Tech 'cal

<<~ <<< .

Reviewer Signature Title

<<<</~E.W Date ~ /J=tC (8) SAFETY REVIEM Two qualified safety reviews are required prior to Final Approval. Attach Nuclear Safety Review Checklist in Accordance with AP-011.

(9) ALARA concurypnce if applicable Signature b/E~A 7"~~ Date 5 /5-Z=

(10) Fire Protection concurrenc if applicable Signature / Date

) s if applicab e Signature Date (12) FINAL APPROVAL Approved lb 3

l8 The ~ E )4 Remarks (Form AP-07-4-3)

{jt.Ci- 'l) (- g MAY 2 1198o

~OCyPB<T SERVlCcS

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PEP-34l Rev. 2 Page ii of 22

Procedure

Title:

RV%CYA of 2G5L

~Sf' F'Q Pwa.'rocedure Number: 0 D PEP 34B Revision Temporary Change Advance Change / l INSTRUCTIONS FOR UPDATING DOCUMENTATION DELETE:

Revision X The pages on the List Of Effective Pages denoted by A/C II Other:

ADD:

The attached procedure to Volume, Part in sequential order.

The attached pages in their place; put the Advance Change form in front of the procedure.

Place the Temporary Change in front of the procedure.

Other:

DOCUMENT SERVICES ADMINISTRATIVE LIBRARY PROCEDURES ZONE 1

OS1 ADVANCE CHANCE FORt (3) Proc. No EP 3-f3 Res. P Change (r Zl I (2) Title,uq fOW< re n f W 4'CS8 D

t) Cr<( 7/6n 8) l PC (3) Reason for the Change 8 Nrs P ( P ESCTff(/5 rcr (4) /lDescription of the Change C Lc C.+HA 8 .8 .0r /j 'dr rd"A1 r 8 a J

+C Rr(ov O/fr o OO~46 fa'/r o O dr iv (5) Additional pages Atcached r) of pages~

(6) Prepared hyT C- '

9 ~ ~

XI/c r l /f /rid/5 Date~NB Z/n Nagfe'/Title (7) Recommende or approval:

1s c +~~M T/chnical Reviewer Signature Title'~~ad~

r ~ /~C + Date MS7 cf"(o

/a<c Emel()ency Preparedness D t cp g~ (rQ 2nd Technical Reviewer Signature Title (8) SAFETY REVIEW Two qualified safety reviews are required pr'r to Final Approval. Attach Nuclear Safety Review Checklist in Accordance with AP-011.

(9) ALARA concu. n ncg if pljcab e Signature Date 5 K7 Gb (10) Fire Protection concurren e if applicable Signature Date

) s if applicable Signature Date (12) FINAL APPROVAL Approved ( 4 D..Z ZF'I'f$

bp'emarks ft()IL ft II'DIj))I(";

(Form AP-07-4-3) RECEIVED JUN 0 0 'igS6 OOCUtaEVT HER'ljCES

APR015 LIST OF EFFECTIVE PAGES

~Pa e Revision land 2 3 3 and 4 3/1 5 3 6 3/1 7 and 8 3 9 through 13 3/1 14 and 15 3

?"=?-3<3 3ev. 3 ~age 3 oc 15

APR015 8~0 SPECIAL TOOLS AND UIPMENT (Continued)

NOTE: Other hardvare configurations may be used after verifying that the programs will run properly. The programs are written such that hardware incompatibility vill only prevent the programs from running, not produce errors in output.

2. Program diskette, SHNPP Emergency Dose Projections, bc 9/t Version 1.1, 5/19/86 S-zv-S 9.0 PROCEDURE STEPS CAUTION When obtained from the Emergency Response Facilities Information System (ERFIS), Main Steam Line flov is in units of thousand pounds mass per hour (KPPH) instead of million pounds mass per hour (MPPH),

Steam flov in KPPH must be converted to MPPH by dividing by 1000.

Additionally, ERFIS displays stability class as a numeric integer (1> 2, 3, etc.) instead of an alpha character (A, B, C, etc.).

ERFIS stability class 1 A, 2 B, 3 C, 4 D, 5 ~ E, 6 F, and 7 ~ G.

Obtain the necessary data required for input to 'the program using Form PEP-343-2 as guidance. All of the necessary information except for hours since reactor shutdovn can be obtained from ERFIS group data display 3DOSE or 4DOSEHEL.

2. Load the Dose Projection Disk into the disk drive 'A'nd close the disk drive door. While simultaneously holding dovn the ALT and CTRL keys, press the DEL key. This vill reset the computer, load the dose projection program, and start the program.

3. After a short pause, the screen vill clear and the introduction to the dose projection program vill be displayed. The displayed version and revision date shall be compared to that listed in Section 8 of this procedure, and if they are not the same, the program disk shall not be used to perform dose projections. As instructed, press any key to continue.

4 ~ Follov the computer prompts and ansver each question as it is asked.

NOTE: "Reference Time/Date" on printouts and displays is the time and date at vhich the dose projection vas performed.

NOTE: When a Yes or No ansver is required, Y and N should be used.

PEP-343 Rev. 3 Page 6 of 15

~ ~

APR015 Page 4 of 7

ATTACHMENT 1 EXAMPLE DOSE PROJECTION Summary of Inputs to Release Rate Analysis  :

Time since reactor shutdmm = 4 Hours. Time until release begins = 0 Hours.

Time since accident began = 4 Hours.

I. Steam Lines Flow {MLbm/Hr) Monitor (mR/Hr) Pressure {PSI) Grab Sample A .4 200 1100 N B .3 250 1100 N C 7 NA NA NA II. Plant Stacks Rad Monitor (uCi/sec) Grab Sample 1 270000 CFM Y 5 5. 15e7 N 5A N III. Containment Hrs. Since Accident 4" Rad Monitor (R/Hr) Grab Sample

~

le8 N Results of Release Rate Analysis:

Release Pathway Whole Body Thyroid (Ci/sec) {Ci/sec)

Main Steam Line A 2.5498+00 4.4998"Ol

. Main Steam Main Steam Vent Stack Line Line 1

C B

{Aux. Bldg.)

2.3908+00 0.0008+00 5.9778+00 4.2188-01 0.0008+00 5.7798-02 Vent Stack 5 {WPB Filtered}  : 5.1508+01 9.088E+00 Vent Stack 5A (WPB Unfiltered) 0.0008+00 O.OOOE+00 Containment I,eakage 6.940E+Ol 1.225E+Ol Grand Total Release Rate All Pathways: 1.3188+02 2.2278+01 Total Thyroid DCF = 1.1088+06 Total Whole Body DCF = 1.4888+02

... both at point of release.

Reference Time/Date: 07:54:17 / 05-27-1986 Summary of Inputs to Release Rate Analysis Time since reactor shutdown = 4 Hours, Time until release begins = 0 Hours.

Time since accident began = 4 Hours.

Steam Lines Flow (MIbm/Hr) Monitor (mR/Hr) Pressure (PSI) Grab Sample A ~ 4 200 1100 N B .3 250 1100 N C NA NA NA II. Plant Stacks Rad Monitor (uCi/sec) Grab Sample 1 270000 CFM 7 Y 5 5. 15e7 N 5A 7 N III. Containment Hrs. Since Accident Rad Monitor (R/Hr) Grab Sample 4 le7 N PEP-343 Rev. 3 Page 11 of 15

APRO15 Page 5 of 7 ATTACHMENT 1 EXAMPLE DOSE PROJECTION Results of Release Rate Analysis:

Release Pathway Whole Body Thyroid (Ci/sec) (Ci/sec)

Main Steam Line A 2.549E+00 4.499E-Ol Main Steam Line B 2.390E+00 4.218E-01 Main Steam Line C O.OOOE+00 0.000E+00 Vent Stack 1 (Aux. Bldg.) 5.977E+00 5.779E-02 Vent Stack 5 (WPB Filtered) 5.150E+Ol 9.088E+00 Vent Stack 5A (WPB .Unfiltered) O.OOOE+00 O.OOOE+00 Containment Leakage  : 6.94OE+00 1.225E+00 Grand Total Release Rate All Pathways: 6.936E+Ol 1.124E+Ol Total Thyroid DCF = 1.108E+06 Total Whole Body DCF = 1.488E+02

... both at point of release.

Reference Time/Date: 07:54:17 / 05-27-1986 Summary of relevant Meteorological Data:

Meteorological data obtained from ERFIS.

Pasquill Stability Class : C Lower Wind Speed : 5.0 MPH Lower Wind Direction  : 215 Degrees (Blowing From)

Reference Time/Date  : 08:09:57 / 05-27-1986 Summary Dose Projection:

Estimated Duration of Release: 2 Hours PEP-343 Rev. 3 Page 12 of 15

APR015 Page 6 of 7 ATTACHMENT 1 EXAMPLE DOSE PROJECTION

-Distance (Km/Mi)

N. B.

St (Rem)

~ose Thyroid (Rem)

W. B. Thyroid Bose-Bete-Dose-Bete (Rem/Hr) (Rem/Hr)

DCFs (mes/3!s-V (Ci/m"3)

W. B. Thyroid Chi/Q 1.6/ 1.00 0.1935 233.5855 116. 7928 1.49E+02 1.11E+06 9.38E-06 4 '/

3.2/ 2.00 3.00 6.4/ 4.00 0.0550 66.4274 0.0264 31.8346 0.0157 18.8907

33. 2137 15.9173 9.4454 1.49E+02 1.49E+02 1.49E+02 1.11E+06 1.11E+06 1.11E+06 2.67E-06 1.28E-06 7.58K-07 8.0/ 5.00 0.0104 12.6021 6.3011 1.49E+02 1.11E+06 5.06E-07 9-6/ 6.00 0.0075 , 9.0532 4.5266 1.49E+02 1.11E+06 3.63E-07 11.3/ 7.00 0.0057 6.8447 3.4223 1.49E+02 1.11E+06 2.75E-07 12.9/ 8.00 0.0045 5.3722 2.6861 1.49E+02 1.11E+06 2.16E-07 14.5/ 9.00 0.0036 4.3387 2.1693 1.49E+02'.11E+06 1.74E-07 16.1/10.00 0.0030 3.5838 1.7919 1.49E+02 1.11E+06 1.44E-07 5 REM THYROID ISOPLETH COORDINATES (+/- METERS)

X Y 1608 404 3216 586 4824 661 6432 636 8040 469

. 00057 REM WHOLE BODY ISOPLETH COORDINATES (+/- METERS)

X Y 1608 516 3216 839 4824 1090 6432 1290 8040 1452 9648 1578 11256 1674 12864 1740 14472 1777 16080 1785 PEP-343 Rev. 3 Page 13 of 15

MAY 21 j986 DATE J

Procedure

Title:

Procedure Number: CX I B ~~ (Z Revision Ci Temporary Change Advance Change INSTRUCTIONS FOR UPDATING DOCUMENTATION DELETE:

Revision The pages on the List Of Effective P

Pages denoted by A/C Other:

~

ADD:

The attached procedure to Volume~0'he Part in sequential order.

attached pages in their place; put the Advance Change form in front of the procedure.

Place the Temporary Change in front of the procedure.

Other:

DOCUMENT SERVICES ADMINISTRATIVE LIBRARY PROCEDURES ZONE 1

WKKF07 LIST OF EFFECTIVE PAGES

~Pa e Revision

1. through 10 0 PEP-372 Rev. 0 Page 2 of 10

MKKF07 1.0 PURPOSE The purpose of this procedure is to partially implement section 4.6.2 (c) "Evacuation & Personnel Accountability" of the SHNPP Emergency Plan which is a regulatory commitment.

This procedure describes the use of the Cape Fear plant facilities as a remote area for monitoring and decontamination of evacuated SHNPP site personnel.

2.0 REFERENCES

2.1 Emer enc Plan References

1. Section 4.6.2, "Evacuation and Personnel Accountability" 2.2 Other References

1. HPP-035, "Posting and Barricading of Radiological Areas"

2. HPP-060, "Performance of Radiation and Contamination Surveys

3. HPP-075, "Vehicle Survey"

4. HPP-251, "Personnel'Wecontamination"

5. HPP>>252, "Tool and Personal Belonging Decontamination"

6. HPP-253, "Area Decontamination" 3.0 RESPONSIBILITIES 3.1 Radiolo ical Control Coordinator The Radiological Control Coordinator is responsible for dispatching I

a radiological control team with decontamination personnel to the Cape Fear Plant in the event -that the facility is determined to be a remote monitoring/decontamination area. The Radiological Control Coordinator shall determine if decontamination of any affected Cape Fear facilities and grounds is complete for unrestricted public use.

3.2 Radiolo ical Control Team The Radiological Control Team is responsible for monitoring all affected personnel, vehicles, facilities and grounds for contamination and shall direct decontamination as necessary. The Radiological Control Team shall control access and egress as necessary at th'e monitoring/decontamination area to ensure control of contamination.

PEP-372 Rev. 0 Page 4 of 10

VKKF07 9.2 Monitorin /Decontamination 0 erations (continued)

2. The Radiological Control Team will survey arriving evacuated personnel for contamination in accordance with HPP-251 prior to releasing them from the Restricted Area.

3. The Radiological Control Team will survey evacuated vehicles in accordance with HPP-075 prior to release of the vehicles from the Restricted Area.

4. The Radiological Control Team will maintain a record of personnel names and vehicle license plates surveyed for historical record.

5. Contaminated personnel and/or vehicles drive to the decontamination station set up adjacent to the employees parking lot.'.

Decontamination personnel on the Radiological Control Team decontaminate vehicles at the decontamination station in accordance with HPP-252. Contaminated personnel will be decontaminated in accordance with HPP-251. The men and women's shower facility inside the Cape Fear Plant may be used for personnel decontamination.

NOTE: Ef the showers are used; wastewater from the showers drains to the septic system. Sampling would be difficult, but possible. The septic system consists of a septic tank and leaching field. Contact the Environmental Supervisor if this is done.

7. Areas contaminated by the evacuated personnel and/or vehicles will be surveyed and decontaminated as necessary in accordance with HPP-253.

8. Coveralls will be provided to decontaminated evacuees to replace contaminated clothing. The Radiological Control Director may request the coveralls from the Radiological Control Manager which are supplied out of the Emergency Reserve Health Physics equipment inventory.

9. The Environmental Supervisor will arrange for the radionuclide sampling and analysis of water from decontamination efforts.

10. The Environmental Supervisor will recommend the appropriate disposal of the decontamination water.

PEP-372 Rev. 0 Page 8 of 10

Procedure

Title:

EM d 7 /4 > AJ. c Art. c V ~'J' Procedure Number: V~ c'y~n,'emporary Revision Change Advance Change INSTRUCTIONS FOR UPDATING DOCUMENTATION DELETE:

Revision The pages on the List Of Effective Pages denoted by A/C Other:

ADD:

The attached procedure to Volum , Part in sequential order.

The attached pages in their place; put the Advance Change form in front of the procedure.

Place the Temporary Change in front of the procedure.

Other:

DOCUMENT SERVICES ADMINISTRATIVE LIBRARY PROCEDURES ZONE 1

WKKF07"'IST OF EFFECTIVE PAGES

~Pa e Revision 1 tiirough 9 0 PEP-373 Rev. 0 Page 2 of 9

WKKF07 1.0 PURPOSE The purpose of this procedure is to partially implement Section 4.6.2(c) "Evacuation and Personnel Accountability" of the SHNPP Emergency Plant which is a regulatory commitment.

This procedure describes the use of the Harris Energy &

Environmental Center facilities as a remote area for monitoring and decontamination of evacuated SHNPP site personnel.

2.0 REFERENCES

2.1 Emer enc Plan References

1. Section 4.6.2, "Evacuation and Personnel Accountability" 2.2 Other References HPP-035, "Posting and Barricading of Radiological Areas"

2. HPP-060,, "Performance of Radiation and Contamination Surveys"

3. HPP-075, "Vehicle- Survey"

4. HPP-251, "Personnel Decontamination

5. HPP-252,, "Tool and Personal Belongings Decontamination"

6. HPP-253, "Area: Decontamination" 3.0 RESPONSXB1LETlES 3.1 Radiolo ical Control Coordinator ~I The Radiological Control Coordinator is responsible for dispatching a Radiological Control Team with decontamination personnel to the Harris Energy & Environmental Center in the event that the facility is determined to be a remote monitoring/decontamination area. The Radiological Control Coordinator shall determine if decontamination of any affected Harris Energy & Environmental Center facilities and grounds is complete .for unrestricted public use.

I 3.2 Radiolo ical Control Team The Radiological Control Team is responsible for monitoring all affected personnel, vehicles, facilities and grounds for contamination and shall decontaminate as necessary. The Radiological Control Team shall control access and egress as necessary at the monitoring/decontamination area to ensure control of contamination.

PEP-373 Rev. 0 Page 4 of 9

9.1 Activation of the Harris Ener & Environmental Center Monitorin /Decontamination Area (continued)

NOTE: The Environmental Monitoring Radio channel is heavily used in an emergency. Any radio traffic between the Radiological Control Coordinator and his team is secondary to, and must yield to, Environmental Monitoring Radio traffic.

3~ The Radiological Control Teams establish roped areas and traffic lanes at the intersection with State Road 1127 for controlling traffic and monitoring vehicles and personnel.

Any potentially contaminated areas, such as the grassy area west of State Road 1127, should be posted in accordance with HPP-035. (See Attachment 1.)

4. Assembly Area Leaders instruct evacuating personnel to evacuate to the Harris Energy & Environmental Center to be monitored for contamination.

9.2 Monitorin /Decontamination 0 erations Evacuees arriving at the intersection with State Road 1127 park in place along State Road 1135 and wait for a monitoring team perssrCto survey them and their vehicles.

The assembly area leaders assist in directing traffic and controlling personnel.

2. The Radiological Contx'ol Team will survey arriving evacuated personnel for contamination in accordance with HPP-251 prior to releasing them from the Restricted Area.

3~ The Radiological Control Team will survey evacuated vehicles in accordance with HPP-075 prior to release of the vehicles from the Restricted Area.

NOTE: If a large number of evacuees are present and require monitoring, request through the Radiological Control Director that the Logistics Suppox't Director obtain tents and portable lighting and heaters as necessary for an enclosed, dry area for monitoring.

4. The= Radiological Control Team will maintain a record of personnel names and vehicle license plates surveyed for historical record.

5. Contaminated vehicles are to be driven and parked over the grassy area adjacent to State Road 1127 between State Road

. 1135 and and the Center. These vehicles will remain in place until they have been decontaminated and determined to be free of contamination in accoxdance with HPP-075.

Contaminated evacuees are led to the Craft Training Building behind the Harris Energy & Environmental Center ~

and are decontaminated in accordance with HPP-251. The men and women's shower facility inside the Craft Tx'aining Building may be used for pexsonnel decontamination.

PEP-373 Rev. 0 'Page 7 of 9

LIST OF EFFECTIVE PACES

~Pa e Revision 1 through 12 z/i

" 4 Pe~f+ ~

FEP-403 Rev. 2/~ Page 3 o 12

2.3 Other References << ~

1. Title 10, Code of Federal Re ulations, Parg 50, Section 50.47, "Emergency Plans 'i 2; Title 10, Code of Federal Re ulati'ons, Part 50., Sect'ion 50.54(q), Conditions of License

3. Title 10, Code of Federal Re ulations, Part 50, Appendix "Emergency Planning and Preparedness for Production and Utilization Facilities"

4. NUREG-0654, FEMA-REP-l, Revision 1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," November. 1980

5. SHNPP Technical Specifications

6. SHNPP Security Personnel Tr'aining and Qualification Plan

7. TI-105, "Fire Protection Training"

8. TI-302, "Emergency Plan Training"

9. CCEIP-10, "Training,'andi'.Retraining" 3.0 RESPONSIBILITIES ~+P4;;-'

3.1 Plant 'General Mana er The Plant General Manager ensures that SHNPP Emergency Plan Training and Retraining is performed in a complete and,timely manner. He also provides for corrections of deficiencies noted as a result of .

training-related functions, and approves all lesson plans.

3 2, Assistant. to the Plant General. Mana er The Assistant to".the Plant, General Manager.'i's the SHNPP- Emergency Planning Coordinator. He is responsible for identifying off-site training needs of state and local emergency support personnel and arranging for. training to meet the identified needs, and for other training-related functus ons as shown on Attachment 1 3 3- Director Trainin (Harris Trainin Uni.t),

The Director Training is responsible for developing plans, procedures and instructional material as required to fulfill the responsibilit'ies 1'isted in Attachment 1, and in the references listed above.. TI-302,',, "Emergency Plan Training,." further delineates the duties and functions of.'he. Director-Training (Harris Training Unit)..

PEP-403. Rev; 2 Page 5 of 12 r

KI( A Fl&~r<< ~j~~~cgggpvA<~<<@ p <<<<++D~ ~+jp pM/~egg q@ <<JI ~pm gPI 51, qugg<<~ j

~ ~

kTQCRNNT- I Sheet 2 of 2 ONRCKNCf RAN TRAISIlC ONRSE RESNNSIRILITXES

+ ~

Responsible for Traiaiags: .

Nsaeger ' Eaergeacy Prspertdness,"pe j 20 hesistant to'the'leat Ceneral Manager, SHRPP/Senior Specielist-taargency Preparedness,. SUPP 3i Oirector - Traiaing, Harris Traiaiag %jt '

LL Seaior Pire Protection Specialist,, SHMPP .

5 Seaior Security Specialist, SHHPP

6. News Coordinator, Corporate Communicat;ions Department Za the coluaas under the heading RESPONSZSZLITV AREA, Sheet 1~ the mabers ia the aatrix refer to the above Listing of persons responsible for training Mhere oe aeabers are listed the first individual shown ia the col~ has lead responsiblity

~ !

.'! S C L

P~03 Rev 2'/1 Page 12 oE LX KCge> <<~!g~NVW>~!!9!ggP~+iPV~i'+kg~~>+~rPfQgW<<!~'y~5LL<<L+a~~g~iWt'<<'i'5>>~gg'if~gehg'<LLfq>L+L g+'g<(~~PW4L>>>>itga~i~4~~,t~>gPq455W>y)4'5!L Cr!!,

ATTACHMENT 20 FORM 1: ISOTOPE RELEASE WORKSHEET A

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.158 1.0 1..7x107 Kr-85m S .158 1.0 1.7x10 7

.158 1.0 1 7x107 TOTAL

.547 1.0 3.2x107 Kr-87 8 .547 1.0 3.2x1'07

.547 1.0 3.2x10 7 TOTAL

.248 1.0 4.4x107 Kr-88 S .248 1.0 4.4x10 7

.248 1.0 4.4x10 7 TOTAL R 1-131 .00245 .00359 .008 7.7x107 4.9x10 5 4.9x10 5 Xe-131m 6 I-131 ..00245 .00359 .008 7.7x 107 4.9x10 5 4.9x105 A'-131 .00245 .00359 .008 7.7x10 4.9x105 4.9x10 5 TOTAL R 1-1 33 .00548 .0341 .976 1.5x108 1.5x108 1.5x10 8 e 133 .00548 .0128 1.0 2.2x10 1.5x108 Xe-133 8 I-133 .00548 .0341 .976 1.5x10 1.5x1 0 1.5x10 8

'-133 .00548 .0128 1.0 2.2x10 7 1.5x1 0 8 A'-133 .00548 .0341 .976 1.5x108 1.5xl 0 1.5x108 e 133 .00548 .0128 1.0 2.2x 107 1.5x108 TOTAL R .0128 .0341 .024 1.5x108 2.2x10 7 2.2x107 I-133 I-133'e-133m S .0128 .0341 .024 1.5x10 2.2x10 2.2x107 A I-1'33 .0128 .0341 .024 1.5x1 ~ 2.2x10 2.2x107 TOTAL R e-135 .0728 2.67 1.0 3.3x107 2 9x107 2.9x107 1-135 .0728 .104 .70 1.3x 108 2.9x107 Xe-135 8 ( e-135 .0'728 2.67 1.0 3.3x 107 2.9x107 2.9x107 1-135 .0728 .104 .70 1.3x1 08 2.9x1 07 A i e-135 .0728 2.67 1.0 3.3x107 2.9x10 7 2.9x107 I-135 .0728 .104 .70 1.3x10 2..9x 10 TOTAL

.00359 1.0 7.7x10 7 I-131 8 .00359 1.0 7.7x107

.00359 1..0 7.7x10 7 TOTAL R Te-132 .307 .00892 1.0 1.1x108 1.1x108 1.1x10 8 1-132 6 Te-132 .307 .00892 1.0 1.1x10. 1.1x10 1.1x108 A Te-132 .307 .00892 1.0 1.1x10 1.1x108 1.1xl08 TOTAL

.0341 1.0 1.5x10 8 1-133 .0341 1.0 1.5x108

.0341 1.0 1.5x108 TOTAL

.104 1.0 1.3x10 8 I-1 35 .104 1.0 1.3x10

.104 1..0 1.3x10 TOTAL R Kr-88 2.34 .248 1.0 4.4x107 4.5x10 7 4.5x107 Rb-88 S Kr-88 2.34. .248 1.0'.4 x1 0 4.5x107 4.5x107 A Kr-88 2.34 .248 1.0 4.4x10 4.5x107 4.5x 107 Cs-134 Cs-137 S

S 3.96x10 3.96x10 3.96x10 2.6 4x 10 6 2.64x10 5

1.0'.8x107 1.0 1.0 1.0'.0 1.0 1.8x10 1.8x107 8.3x 10 6 8.3x10 7

TOTAL TOTAL'OTAL 2.64x1'0 8.3x106 R Sb-129 .605 .161 2.5x107 2.6x107 2.6x107 e-129 .605 8.47x10 .680 6.2x10 2.6x107 Te-129 8 Sb" 129 .605 .161 .827 2.5x10 2.6x1 07 2.6x107 e-12'9 .605 8.47x10 .680 2.6x107 6.2x10'.5x10 A Sb-129 2.6x10 6.2x10'827

,605 .161 .827 2.6x107 e-129 .605 8.47x10 .680 2.6x107 TOTAL

.00892 1.0 1.1x10 8 Te-132 S .00892 1.0 1.1x10 8

.00892 1.0 1.1x1'08 TOTAL 5.48x1 0 4 1.0 6.1x10 7 Sr-89 S 5.48x1 0 1..0 6.1x107 5.48x10 1.0 6.1x10 7 TOTAL 2.83x1 0 1.0 5.6x108 Sr-90 6 2.83x10 1.0 5.6x108 2.83x10 5.6x10 1.0'.0 TOTAL

.00226 1.3x 108 Ba-140 8 .00226 1.0 1.3x10 8

.00226 1.0 1.3x 108 TOTAL R Ba-140 .0172 .00226 1.0 1.3x10 1.3x108 1.3x108 La-140 S Ba-140 .0172 .00226 1.0 1.3x10 1..3x108 1.3x 108 A Ba-140 .0172 .00226 1.0 1.3x10 1.3x108 1.3x108 TOTAL R Ba-142 .450 3.78 1.0 1.2x108 1.1 XI 08 1.1x108 La-142 8 Ba-142 .450 3.78 1.0 f,gxf0 8 1.1x10 A Ba-142 .450 3.78 1.0 . xIO 1.1x 108 1.1x108 TOTAL R Ce-144 2.41 1.02x10 4 1.0 8.3x)g 7 9.6x107 9.6x107 Pr-144 S Ce-144 2.41 1.02x10 1.0 8.3x107 9.6x107 9.6x107 A Ce-144 2.41 1.02x10 1.0 8.3x10 9.6x107 9.6x10 TOTAL PEP-362 Rev. 0 ATTACHMENT 20 FORM 1: ISOTOPE RELEASE WORKSHEET PEP-362 Rev. 0 Page 34 of 41 8'CVI70598-os Tf

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